Publications Fuel Cycle / FUSION

Here you find TLK publications related to the topics Fuel Cycle and FUSION.


2022
Status of maturation of critical technologies and systems design: Breeding blanket
Boccaccini, L. V.; Arbeiter, F.; Arena, P.; Aubert, J.; Bühler, L.; Cristescu, I.; Nevo, A. D.; Eboli, M.; Forest, L.; Harrington, C.; Hernandez, F.; Knitter, R.; Neuberger, H.; Rapisarda, D.; Sardain, P.; Spagnuolo, G. A.; Utili, M.; Vala, L.; Venturini, A.; Vladimirov, P.; Zhou, G.
2022. Fusion Engineering and Design, 179, Art.Nr. 113116. doi:10.1016/j.fusengdes.2022.113116
Probing the Neutrino-Mass Scale with the KATRIN Experiment
Lokhov, A.; Mertens, S.; Parno, D. S.; Schlösser, M.; Valerius, K.
2022. Annual Review of Nuclear and Particle Science, 72, 259–282. doi:10.1146/annurev-nucl-101920-113013
2020
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems
Cismondi, F.; Spagnuolo, G. A.; Boccaccini, L. V.; Chiovaro, P.; Ciattaglia, S.; Cristescu, I.; Day, C.; Del Nevo, A.; Di Maio, P. A.; Federici, G.; Hernandez, F.; Moreno, C.; Moscato, I.; Pereslavtsev, P.; Rapisarda, D.; Santucci, A.; Utili, M.
2020. Fusion engineering and design, 157, 111640. doi:10.1016/j.fusengdes.2020.111640
Tritium Processing Systems and First Tritium Operation of the KATRIN Experiment
Priester, F.; Hillesheimer, D.; Marsteller, A.; Röllig, M.; Sturm, M.
2020. Fusion science and technology, 76 (4), 600–604. doi:10.1080/15361055.2020.1730118
Minimal and complete set of descriptors for IR-absorption spectra of liquid H2–D2 mixtures
Grössle, R.; Bornschein, B.; Kraus, A.; Mirz, S.; Wozniewski, S.
2020. AIP Advances, 10 (5), Article no: 055108. doi:10.1063/1.5111000
Precision measurement of the fundamental vibrational frequencies of tritium-bearing hydrogen molecules: T, DT, HT
Lai, K.-F.; Hermann, V.; Trivikram, T. M.; Diouf, M.; Schlösser, M.; Ubachs, W.; Salumbides, E. J.
2020. Physical chemistry, chemical physics, 22 (16), 8973–8987. doi:10.1039/d0cp00596g
Material Studies to Reduce the Tritium Memory Effect in BIXS Analytic Systems
Aker, M.; Röllig, M.
2020. Fusion science and technology, 76 (3), 373–378. doi:10.1080/15361055.2020.1712989
Tritium Supply and Processing for the First KATRIN Tritium Operation
Welte, S.; Sturm, M.; Hillesheimer, D.; Le, L. T.; Schäfer, S.; Fanghänel, E.; Priester, F.; Marsteller, A.
2020. Fusion science and technology, 76 (3), 227–231. doi:10.1080/15361055.2019.1705681
The fundamental ν3 band of DTO and the 2ν1 overtone band of HTO from the analysis of a high-resolution spectrum of tritiated water vapour
Reinking, J.; Hermann, V.; Müller, J.; Schlösser, M.; Hase, F.; Orphal, J.
2020. Journal of molecular spectroscopy, 370, Art. Nr.: 111295. doi:10.1016/j.jms.2020.111295
Recent advances in tritium modeling and its implications on tritium management for outer fuel cycle
Ying, A.; Riva, M.; Ahn, M.-Y.; Moreno, C.; Cristescu, I.
2020. Fusion engineering and design, 161, Art.Nr. 111895. doi:10.1016/j.fusengdes.2020.111895
Developments on the tritium extraction and recovery system for HCPB
Cristescu, I.; Draghia, M.
2020. Fusion engineering and design, 158, Article: 111558. doi:10.1016/j.fusengdes.2020.111558
Overview of the Tritium Technologies for the EU DEMO Breeding Blanket
Cristescu, I.; Priester, F.; Rapisarda, D.; Santucci, A.; Utili, M.
2020. Fusion science and technology, 76 (4), 446–457. doi:10.1080/15361055.2020.1716456
Concentrated Nonequilibrium HD for the Cross Calibration of Hydrogen Isotopologue Analytics
Mirz, S.; Brunst, T.; Größle, R.; Krasch, B.
2020. Fusion science and technology, 76 (3), 284–290. doi:10.1080/15361055.2020.1711688
Isotopic effects on the permeation of all hydrogen isotopologues through MFI-ZSM-5 zeolite membranes
Antunes, R.; Böhmländer, A.; Cruz, M. M.; Frances, L.; Hillesheimer, D.; Krasch, B.; Welte, S.
2020. International journal of hydrogen energy, 45 (3), 2009–2016. doi:10.1016/j.ijhydene.2019.11.099
2019
Modelling synergistic isotope effects of the permeation of multiple hydrogen isotopes through metals
Bidica, N.; Cristescu, I.; Carcadea, E.; Bornea, A.; Bucur, C.; Sofilca, N.; Lazar, A.
2019. Fusion engineering and design, 146 (Part B, SI), 1938–1941. doi:10.1016/j.fusengdes.2019.03.071
Micro ion beam analysis for the erosion of beryllium marker tiles in a tokamak limiter
JET Contributors; Zhou, Y.; Bergsaker, H.; Bykov, I.; Petersson, P.; Paneta, V.; Possnert, G.; Romanelli, F.; Abhangi, M.; Abreu, P.; Aftanas, M.; Afzal, M.; Aggarwal, K. M.; Aho-Mantila, L.; Ahonen, E.; Aints, M.; Airila, M.; Albanese, R.; Alegre, D.; Alessi, E.; Aleynikov, P.; Alfier, A.; Alkseev, A.; Allan, P.; Almaviva, S.; Wendel, J.; Welte, S.; Michling, R.; Cristescu, I.; Bekris, N.; et al.
2019. Nuclear instruments & methods in physics research / B, 450, 200–204. doi:10.1016/j.nimb.2018.08.028
Custom-built light-pipe cell for high-resolution infrared absorption spectroscopy of tritiated water vapor and other hazardous gases
Müller, J.; Schlösser, M.; Hase, F.; Ziegler, N.; Grössle, R.; Hillesheimer, D.; Orphal, J.
2019. Optics express, 27 (12), 17251–17261. doi:10.1364/OE.27.017251
Numerical study and experimental verification of protium permeation through Pd/Ag membranes for fusion applications
Antunes, R.; Frances, L.; Incelli, M.; Santucci, A.
2019. Fusion engineering and design, 146A, 1286–1290. doi:10.1016/j.fusengdes.2019.02.060
First high-resolution spectrum and line-by-line analysis of the 2ν band of HTO around 3.8 microns
Reinking, J.; Schlösser, M.; Hase, F.; Orphal, J.
2019. Journal of quantitative spectroscopy & radiative transfer, 230, 61–64. doi:10.1016/j.jqsrt.2019.03.017
2018
Experimental investigation of the ideal selectivity of MFI-ZSM-5 zeolite-type membranes for a first evaluation of the separation of hydrogen isotopologues from helium
Antunes, R.; Böhmländer, A.; Bükki-Deme, A.; Krasch, B.; Cruz, M. M.; Frances, L.
2018. Separation and purification technology, 212, 767–773. doi:10.1016/j.seppur.2018.11.088
Compatibility test of common electronics with gaseous tritium
Priester, F.
2018. Fusion engineering and design, 136, 608–611. doi:10.1016/j.fusengdes.2018.03.037
Gaseous Kr-83m generator for KATRIN
Sentkerestiová, J.; Dragoun, O.; Lebeda, O.; Ryšavý, M.; Sturm, M.; Vénos, D.
2018. Journal of Instrumentation, 13 (4), Art. Nr.: P04018. doi:10.1088/1748-0221/13/04/P04018
Overview of the HCPB research activities in EUROfusion
Hernandez, F. A.; Arbeiter, F.; Boccaccini, L. V.; Bubelis, E.; Chakin, V. P.; Cristescu, I.; Ghidersa, B. E.; Gonzalez, M.; Hering, W.; Hernandez, T.; Jin, X. Z.; Kamlah, M.; Kiss, B.; Knitter, R.; Kolb, M. H. H.; Kurinskiy, P.; Leys, O.; Maione, I. A.; Moscardini, M.; Nadasi, G.; Neuberger, H.; Pereslavtsev, P.; Pupeschi, S.; Rolli, R.; Ruck, S.; Spagnuolo, G. A.; Vladimirov, P. V.; Zeile, C.; Zhou, G.
2018. IEEE transactions on plasma science, 46 (9), 2247–2261. doi:10.1109/TPS.2018.2830813
Liquid scintillation. Mesuring procedures, new developments
Möbius, S.; Erat, S.; Möbius, R.; Möbius, T.; Santiago, L.; Taracon, A.; Wendel, J.; Wisser, S.
2018. Karlsruher Institut für Technologie (KIT)
2017
Tritium Behavior in HCPB Breeder Blanket Unit: Modeling and Experiments
Carella, E.; Moreno, C.; Urgorri, F. R.; Demange, D.; Castellanos, J.; Rapisarda, D.
2017. Fusion science and technology, 71, 357–362. doi:10.1080/15361055.2017.1289584
Tritium accountancy and relevant instrumentation for the WDF from Cernavoda NPP
Draghia, M. M.; Cristescu, I.; Trantea, N.; Pasca, G.; Fuciu, A.
2017. Fusion science and technology, 71 (4), 654–659. doi:10.1080/15361055.2017.1290947
Tritium recovery efficiency from an array of PbLi droplets in vacuum
Okino, F.; Frances, L.; Demange, D.; Kasada, R.; Konishi, S.
2017. Fusion science and technology, 71 (4), 575–583. doi:10.1080/15361055.2017.1290972
Design of a Spectroscopy Experiment for All Hydrogen Isotopologues in the Gaseous, Liquid, and Solid Phase
Mirz, S.; Besserer, U.; Bornschein, B.; Groessle, R.; Krasch, B.; Welte, S.
2017. Fusion science and technology, 17 (3), 375–380. doi:10.1080/15361055.2016.1273706
Review of the TLK Activities Related to Water Detritiation, Isotope Separation Based on Cryogenic Distillation and Development of Barriers Against Tritium Permeation
Cristescu, I.; Bukki-Deme, A.; Carr, R.; Gramlich, N.; Groessle, R.; Melzer, C.; Schaefer, P.; Welte, S.
2017. Fusion science and technology, 17 (3), 225–230. doi:10.1080/15361055.2017.1288057
A New Device for Activity Measurement of Tritiated Water
Priester, F.
2017. Fusion science and technology, 71 (4), 600–604. doi:10.1080/15361055.2017.1289585
Experimental Investigation of ZrCo Getter Beds as Candidate Process for the Tritium Extraction Systems of the European Test Blanket Modules
Buekki-Deme, A.; Calderoni, P.; Demange, D.; Fanghaenel, E.; Le, T.-L.; Sirch, M.; Ricapito, I.
2017. Fusion science and technology, 71 (4), 527–531. doi:10.1080/15361055.2017.1288976
2016
TRitium Activity Measurements with a PhotomultipliEr in Liquids–The TRAMPEL experiment
Priester, F.; Klein, M.
2016. Fusion engineering and design, 109-111 (Part B), 1356–1359. doi:10.1016/j.fusengdes.2015.12.027
Numerical analysis of H₂/He gas separation experiments performed with a MFI-type tubular zeolite membrane
Antunes, R.; Borisevich, O.; Demange, D.
2016. Chemical engineering research and design, 109, 327–334. doi:10.1016/j.cherd.2016.02.009
Tritium extraction technologies and DEMO requirements
Demange, D.; Antunes, R.; Borisevich, O.; Frances, L.; Rapisarda, D.; Santucci, A.; Utili, M.
2016. Fusion engineering and design, 109, Part A, 912–916. doi:10.1016/j.fusengdes.2016.01.053
PERMCAT experiments with tritium at high helium flow rates relevant for the tritium extraction systems using the CAPER facility at TLK
Buekki-Deme, A.; Demange, D.; Thanh-Long Le; Fanghaenel, E.; Simon, K.-H.
2016. Fusion engineering and design, 109, Part B, 1331–1334. doi:10.1016/j.fusengdes.2015.12.032
Investigations of the applicability of a new accountancy tool in a closed tritium loop
Ebenhoech, S.; Niemes, S.; Priester, F.; Roellig, M.
2016. Fusion engineering and design, 109, Part B, 1376–1379. doi:10.1016/j.fusengdes.2015.12.018
Advanced design of the Mechanical Tritium Pumping System for JET DTE2
Giegerich, T.; Bekris, N.; Camp, P.; Day, C.; Gethins, M.; Lesnoy, S.; Luo, X.; Müller, R.; Ochoa, S.; Pfeil, P.; Smith, R.; Strobel, H.; Stump, H.
2016. Fusion engineering and design, 109-111, 359–364. doi:10.1016/j.fusengdes.2016.02.098
Model and simulation of a vacuum sieve tray for T extraction from liquid PbLi breeding blankets
Mertens, M. A. J.; Demange, D.; Frances, L.
2016. Fusion engineering and design, 112, 541–547. doi:10.1016/j.fusengdes.2016.05.038
2015
Liquid scintillation. Mesuring procedures, new developments
Möbius, S.; Erat, S.; Möbius, R.; Möbius, T.; Santiago, L.; Wendel, J.; Wisser, S.
2015. Karlsruher Institut für Technologie (KIT)
Experimental study of permeation and selectivity of zeolite membranes for tritium processes
Borisevich, O.; Antunes, R.; Demange, D.
2015. Fusion engineering and design, 98-99, 1755–1758. doi:10.1016/j.fusengdes.2015.04.015
Development of a compact tritium activity monitor and first tritium measurements
Röllig, M.; Ebenhöch, S.; Niemes, S.; Priester, F.; Sturm, M.
2015. Fusion engineering and design, 100, 177–180. doi:10.1016/j.fusengdes.2015.05.056
Highly tritiated water processing by isotopic exchange
Shu, W. M.; Cristescu, I.; Michling, R.; Demange, D.; Willms, R. S.; Glugla, M.
2015. Fusion science and technology, 67, 563–566. doi:10.13182/FST14-T80
Tritium laboratory Karlsruhe: Administrative and technical framework for isotope laboratory operation
Welte, S.; Besserer, U.; Osenberg, D.; Wendel, J.
2015. Fusion science and technology, 67, 635–638. doi:10.13182/FST14-T98
Dismantling of the PETRA glove box: Tritium contamination and inventory assessment
Wagner, R.; Demange, D.; Fanghänel, E.; Le, T. L.; Schwarz, M.; Simon, K. H.
2015. Fusion science and technology, 67, 631–634. doi:10.13182/FST14-T97
How to make Raman-inactive helium visible in Raman spectra of tritium-helium gas mixtures
Schlösser, M.; Pakari, O.; Rupp, S.; Mirz, S.; Fischer, S.
2015. Fusion science and technology, 67, 559–562. doi:10.13182/FST14-T79
Raman spectroscopy at the Tritium Laboratory Karlsruhe
Schlösser, M.; Bornschein, B.; Fischer, S.; James, T. M.; Kassel, F.; Rupp, S.; Sturm, M.; Telle, H. H.
2015. Fusion science and technology, 67, 555–558. doi:10.13182/FST14-T78
Tritium processing for the European tests blanket systems: current status of the design and development strategy
Ricapito, I.; Calderoni, P.; Poitevin, Y.; Aiello, A.; Utili, M.; Demange, D.
2015. Fusion science and technology, 67, 543–546. doi:10.13182/FST14-T75
High level tritiated water monitoring by bremsstrahlung counting using a silicon drift detector
Niemes, S.; Sturm, M.; Michling, R.; Bornschein, B.
2015. Fusion science and technology, 67 (3), 507–510. doi:10.13182/FST14-T66
Capture and isotopic exchange method for water and hydrogen isotopes on zeolite catalysts up to technical scale for pre-study of processing highly tritiated water
Michling, R.; Braun, A.; Cristescu, I.; Dittrich, H.; Glugla, M.; Gramlich, N.; Lohr, N.; Shu, W.; Willms, S.
2015. Fusion science and technology, 67 (3), 483–486. doi:10.13182/FST14-T60
Current status of tritium calorimetry at TLK
Bükki-Deme, A.; Alecu, C. G.; Kloppe, B.; Bornschein, B.
2015. Fusion science and technology, 67 (2), 282–285. doi:10.13182/FST14-T11
Micro-channel catalytic reactor integration in caper and R&D on highly tritiated water handling and processing
Demange, D.; Cristescu, I.; Fanghänel, E.; Glugla, M.; Gramlich, N.; Le, T. L.; Michling, R.; Moosmann, H.; Shu, W. M.; Simon, K. H.; Wagner, R.; Welte, S.; Willms, R. S.
2015. Fusion science and technology, 67 (2), 312–315. doi:10.13182/FST14-T18
Zeolite membrane cascade for tritium extraction and recovery systems
Borisevich, O.; Demange, D.; Kind, M.; Lefebvre, X.
2015. Fusion science and technology, 67, 262–265. doi:10.13182/FST14-T6
CAPER as central and crucial facility to support R&D with tritium at TLK
Demange, D.; Fanghänel, E.; Fischer, S.; Le, T. L.; Priester, F.; Röllig, M.; Schlösser, M.; Simon, K. H.
2015. Fusion science and technology, 67 (2), 308–311. doi:10.13182/FST14-T17
First calibration measurements of an FTIR absorption spectroscopy system for liquid hydrogen isotopologues for the isotope separation system of fusion power plants
Größle, R.; Beck, A.; Bornschein, B.; Fischer, S.; Kraus, A.; Mirz, S.; Rupp, S.
2015. Fusion science and technology, 67 (2), 357–360. doi:10.13182/FST14-T29
Investigation of durability of optical coatings in highly purified tritium gas
Fischer, S.; Schönung, K.; Bornschein, B.; Rolli, R.; Schäfer, V.; Sturm, M.
2015. Fusion science and technology, 67 (2), 316–319. doi:10.13182/FST14-T19
2014
Tritium migration in HCLL and WCLL blankets: impact of tritium solubility in liquid Pb-17Li
Santucci, A.; Ciampichetti, A.; Demange, D.; Franza, F.; Tosti, S.
2014. IEEE transactions on plasma science, 42, 1053–1057. doi:10.1109/TPS.2014.2305759
Design and R&D activities of TriPla-CA consortium in support of ITER tritium plant development
Cristescu, I.; Ana, G.; Demange, D.; Michling, R.; Niculescu, A.; Petrutiu, C.; Pinna, T.; Welte, S.
2014. Fusion engineering and design, 89, 1524–1528. doi:10.1016/j.fusengdes.2014.03.067
A novel ⁸³sup(m)Kr tracer method for characterizing xenon gas and cryogenic distillation systems
Rosendahl, S.; Bokeloh, K.; Brown, E.; Cristescu, I.; Fieguth, A.; Huhmann, C.; Lebeda, O.; Levy, C.; Murra, M.; Schneider, S.; V’enos, D.; Weinheimer, C.
2014. Journal of Instrumentation, 9, 10010. doi:10.1088/1748-0221/9/10/P10010
Tritium transport issues for helium-cooled breeding blankets
Franza, F.; Boccaccini, L. V.; Demange, D.; Ciamichetti, A.; Zucchetti, M.
2014. IEEE transactions on plasma science, 42, 1951–1957. doi:10.1109/TPS.2014.2329573
Permeation of single gases and binary mixtures of hydrogen and helium through a MFI zeolite hollow fibre membrane for application in nuclear fusion
Simplicio, M.; Afonso, M. D.; Borisevich, O.; Lefebvre, X.; Demange, D.
2014. Separation and purification technology, 122, 199–205. doi:10.1016/j.seppur.2013.10.034
Advanced tritium extraction process for HCPB breeding blanket
Demange, D.
2014. Proceedings of the 17th IEA International Workshop on Ceramic Breeder Blanket Interactions (CBBl-17), September 12-14, 2013, Barcelona, Spain. Ed.: R. Knitter, 205–218, KIT Scientific Publishing
2013
Activity monitoring of a gaseous tritium source by beta induced X-ray spectrometry
Röllig, M.; Priester, F.; Babutzka, M.; Bonn, J.; Bornschein, B.; Drexlin, G.; Ebenhöch, S.; Otten, E. W.; Steidl, M.; Sturm, M.
2013. Fusion Engineering and Design, 88, 1263–1266. doi:10.1016/j.fusengdes.2012.11.001
Experimental assessment of a catalytic hydrogen oxidation system for the off-gas processing of the ITER WDS
Plusczyk, C.; Bekris, N.; Cristescu, I.; Lohr, N.; Michling, R.; Moosmann, H.; Welte, S.
2013. Fusion Engineering and Design, 88, 2332–2335. doi:10.1016/j.fusengdes.2013.05.104
Water detritation processing of JET purified waste water using the TRENTA facility at tritium laboratory Karlsruhe
Micheling, R.; Bekris, N.; Cristescu, I.; Lohr, N.; Plusczyk, C.; Welte, S.; Wendel, J.
2013. Fusion Engineering and Design, 88 (9-10), 2361–2365. doi:10.1016/j.fusengdes.2013.05.070
Setup and commissioning of a combined water detritiation and isotope separation experiment at the Tritium Laboratory Karlsruhe
Welte, S.; Cristescu, I.; Dittrich, H.; Lohr, N.; Melzer, R.; Michling, R.; Plusczyk, C.; Schäfer, P.
2013. Fusion Engineering and Design, 88, 2251–2254. doi:10.1016/j.fusengdes.2013.03.061
Zeolite membranes and palladium membrane reactor for tritium extraction from the breeder blankets of ITER and DEMO
Demange, D.; Borisevich, O.; Gramlich, N.; Wagner, R.; Welte, S.
2013. Fusion Engineering and Design, 88, 2396–2399. doi:10.1016/j.fusengdes.2013.05.102
Tritium management and safety issues in ITER and DEMO breeding blankets
Bornschein, B.; Day, C.; Demange, D.; Pinna, T.
2013. Fusion Engineering and Design, 88, 466–471. doi:10.1016/j.fusengdes.2013.03.032
2012
Technology Developments at KIT Towards a Magnetic Confinement Fusion Power Plant
Hesch, K.; Aktaa, J.; Antusch, S.; Boccaccini, L. V.; Day, C.; Demange, D.; Fietz, W. H.; Gantenbein, G.; Möslang, A.; Norajitra, P.; Rieth, M.
2012. Transactions of Fusion Science and Technology, 61 (1T), 64–69
Permeance and selectivity of helium and hydrogen in nanocomposite MFI-alumina hollow fibre for tritium processes
Borisevich, O.; Demange, D.; Parracho, T.; Pera-Titus, M.; Nicolas, C. H.
2012. 5th Internat. FEZA Conf., Valencia, E, July 3-7, 2011. Ed.: T. Blasco, 1054–1055, Universitat Politècnica de València
Overview of processes using zeolite at the Tritium Laboratory Karlsruhe
Demange, D.; Bekris, N.; Besserer, U.; Le, L. T.; Kramer, F.; Parracho, A.; Wagner, R.
2012. 5th Internat. FEZA Conf., Valencia, E, July 3-7, 2011. Ed.: T. Blasco, 1060–1062, Universitat Politècnica de València
Inactive commissioning of a micro channel catalytic reactor for highly tritiated water production in the CAPER facility of TLK
Santucci, A.; Demange, D.; Goerke, O.; Le, L. T.; Pfeifer, P.; Welte, S.
2012. Fusion Engineering and Design, 87, 547–550. doi:10.1016/j.fusengdes.2012.01.021
Processing highly tritiated water desorbed from molecular sieve bed using PERMCAT
Parracho, A. I.; Demange, D.; Knipe, S.; Le, L. T.; Simon, K. H.; Welte, S.
2012. Fusion Engineering and Design, 87, 1277–1281. doi:10.1016/j.fusengdes.2012.02.118
Development of a technical scale PERMCAT reactor for processing of highly tritiated water
Welte, S.; Demange, D.; Wagner, R.; Gramlich, N.
2012. Fusion Engineering and Design, 87, 1045–1049. doi:10.1016/j.fusengdes.2012.02.100
Overview of R&D at TLK for process and analytical issues on tritium management in breeder blankets of ITER and DEMO
Demange, D.; Alecu, C. G.; Bekris, N.; Borisevich, O.; Bornschein, B.; Fischer, S.; Gramlich, N.; Köllö, Z.; Le, T. L.; Michling, R.; Priester, F.; Röllig, M.; Schlösser, M.; Stämmler, S.; Sturm, M.; Wagner, R.; Welte, S.
2012. Fusion Engineering and Design, 87, 1206–1213. doi:10.1016/j.fusengdes.2012.02.105
Conceptual design of tritium extraction system for the european HCPB test blanket module
Ciampichetti, A.; Nitti, F. S.; Aiello, A.; Ricapito, I.; Liger, K.; Demange, D.; Sedano, L.; Moreno, C.; Succi, M.
2012. Fusion Engineering and Design, 87, 620–624. doi:10.1016/j.fusengdes.2012.01.047
On the mechanism of disproportionation of ZrCo hydrides
Bekris, N.; Sirch, M.
2012. Fusion Science and Technology, 62, 50–55
2011
A new method to measure small volumes in tritium handling facilities, using p-V measurements
Köllö, Z.; Alecu, C. G.; Moosmann, H.
2011. Fusion Science and Technology, 60, 972–975
HCLL and HCPB coolant purification system: Preliminary measurement and instrumentation plan
Liger, K.; Ciampichetti, A.; Demange, D.
2011. Fusion Science and Technology, 60, 1431–1435
Improvement and characterization of small cross-piece ionization chambers at the Tritium Laboratory Karlsruhe
Wagner, R.; Besserer, U.; Demange, D.; Dittrich, H.; Le, T. L.; Simon, K. H.; Guenther, K.
2011. Fusion science and technology, 60 (3), 968–971
Development of numerical simulation code of membrane reactor for detritiation
Munakata, K.; Demange, D.
2011. Fusion engineering and design, 86 (9-11), 2334–2337. doi:10.1016/j.fusengdes.2011.03.028
CAPER modifications and first experimental results on highly tritiated water processing with PERMCAT at the Tritium Laboratory Karlsruhe
Demange, D.; Fanghänel, E.; Kloppe, B.; Le, T. L.; Scheel, F.; Simon, K. H.; Wagner, R.; Welte, S.
2011. Fusion Science and Technology, 60 (4), 1317–1322
Between fusion and cosmology - the future of the Tritium Laboratory Karlsruhe
Bornschein, B.
2011. Fusion Science and Technology, 60 (3), 1088–1091
Reachable accuracy and precision for tritium measurements by calorimetry at TLK
Alecu, C. G.; Besserer, U.; Bornschein, B.; Kloppe, B.; Köllö, Z.; Wendel, J.
2011. Fusion Science and Technology, 60 (3), 937–940
Considerations towards the fuel cycle of a steady-state DT fusion device
Day, C.; Cristescu, I.; Pegourie, B.; Weyssow, B.
2011. 23rd IAEA Fusion Energy Conference, Daejeon, Korea, October 11-16, 2010 Proc.publ.in the Web Wien : IAEA, 2011 FTP/P1-04
2010
Modification of a solid polymer electrolyte (SPE) electrolyser to ensure tritium compatibility
Eichelhardt, F.; Cristescu, I.; Michling, R.; Welte, S.
2010. Fusion Engineering and Design, 85, 1211–1214. doi:10.1016/j.fusengdes.2010.03.004
Processing test of an upgraded mechanical design for PERMCAT reactor
Borgognoni, F.; Demange, D.; Dörr, L.; Tosti, S.; Welte, S.
2010. Fusion Engineering and Design, 85, 2171–2175. doi:10.1016/j.fusengdes.2010.08.022
Counter-current isotope swamping in a membrane reactor: the PERMCAT process and its applications in fusion technology
Demange, D.; Glugla, M.; Günther, K.; Le, T. L.; Simon, K. H.; Wagner, R.; Welte, S.
2010. Catalysis Today, 156, 140–145. doi:10.1016/j.cattod.2010.02.033
Mockup testing facilities and qualification strategy for EU ITER TBMs
Aiello, A.; Bühler, L.; Ciampichetti, A.; Demange, D.; Dörr, L.; Freibergs, J. F.; Ghidersa, B.; Ilic, M.; Laffont, G.; Messemer, G.; Platnieks, I.; Rampal, G.
2010. Fusion Engineering and Design, 85, 2012–2021. doi:10.1016/j.fusengdes.2010.07.007
2009
Performance tests of tritium separation by LPCE column at TLK facility
Sugiyama, T.; Tanaka, M.; Cristescu, I.; Dörr, L.; Welte, S.; Michling, R.; Asakura, Y.; Uda, T.; Yamamoto, I.
2009. Fusion Science and Technology, 56, 861–66
Construction and commissioning of an ITER sized Pd/Ag permeator for a water detritiation experiment
Welte, S.; Ana, G.; Cristescu, I.; Dörr, L.; Kuntz, B.; Konrad, J.; Michling, R.
2009. Fusion Engineering and Design, 84, 1969–72. doi:10.1016/j.fusengdes.2009.02.027
Modification, enhancement and operation of a water detritiation facility at the Tritium Laboratory Karlsruhe
Michling, R.; Cristescu, I.; Dörr, L.; Welte, S.; Wurster, W.
2009. Fusion Engineering and Design, 84, 338–43. doi:10.1016/j.fusengdes.2009.03.003
Calibrating a gas chromatograph to measure tritium using calorimetry
Köllö, Z.; Demange, D.; Bornschein, B.; Dörr, L.; Günther, K.; Kloppe, B.
2009. Fusion Engineering and Design, 84, 1073–75. doi:10.1016/j.fusengdes.2008.11.106
Design and experimental activities in view of water detritiation-isotopic separation systems combination in TRENTA, facility
Ana, R. G.; Cristescu, I.; Dörr, L.; Michling, R.; Welte, S.; Wurster, W.
2009. Fusion Engineering and Design, 84, 398–403. doi:10.1016/j.fusengdes.2008.12.093
Tritium release from lithium orthosilicate pebbles deposited with palladium
Munakata, K.; Shinozaki, T.; Inoue, K.; Kajii, S.; Shinozaki, Y.; Takeishi, T.; Knitter, R.; Bekris, N.; Fujii, T.; Yamana, H.; Okuno, K.
2009. Journal of Nuclear Materials, 386-388, 1091–94. doi:10.1016/j.jnucmat.2008.12.298
2008
Tritium release from lithium silicate pebbles produced from lithium hydroxide
Munakata, K.; Shinozaki, T.; Inoue, K.; Kajii, S.; Shinozaki, Y.; Knitter, R.; Bekris, N.; Fujii, T.; Yamana, H.; Okuno, K.
2008. Fusion Engineering and Design, 83, 1317–20. doi:10.1016/j.fusengdes.2008.05.039
Recent advances on hydrogen retention in ITER’s plasma-facing materials: Beryllium, carbon and tungsten
Skinner, C. H.; Haasz, A. A.; Alimov, V. K.; Bekris, N.; Causey, R. A.; Clark, R. E. H.; Coad, J. P.; Davis, J. W.; Doerner, R. P.; Mayer, M.; Pisarev, A.; Roth, J.; Tanabe, T.
2008. Fusion Science and Technology, 54, 891–945
ITER design review: Tritium issues
Murdoch, D.; Beloglazov, S.; Boucquey, P.; Chung, H.; Glugla, M.; Hayashi, T.; Perevezentsev, A.; Sessions, K.; Taylor, C.
2008. Fusion Science and Technology, 54, 3–8
Behavior of solid polymer membrane electrolyzers in use with highly tritiated water
Michling, R.; Cristescu, I.; Dörr, L.; Fanghänel, T.; Welte, S.; Wurster, W.
2008. Fusion Science and Technology, 54, 470–74
Behavior of NAFION perfluorosulfonate ionomer membranes in presence of tritiated water
Matei, L.; Postolache, C.; Cristescu, I.; Brad, S.
2008. Fusion Science and Technology, 54, 475–78
A decade of tritium technology development and operation at the Tritium Laboratory Karlsruhe
Dörr, L.; Besserer, U.; Bekris, N.; Bornschein, B.; Caldwell-Nichols, C.; Demange, D.; Cristescu, I.; Cristescu, I. R.; Glugla, M.; Hellriegel, G.; Schäfer, P.; Welte, S.; Wendel, J.
2008. Fusion Science and Technology, 54, 143–48
Tritium processing tests for the validation of upgraded PERMCAT mechanical design
Demange, D.; Glugla, M.; Günther, K.; Le, T. L.; Simon, K. H.; Wagner, R.; Welte, S.
2008. Fusion Science and Technology, 54, 14–17
Experiments on water detritiation and cryogenic distillation at TLK. Impact on ITER fuel cycle subsystems interfaces
Cristescu, I.; Cristescu, I. R.; Dörr, L.; Hellriegel, G.; Michling, R.; Murdoch, D.; Schaefer, P.; Welte, S.; Wurster, W.
2008. Fusion Science and Technology, Rochester, 54, 440–45
Uncertainty assessment and analysis of ITER in VV tritium inventory determination
Cristescu, I. R.; Cristescu, I.; Glugla, M.; Murdoch, D.; Ciattaglia, S.
2008. Fusion Science and Technology, 54, 9–13
Post service examination of a tritium permeator and a turbomolecular pump from the CAPER facility at the tritium laboratory Karlsruhe
Caldwell-Nichols, C. J.; Adami, H. D.; Bekris, N.; Demange, D.; Glugla, M.; Kramer, K. F.; Simon, K. H.
2008. Fusion Science and Technology, 54, 599–602
Effect of radiogenic helium on stainless steel 12Cr18Ni10Ti structural changes and hydrogen sorption
Denisov, E.; Kanashenko, S.; Causey, R.; Grishechkin, S.; Glugla, M.; Hassanein, A.; Kompaniets, T.; Kurdyumov, A.; Malkov, I.; Yukhimchuk, A.
2008. Fusion Science and Technology, 54, 493–96
Effect of radiogenic helium on stainless steel 12Cr18Ni10Ti mechanical properties and hydrogen permeability
Boitsov, I.; Kanashenko, S.; Causey, R.; Denisov, E.; Glugla, M.; Grishechkin, S.; Hassanein, A.; Lebedev, B.; Kompaniets, T.; Kurdyumov, A.; Malkov, I.; Yukhimchuk, A.
2008. Fusion Science and Technology, 54, 497–500
Accounting strategy of tritium inventory in the heavy water detritiation pilot plant from ICIT Rm. Valcea
Bidica, N.; Stefanescu, I.; Cristescu, I.; Bornea, A.; Zamfirache, M.; Lazar, A.; Vasut, F.; Pearsica, C.; Stefan, I.; Prisecaru, I.; Sindilar, G.
2008. Fusion Science and Technology, 54, 346–49
Tritium confinement, retention and releases at the Tritium Laboratory Karlsruhe
Besserer, U.; Dörr, L.; Glugla, M.
2008. Fusion Science and Technology, 54, 160–63
Performance of a full-scale ITER metal hydride storage bed in comparison with requirements
Beloglazov, S.; Glugla, M.; Fanghänel, E.; Perevezentsev, A.; Wagner, R.
2008. Fusion Science and Technology, 54, 22–26
Tritium in fusion: R&D in the EU
Lässer, R.; Antipenkov, A.; Bekris, N.; Boccaccini, L. V.; Caldwell-Nichols, C. J.; Cristescu, I.; Day, C.; Gasparotto, M.; Glugla, M.; Dell’Orco, G.; Gabriel, F.; Gastaldi, O.; Grisolia, C.; Knipe, S.; Magielsen, A. J.; Möslang, A.; Murdoch, D.; Pearce, R.; Perevezentsev, A.; Piazza, G.; Poitevin, Y.; Ricapito, I.; Salavy, J. F.; Sedano, L. A.; Zmitko, M.
2008. Fusion Science and Technology, 54, 39–44
Cryogenic design of the KATRIN source cryostat
Grohmann, S.; Bonn, J.; Bornschein, B.; Gehring, R.; Gil, W.; Kazachenko, O.; Neumann, H.; Noe, M.; Weiss, C.
2008. Weisend, J.G. [Hrsg.] Advances in Cryogenic Engineering : Transactions of the Cryogenic Engineering Conf., Chattanooga, Tenn., July 16-20, 2007 Melville, N.Y. : AIP, 2008 (AIP Conference Proceedings ; 985) (Advances in Cryogenic Engineering ; 53B), 1277–84
Vacuum technology for ITER
Murdoch, D.; Antipenkov, A.; Caldwell-Nichols, C.; Day, C.; Dremel, M.; Haas, H.; Hauer, V.; Jensen, H.
2008. Journal of Physics: Conference Series, 100, 062002/1–7. doi:10.1088/1742-6596/100/6/062002
2007
Experimental and simulation study on adsorption of hydrogen isotopes on MS5A at 77 K
Munakata, K.; Beloglazov, S.; Bekris, N.; Glugla, M.; Wagner, R.; Fanghänel, E.
2007. Fusion Engineering and Design, 82, 2303–10. doi:10.1016/j.fusengdes.2007.07.062
Treatment of ITER plasma facing components: Current status and remaining open issues before ITER implementation
JET EFDA Contributors; Grisolia, C.; Counsell, G.; Dinescu, G.; Semerok, A.; Bekris, N.; Coad, P.; Hopf, C.; Roth, J.; Rubel, M.; Widdowson, A.; Tsitrone, E.
2007. Fusion engineering and design, 82, 2390–98. doi:10.1016/j.fusengdes.2007.05.047
Commissioning of water detritiation and cryogenic distillation systems at TLK in view of ITER design
Cristescu, I.; Cristescu, I. R.; Dörr, L.; Glugla, M.; Hellriegel, G.; Michling, R.; Murdoch, D.; Schäfer, P.; Welte, S.; Wurster, W.
2007. Fusion Engineering and Design, 82, 2126–32. doi:10.1016/j.fusengdes.2007.04.001
Experimental validation of a method for performance monitoring of the impurity processing stage in the TEP system of ITER
Bornschein, B.; Corneli, D.; Glugla, M.; Günther, K.; Le, T. L.; Simon, K. H.
2007. Fusion Engineering and Design, 82, 2133–39. doi:10.1016/j.fusengdes.2006.12.010
Efficacy of photon cleaning of JET divertor tiles
JET EFDA Contributors; Widdowson, A.; Coad, J. P.; Bekris, N.; Counsell, G.; Forrest, M. J.; Gibson, K. J.; Hole, D.; Likonen, J.; Parsons, W.; Renvall, T.; Rubel, M.
2007. Journal of nuclear materials, 363-365, 341–45. doi:10.1016/j.jnucmat.2007.01.030
In-situ tokamak laser applications for detritiation and co-deposited layers studies
Grisolia, C.; Semerok, A.; Weulersse, J. M.; Le Guern, F.; Fomichev, S.; Brygo, F.; Fichet, P.; Thro, P. Y.; Coad, P.; Bekris, N.; Stamp, M.; Rosanvallon, S.; Piazza, G.
2007. Journal of Nuclear Materials, 363-365, 1138–47. doi:10.1016/j.jnucmat.2007.01.169
Tritium inventories and tritium safety design principles for the fuel cycle of ITER
Cristescu, I. R.; Cristescu, I.; Dörr, L.; Glugla, M.; Murdoch, D.
2007. Nuclear Fusion, 47, S458-S463. doi:10.1088/0029-5515/47/7/S08
Integrated tests of water detritiation and cryogenic distillation in view of ITER design
Cristescu, I.; Cristescu, I. R.; Dörr, L.; Glugla, M.; Murdoch, D.
2007. Fusion Science and Technology, 52, 667–71
Modeled tritium inventories within the ITER fuel cycle systems in typical fueling scenarios
Cristescu, I. R.; Cristescu, I.; Day, C.; Glugla, M.; Murdoch, D.
2007. Fusion Science and Technology, 52, 659–66
Thermal release rate of tritium trapped in bulk and plasma exposed surfaces of carbon specimens obtained from JET divertor
Bekris, N.; Coad, J. P.; Skinner, C. H.; Damm, E.; Nägele, W.
2007. Journal of Nuclear Materials, 367-370, 1254–59. doi:10.1016/j.jnucmat.2007.03.254
The ITER tritium systems
Glugla, M.; Antipenkov, A.; Beloglazov, S.; Caldwell-Nichols, C.; Cristescu, I. R.; Cristescu, I.; Day, C.; Doerr, L.; Girard, J. P.; Tada, E.
2007. Fusion Engineering and Design, 82, 472–87. doi:10.1016/j.fusengdes.2007.02.025
EU fuel cycle development priorities for ITER
Murdoch, D.; Cristescu, I.; Day, C.; Glugla, M.; Laesser, R.; Mack, A.
2007. Fusion Engineering and Design, 82, 2158–63. doi:10.1016/j.fusengdes.2007.07.058
Material compatibility issues in EU fusion fuel cycle R&D and design
Murdoch, D. K.; Cristescu, I.; Day, C.; Glugla, M.; Lässer, R.; Mack, A.
2007. Journal of Nuclear Materials, 367-370, 1366–70. doi:10.1016/j.jnucmat.2007.03.263
2006
A leak localisation technique for ITER water cooling circuits
Caldwell-Nichols, C. J.; Glugla, M.; Day, C.; Haas, H.; Murdoch, D. K.; Wykes, M. E. P.
2006. 21st IEEE/NPSS Symp.on Fusion Engineering (SOFE 05), Knoxville, Tenn., September 26-29, 2005 Proc.on CD-ROM Piscataway, N.J.: IEEE Operations Center, 2006
Der ITER-Brennstoffkreislauf - Wasserstoffprozesstechnik für die Fusion
Day, C.; Glugla, M.; Janeschitz, G.
2006. Nachrichten - Forschungszentrum Karlsruhe, 38, 19–21
Hydrogen isotope separation by permeation through palladium membranes
Glugla, M.; Cristescu, I. R.; Cristescu, I.; Demange, D.
2006. Journal of Nuclear Materials, 355, 47–53. doi:10.1016/j.jnucmat.2006.04.003
Tritium inventory assessment for ITER using TRIMO
Cristescu, I. R.; Cristescu, I.; Murdoch, D.; Dörr, L.; Glugla, M.
2006. Fusion Engineering and Design, 81, 763–69. doi:10.1016/j.fusengdes.2005.06.367
Study of poisoning effects with the ITER model pump during relevant operation cycles
Haas, H.; Caldwell-Nichols, C.; Day, C.; Mack, A.; Murdoch, D.
2006. Fusion Engineering and Design, 81, 845–50. doi:10.1016/j.fusengdes.2005.09.077
JET contributions to ITER technology issues
Grisolia, C.; Rosanvallon, S.; Coad, P.; Bekris, N.; Braet, J.; Brennan, D.; Brichard, B.; Counsell, G.; Day, C.; Likonen, J.; Piazza, G.; Poletiko, C.; Rubel, M.; Semerok, A.
2006. Fusion Engineering and Design, 81, 149–54. doi:10.1016/j.fusengdes.2005.08.033
ITER fuel cycle R&D: consequences for the design
Glugla, M.; Murdoch, D. K.; Antipenkov, A.; Beloglazov, S.; Cristescu, I.; Cristescu, I. R.; Day, C.; Lässer, R.; Mack, A.
2006. Fusion Engineering and Design, 81, 733–44. doi:10.1016/j.fusengdes.2005.07.038
Hydrogen inventories in the vacuum pumping systems of ITER
Day, C.; Antipenkov, A.; Cristescu, I. R.; Dremel, M.; Federici, G.; Haas, H.; Hauer, V.; Mack, A.; Murdoch, D. K.; Wykes, M.
2006. Fusion Engineering and Design, 81, 777–84. doi:10.1016/j.fusengdes.2005.07.020
Long term performances assessment of a water detritiation system components
Cristescu, I.; Cristescu, I. R.; Dörr, L.; Glugla, M.; Murdoch, D.; Welte, S.
2006. Fusion Engineering and Design, 81, 839–44. doi:10.1016/j.fusengdes.2005.07.027
2005
Collection and analysis of data related to fusion machines (JET and TLK) operating experience on component failure
Pinna, T.; Cambi, G.; Ciattaglia, S.; Lo Bue, A.; Knipe, S.; Orchard, J.; Pearce, R.; Besserer, U.
2005. Fusion Engineering and Design, 75-79, 1199–1203. doi:10.1016/j.fusengdes.2005.06.043
Comparison of modelling of tritium release from ceramic breeder materials
Munakata, K.; Yokoyama, Y.; Baba, A.; Penzhorn, R. D.; Oyaidzu, M.; Okuno, K.
2005. Fusion Engineering and Design, 75-79, 673–78. doi:10.1016/j.fusengdes.2005.06.138
Strategy for determination of ITER in-vessel tritium inventory
Murdoch, D.; Cristescu, I. R.; Lässer, R.
2005. Fusion Engineering and Design, 75-79, 667–71. doi:10.1016/j.fusengdes.2005.06.246
Requirements and selection criteria for the mechanical pumps for the ITER tritium plant
Caldwell-Nichols, C. J.; Glugla, M.; Welte, S.; Murdoch, D. K.
2005. Fusion Engineering and Design, 75-79, 663–666. doi:10.1016/j.fusengdes.2005.06.129
Influence of deuterium on the design of the JET water detritiation system
Cristescu, I.; Cristescu, I. R.; Dörr, L.; Glugla, M.; Bell, A.; Brennan, D.; Murdoch, D.
2005. Fusion Engineering and Design, 75-79, 651–54. doi:10.1016/j.fusengdes.2005.06.310
Experimental validation of a method for performance monitoring of the front-end permeators in the TEP system of ITER
Bornschein, B.; Glugla, M.; Günther, K.; Le, T. L.; Simon, K. H.
2005. Fusion Engineering and Design, 75-79, 645–50. doi:10.1016/j.fusengdes.2005.06.038
Protection of the primary circuits and effect on the design of the inner deuterium/tritium fuel cycle of ITER
Glugla, M.; Caldwell-Nichols, C.; Cristescu, I. R.; Dörr, L.; Hellriegel, G.; Lässer, R.; Murdoch, D.; Schäfer, P.
2005. Fusion Engineering and Design, 75-79, 637–43. doi:10.1016/j.fusengdes.2005.06.047
JET contributions to the ITER fuel cycle issues
JET EFDA Contributors; Grisolia, C.; Bekris, N.; Likonen, J.; Coad, P.; Semerok, A.; Brennan, D.; Piazza, G.; Rosanvallon, S.
2005. Fusion engineering and design, 75-79, 679–83. doi:10.1016/j.fusengdes.2005.06.035
Comparison of tritium retention and carbon deposition in JET and JT-60U
Tanabe, T.; Sugiyama, K.; Coad, P.; Bekris, N.; Glugla, M.; Miya, N.
2005. Journal of Nuclear Materials, 345, 89–95. doi:10.1016/j.jnucmat.2005.05.004
Stellar neutron capture rates of ¹⁴C
Reifarth, R.; Heil, M.; Plag, R.; Besserer, U.; Dababneh, S.; Dörr, L.; Görres, J.; Haight, R. C.; Käppeler, F.; Mengoni, A.; O’Brian, S.; Patronis, N.; Rundberg, R. S.; Wiescher, M.; Wilhelmy, J. B.
2005. Nuclear Physics A, 758, 787–790. doi:10.1016/j.nuclphysa.2005.05.141
Tritium related studies within JET fusion technology work programme
JET EFDA Contributors; Rosanvallon, S.; Bekris, N.; Braet, J.; Coad, P.; Counsel, G.; Cristescu, I.; Grisolia, C.; Le Guern, F.; Ionita, G.; Likonen, J.; Perevezenstev, A.; Piazza, G.; Poletiko, C.; Rubel, M.; Weulersse, J. M.; Williams, J.
2005. Fusion science and technology, 48, 268–273
Recovery method of bred tritium from solid breeders
Furukubo, Y. Y.; Fukuda, K.; Nishikawa, M.; Beloglazov, S.
2005. Fusion Science and Technology, 48, 658–61
Release behavior of bred tritium from irradiated Li₄SiO₄
Kinjyo, T.; Nishikawa, M.; Katayama, K.; Tanifuji, T.; Enoeda, M.; Beloglazov, S.
2005. Fusion Science and Technology, 48, 646–49
Tritium retention in the gap between the plasma-facing carbon tiles Used in D-T discharge phase in JET and TFTR
Tanabe, T.; Sugiyama, K.; Skinner, C. H.; Bekris, N.; Gentile, C. A.; Coad, J. P.
2005. Fusion Science and Technology, 48, 577–80
Detailed tritium distribution on the JET MK IIA divertor tiles
Sugiyama, K.; Tanabe, T.; Bekris, N.; Glugla, M.; Coad, J. P.
2005. Fusion Science and Technology, 48, 573–76
Distribution of hydrogen isotopes, carbon and beryllium on in-vessel surfaces in the various JET divertors
JET EFDA Contributors; Coad, J. P.; Rubel, M.; Bekris, N.; Brennan, D.; Hole, D.; Likonen, J.; Vainonen-Ahlgren, E.
2005. Fusion science and technology, 48, 551–56
Tritium accountancy issues of the ITER fuel cycle
Lässer, R.; Murdoch, T. K.; Glugla, M.
2005. Fusion Science and Technology, 48, 337–42
Investigation of isotope effects in the gas streams supplied by a 1:1 ITER storage bed using a micro gas chromatography
Beloglazov, S.; Glugla, M.; Wagner, R.; Fanghänel, S.; Grünhagen, S.
2005. Fusion Science and Technology, 48, 67–70
Numerical simulation of membrane reactor for detritiation of plasma exhaust gas
Munakata, K.; Bornschein, B.; Corneli, D.; Glugla, M.
2005. Fusion Science and Technology, 48, 17–22
ITER fuel cycle development: EU-PT activities
Murdoch, D. K.; Lässer, R.; Glugla, M.; Mack, A.
2005. Fusion Science and Technology, 48, 3–10
Semi-technical cryogenic molecular Sieve bed for the tritium extraction system of the test blanket module for ITER
Beloglazov, S.; Bekris, N.; Glugla, M.; Wagner, R.
2005. Fusion Science and Technology, 48, 662–65
Simulation of tritium spreading in controlled areas after a tritium release
Cristescu, I. R.; Travis, J.; Iwai, Y.; Kobayashi, H.; Murdoch, D.
2005. Fusion Science and Technology, 48, 464–67
High resolution vacuum calorimeter
Dörr, L.; Besserer, U.; Grünhagen, S.; Glugla, M.; Kloppe, B.; Sirch, M.; Hemmerich, J. L.
2005. Fusion Science and Technology, 48, 358–61
ITER dynamic tritium inventory modelling code
Cristescu, I. R.; Dörr, L.; Busigin, A.; Murdoch, D.
2005. Fusion Science and Technology, 48, 343–48
The closed tritium cycle of the tritium laboratory Karlsruhe
Dörr, L.; Besserer, U.; Glugla, M.; Hellriegel, G.; Hellriegel, W.; Schäfer, P.; Wendel, J.
2005. Fusion Science and Technology, 48, 262–67
Decontamination, dismantling and refurbishing of the PETRA glove box at the Tritium Laboratory Karlsruhe
Caldwell-Nichols, C. J.; Glugla, M.; Dörr, L.; Berndt, U.
2005. Fusion Science and Technology, 48, 216–19
TRENTA facility for trade-off studies between combined electrolysis catalytic exchange and cryogenic distillation processes
Cristescu, I.; Cristescu, I. R.; Dörr, L.; Glugla, M.; Hellriegel, G.; Kveton, O.; Murdoch, D.; Schäfer, P.; Welte, S.
2005. Fusion Science and Technology, 48, 97–101
Memory effects in measurements of low tritium concentrations as required for the outlet of the TEP system of the ITER fuel cycle
Corneli, D.; Bornschein, B.; Fanghänel, E.; Glugla, M.; Günther, K.; Le, T. L.; Simon, K. H.
2005. Fusion Science and Technology, 48, 55–58
Successful experimental verification of the Tokamak exhaust processing concept of ITER with the CAPER facility
Bornschein, B.; Glugla, M.; Günther, K.; Le, T. L.; Simon, K. H.; Welte, S.
2005. Fusion Science and Technology, 48, 11–16
Tritium pumps for ITER roughing system
Antipenkov, A.; Day, C.; Lässer, R.; Mack, A.; Wagner, R.
2005. Fusion Science and Technology, 48, 47–50
Tritium distribution on plasma-facing tiles from ASDEX Upgrade
Sugiyama, K.; Tanabe, T.; Krieger, K.; Neu, R.; Bekris, N.
2005. Journal of Nuclear Materials, 337-339, 634–38. doi:10.1016/j.jnucmat.2004.10.158
Tritium distribution in JET Mark IIA type divertor tiles analysed by BIXS
Torikai, Y.; Matsuyama, M.; Bekris, N.; Glugla, M.; Coad, P.; Naegele, W.; Erbe, A.; Noda, N.; Philipps, V.; Watanabe, K.
2005. Journal of Nuclear Materials, 337-339, 575–79. doi:10.1016/j.jnucmat.2004.10.150
Characterisation of flakes generated in JET after DD and DT plasma operations
Bekris, N.; Coad, J. P.; Penzhorn, R. D.; Knipe, S.; Doerr, L.; Rolli, R.; Nägele, W.
2005. Journal of Nuclear Materials, 337-339, 659–63. doi:10.1016/j.jnucmat.2004.09.072
2004
A small and compact AMS facility for tritium depth profiling
Friedrich, M.; Pilz, W.; Bekris, N.; Glugla, M.; Kiisk, M.; Liechtenstein, V.
2004. Nuclear Instruments and Methods B, Proc. of the 9. Int. Conf. on Accelerator Mass Spectrometry, Nagoya, J, September 9-13, 2002, 223-224, 21–25. doi:10.1016/j.nimb.2004.04.008
Modeling of tritium release from ceramic breeder materials by focusing on transport process in breeder grain
Okabe, H.; Munakata, K.; Yokoyama, Y.; Koga, A.; Narisato, Y.; Penzhorn, R. D.; Okuno, K.
2004. Journal of Nuclear Materials, 11th Internat.Conf.on Fusion Reactor Materials (ICFRM-11), Kyoto, J, December 7-12, 2003, 329-33, 1309–12. doi:10.1016/j.jnucmat.2004.04.224
Der Brennstoffkreislauf von Fusionsreaktoren
Cristescu, I. R.; Dörr, L.; Glugla, M.; Day, C.; Mack, A.; Gross, S.
2004. Nachrichten - Forschungszentrum Karlsruhe, 36, 23–29
Recent activities on the design of the ITER deuterium/tritium fuel cycle
Glugla, M.; Antipenkov, A.; Bekris, N.; Caldwell-Nichols, C.; Cristescu, I.; Cristescu, I. R.; Day, C.; Doerr, L.; Gross, S.; Haas, H.; Janeschitz, G.; Lässer, R.; Mack, A.
2004. 20th IEEE/NPSS Symp.on Fusion Engineering (SOFE), San Diego, Calif., October 14- 17, 2003 Piscataway, N.J. : IEEE, 2003 Auch als CD-ROM, 16–19
The manufacturing technologies of the European breeding blankets
Cardella, A.; Rigal, E.; Bedel, L.; Bucci, P.; Fiek, J.; Forest, L.; Boccaccini, L. V.; Diegele, E.; Giancarli, L.; Hermsmeyer, S.; Janeschitz, G.; Lässer, R.; Li Puma, A.; Lulewicz, J. D.; Möslang, A.; Poitevin, Y.; Rabaglino, E.
2004. Journal of Nuclear Materials, 11th Internat.Conf.on Fusion Reactor Materials (ICFRM-11), Kyoto, J, December 7- 12, 2003, 329-33, 133–40. doi:10.1016/j.jnucmat.2004.04.014
Modeling of HT and HTO release from irradiated metazirconate
Beloglazov, S.; Nishikawa, M.; Glugla, M.; Kinjyo, T.
2004. Journal of Nuclear Materials, 11th Internat.Conf.on Fusion Reactor Materials, Kyoto, J, December 7-12, 2003, 329-33, 1274–78. doi:10.1016/j.jnucmat.2004.04.232
Fusion technology research and development at JET
Ciattaglia, S.; Bekris, N.; Bell, A. C.; Braet, J.; Brichard, B.; Caldwell-Nichols, C.; Cambi, G.; Coad, P.; Cristescu, I.; Cristescu, I. R.; Day, C.; Gautier, E.; Glugla, M.; Lässer, R.; Likonen, J.; Mayer, M.; Perevesentev, A.; Piazza, G.; Pinna, T.; Poletiko, C.; Rosanvallon, S.; Williams, J.
2004. 20th IEEE/NPSS Symp.on Fusion Engineering (SOFE), San Diego, Calif., October 14-17, 2003 Piscataway, N.J. : IEEE, 2003 Auch als CD-ROM, 250–55
Assessment of the heating technique as a possible ex-situ detritiation method for carbon first wall materials from fusion machines
Bekris, N.; Skinner, C. H.; Berndt, U.; Gentile, C. A.; Glugla, M.; Erbe, A.; Pilz, W.
2004. Journal of Nuclear Materials, 11th Internat.Conf.on Fusion Reactor Materials, Kyoto, J, December 7-12, 2003, 329-33, 814–19. doi:10.1016/j.jnucmat.2004.04.158
2003
Effect of water vapor on tritium release from ceramic breeder material
Munakata, K.; Koga, A.; Yokoyama, Y.; Kanjo, S.; Beloglazov, S.; Ianovski, D.; Takeishi, T.; Penzhorn, R. D.; Kawamoto, K.; Moriyama, H.; Morimoto, Y.; Akahori, S.; Okuno, K.
2003. Fusion Engineering and Design, 22n Symp.on Fusion Technology (SOFT), Helsinki, SF, September 9-13, 2002, 69, 27–31. doi:10.1016/S0920-3796(03)00228-X
Gas chromatography at the tritium laboratory Karlsruhe
Lässer, R.; Grünhagen, S.
2003. Wissenschaftliche Berichte, FZKA-6894 (August 2003). doi:10.5445/IR/270055409
CECE experimental facility for water detritiation at TLK
Cristescu, I. R.; Cristescu, I.; Glugla, M.; Dörr, L.; Welte, S.
2003. Jahrestagung Kerntechnik 2003, Berlin, 20.-22.Mai 2003 Berlin : INFORUM GmbH, 2003 (Auch auf CD-ROM), 429–32
Thermal response of tritiated codeposits from JET and TFTR to transient heat pulses
Skinner, C. H.; Bekris, N.; Coad, J. P.; Gentile, C. A.; Hassanein, A.; Reiswig, R.; Willms, S.
2003. Physica Scripta, T103, 34–37
Characterisation of dust and flakes generated in fusion machines after DD and DT operations
Bekris, N.; Penzhorn, R. D.
2003. Wissenschaftliche Berichte, FZKA-6858 (April 2003). doi:10.5445/IR/270054709
Tritium extraction from JET CFC tile samples. Detritiation techniques of first wall carbon materials used in fusion machines
Bekris, N.; Caldwell-Nichols, C.; Doerr, L.; Glugla, M.; Nägele, W.; Penzhorn, R. D.; Rolli, R.; Ziegler, H.
2003. Wissenschaftliche Berichte, FZKA-6859 (April 2003). doi:10.5445/IR/270054708
Tritium retention of plasma facing components in tokamaks
Tanabe, T.; Bekris, N.; Coad, P.; Skinner, C. H.; Glulga, M.; Miya, N.
2003. Journal of nuclear materials, Proc. of the 15th Internat.Conf.on Plasma Surface Interactions in Controlled Fusion Devices (PSI-15), Gifu, J, May 27-31, 2002, 313-316, 478–490. doi:10.1016/S0022-3115(02)01377-6
Tritium distribution on the surface of plasma facing carbon tiles used in JET
Sugiyama, K.; Miyasaka, K.; Tanabe, T.; Glugla, M.; Bekris, N.; Coad, P.
2003. Journal of nuclear materials, Proc. of the 15th Internat.Conf.on Plasma Surface Interactions in Controlled Fusion Devices (PSI-15), Gifu, J, May 27-31, 2002, 313-316, 507–513. doi:10.1016/S0022-3115(02)01387-9
Tritium removal from JET and TFTR tiles by a scanning laser
Skinner, C. H.; Bekris, N.; Coad, J. P.; Gentile, C. A.; Glugla, M.
2003. Journal of nuclear materials, Proc. of the 15th Internat.Conf.on Plasma Surface Interactions in Controlled Fusion Devices (PSI-15), Gifu, J, May 27-31, 2002, 313-316, 496–500. doi:10.1016/S0022-3115(02)01382-X
Beryllium and carbon films in JET following D-T operation
Rubel, M.; Coad, J. P.; Bekris, N.; Erents, S. K.; Hole, D.; Matthews, G. F.; Penzhorn, R. D.
2003. Journal of nuclear materials, Proc. of the 15th Internat.Conf.on Plasma Surface Interactions in Controlled Fusion Devices (PSI-15), Gifu, J, May 27-31, 2002, 313-316, 321–326. doi:10.1016/S0022-3115(02)01350-8
Non-destructive tritium measurements of Mk IIA divertor tile by BIXS
Matsuyama, M.; Bekris, N.; Glugla, M.; Noda, N.; Philipps, V.; Watanabe, K.
2003. Journal of nuclear materials, Proc. of the 15th Internat.Conf.on Plasma Surface Interactions in Controlled Fusion Devices (PSI-15), Gifu, J, May 27-31, 2002, 313-316, 491–495. doi:10.1016/S0022-3115(02)01380-6
Tritium depth profiles and accelerator mass spectroscopy for JET tiles (graphite/CFC tiles)
Bekris, N.; Glugla, M.; Berndt, U.; Penzhorn, R. D.; Friedrich, M.; Pilz, W.
2003. Watanabe, K. [Hrsg.] Internat.Workshop on Tritium-Material Interactions, Contamination and Decontamination, Toyama, J, November 18-19, 2001 Proc
A small and compact AMS facility for tritium depth profiling
Friedrich, M.; Pilz, W.; Bekris, N.; Glugla, M.; Kiisk, M.; Liechtenstein, V.
2003. PRAMANA : Journal of Physics, (2002), 59, 1053–59
Overview of JET results, near term plans
JET EFDA Contributors; Pamela, J.; Rapp, J.; Day, C.; Jensen, H. S.; Lässer, R.; Müller, G.; Piosczyk, B.; Thumm, M.
2003. Fusion engineering and design, 22nd Symp.on Fusion Technology (SOFT), Helsinki, SF, September 9-13, 2002, 66-68, 25–37. doi:10.1016/S0920-3796(03)00112-1
EU contribution to ITER CTA fuel cycle design and R&D
Murdoch, D.; Bekris, N.; Boissin, J. C.; Day, C.; Gilroy, J.; Glugla, M.; Lässer, R.; Mack, A.
2003. Fusion Engineering and Design, Proc.of the 22nd Symp.on Fusion Technology (SOFT), Helsinki, SF, September 9-13, 2002, 69, 45–49. doi:10.1016/S0920-3796(03)00233-3
Tritium depth profiles in 2D and 4D CFC tiles from JET and TFTR
Bekris, N.; Skinner, C. H.; Berndt, U.; Gentile, C. A.; Glugla, M.; Schweigel, B.
2003. Journal of nuclear materials, Proc. of the 15th Internat.Conf.on Plasma Surface Interactions in Controlled Fusion Devices (PSI-15), Gifu, J, May 27-31, 2002, 313-316, 501–506. doi:10.1016/S0022-3115(02)01576-3
Simultaneous tritium and deuterium transfer in a water detritiation CECE facility at TLK
Cristescu, I.; Cristescu, I. R.; Tamm, U.; Caldwell-Nichols, C. J.; Glugla, M.; Murdoch, D.; Welte, S.
2003. Fusion engineering and design, 69 (1-4), 109–113. doi:10.1016/S0920-3796(03)00270-9
The inner deuterium/tritium fuel cycle of ITER
Glugla, M.; Lässer, R.; Dörr, L.; Murdoch, D.; Haange, R.; Yoshida, H.
2003. Fusion Engineering and Design, 22nd Symp.on Fusion Technology (SOFT), Helsinki, SF, September 9-13, 2002, 69, 39–43. doi:10.1016/S0920-3796(03)00231-X
Tritium tests with a technical PERMCAT for final clean-up of ITER exhaust gases
Bornschein, B.; Glugla, M.; Günther, K.; Le, T. L.; Simon, K. H.; Welte, S.
2003. Fusion Engineering and Design, 22nd Symp.on Fusion Technology (SOFT), Helsinki, SF, September 9-13, 2002, 69, 51–56. doi:10.1016/S0920-3796(03)00234-5
Tritium related studies at the JET facilities
Lässer, R.; Bekris, N.; Bell, A. C.; Caldwell-Nichols, C.; Cristescu, I.; Ciattaglia, S.; Coad, P.; Day, C.; Glugla, M.; Likonen, J.; Murdoch, D. K.; Rosanvallon, S.; Scaffidi-Argentina, F.
2003. Fusion Engineering and Design, Proc.of the 22nd Symp.on Fusion Technology (SOFT), Helsinki, SF, September 9-13, 2002, 69, 75–80. doi:10.101/S0920-3796(03)00248-5
Use of micro gas chromatography in the fuel cycle of fusion reactors
Lässer, R.; Grünhagen, S.; Kawamura, Y.
2003. Fusion Engineering and Design, 22nd Symp.on Fusion Technology (SOFT), Helsinki, SF, September 9-13, 2002, 69, 813–17. doi:10.1016/S0920-3796(03)00413-7
2002
Design of the ITER tritium plant, confinement and detritiation facilities
Yoshida, H.; Glugla, M.; Hayashi, T.; Lässer, R.; Murdoch, D.; Nishi, M.; Haange, R.
2002. Fusion engineering and design, Proc.of the 6th Internat.Symp.on Fusion Nuclear Technology (ISFNT-6), San Diego, Calif., April 7-12, 2002,(2002), 61-62, 513–523. doi:10.1016/S0920-3796(02)00105-9
Fusion nuclear technology issues studied on the JET facilities
Lässer, R.; Bell, A. C.; Brennan, D.; Ciattaglia, S.; Coad, J. P.; Forrest, R. A.; Loughlin, M. J.; Newbert, G.; Patel, B.; Rolfe, A.; Scaffidi-Argentina, F.
2002. Fusion engineering and design, Proc.of the 6th Internat.Symp.on Fusion Nuclear Technology (ISFNT-6), San Diego, Calif., April 7-12, 2002,(2002), 63-64, 35–46. doi:10.1016/S0920-3796(02)00265-X
Results from the Mainz neutrino mass experiment
Bonn, J.; Bornschein, B.; Bornschein, L.; Fickinger, L.; Flatt, B.; Kovalik, A.; Kraus, C.; Müller, B.; Otten, E. W.; Schall, J. P.; Thümmler, T.; Ulrich, H.; Weinheimer, C.; Otten, E. W.
2002. Progress in particle and nuclear physics, 48 (1), 133–139. doi:10.1016/S0146-6410(02)00119-9
The effect of UV light irradiation on the removal of tritium from the codeposited carbon-tritium layer in fusion reactors
Venhaus, T. J.; Penzhorn, R. D.; Causey, R. A.; Bekris, N.
2002. Journal of nuclear materials, 302 (2-3), 224–226. doi:10.1016/S0022-3115(02)00808-5
The storage and delivery system of the ITER tritium fuel processing plant
Lässer, R.; Dörr, L.; Glugla, M.; Penzhorn, R. D.; Hayashi, T.; Murdoch, D. K.; Yoshida, H.
2002. Fusion Science and Technology, Proc.of the 6th Internat.Conf.on Tritium Science and Technology, Tsukuba, J, November 11-16, 2001, 41, 854–58
Use of ferrofluidic seals in the design of tritium compatible pumps
Lässer, R.; Murdoch, D. K.; Penzhorn, R. D.
2002. Fusion Science and Technology, Proc.of the 6th Internat.Conf.on Tritium Science and Technology, Tsukuba, J, November 11-16, 2001, 41, 621–25
The analytical system of the ITER tritium fuel processing plant
Lässer, R.; Glugla, M.; Schuster, P.; Hayashi, T.; Yoshida, H.
2002. Fusion Science and Technology, Proc.of the 6th Internat.Conf.on Tritium Science and Technology, Tsukuba, J, November 11-16, 2001, 41, 520–24
Use of gas chromatography in the tritium laboratory Karlsruhe
Lässer, R.; Glugla, M.; Grünhagen, S.; Günther, K.; Penzhorn, R. D.; Wendel, J.
2002. Fusion Science and Technology, Proc.of the 6th Internat.Conf.on Tritium Science and Technology, Tsukuba, J, November 11-16, 2001, 41, 515–19
Design of the inner tritium fuel cycle of ITER
Glugla, M.; Dörr, L.; Lässer, R.; Murdoch, D.; Yoshida, H.
2002. Jahrestagung Kerntechnik 2002, Stuttgart, 14.-16.Mai 2002 Bonn : INFORUM GmbH, 2002 (Auch auf CD-ROM), 489–92
Recovery of tritium from different sources by the ITER tokamak exhaust processing system
Glugla, M.; Dörr, L.; Lässer, R.; Murdoch, D. K.; Yoshida, H.
2002. Fusion engineering and design, Proc.of the 6th Internat.Symp.on Fusion Nuclear Technology (ISFNT-6), San Diego, Calif., April 7-12, 2002,(2002), 61-62, 569–574. doi:10.1016/S0920-3796(02)00250-8
Investigation of simultaneous tritium and deuterium transfer in a catalytic isotope exchange column for water detritiation
Cristescu, I.; Tamm, U.; Cristescu, I. R.; Glugla, M.; Caldwell-Nichols, C. J.
2002. Fusion engineering and design, Proc.of the 6th Internat.Symp.on Fusion Nuclear Technology (ISFNT-6), San Diego, Calif., April 7-12, 2002,(2002), 61-62, 537–542. doi:10.1016/S0920-3796(02)00164-3
Entwicklung von Technologien für die Kernfusion im Forschungszentrum Karlsruhe. Teil I
Bahm, W.; Dammertz, G.; Glugla, M.; Janeschitz, G.; Komarek, P.; Mack, A.
2002. ATW - Internationale Zeitschrift für Kernenergie, 47, 96–106
Overview of ITER fuel cycle R&D and design activities by the European home team
Murdoch, D.; Day, C.; Glugla, M.; Laesser, R.; Mack, A.; Penzhorn, R. D.; Busigin, A.; Maynard, K.; Kveton, O.
2002. Fusion Science and Technology, 6th Internat.Conf.on Tritium Science and Technology, Tsukuba, J, November 11-16, 2001, 41, 1018–22
Possible techniques for the detritiation of first wall materials from fusion machines
Bekris, N.; Caldwell-Nichols, C.; Dörr, L.; Glugla, M.; Penzhorn, R. D.; Ziegler, H.
2002. Journal of nuclear materials, 10th Internat.Conf.on Fusion Reactor Materials (ICFRM-10), Baden-Baden, October 14-19, 2001, 307-311 (Supplement 2), 1649–1654. doi:10.1016/S0022-3115(02)01131-5
Status and perspectives of tritium work performed at the Karlsruhe Research Center
Gross, S.; Day, C.; Glugla, M.; Raskob, W.
2002. Fusion Science and Technology, 6th Internat.Conf.on Tritium Science and Technology, Tsukuba, J, November 11-16, 2001, 41, 573–77
Development of specific catalysts for detritiation of gases by counter current isotopic swamping
Glugla, M.; Gross, S.; Lässer, R.; Le, T. L.; Niyongabo, D.; Simon, K. H.
2002. Fusion Science and Technology, Proc.of the 6th Internat.Conf.on Tritium Science and Technology, Tsukuba, J, November 11-16, 2001, 41, 969–73
Upgrade of the isotope separation system at the Tritium Laboratory Karlsruhe
Doerr, L.; Dehne, J.; Glugla, M.; Kissel, H.; Penzhorn, R. D.; Welte, S.; Hemmerich, J. L.
2002. Fusion Science and Technology, Proc.of the 6th Internat.Conf.on Tritium Science and Technology, Tsukuba, J, November 11-16, 2001, 41, 1155–59
Post service examination of tritium process components from the Tritium Laboratory Karlsruhe
Caldwell-Nichols, C. J.; Glugla, M.; Gross, S.; Lässer, R.; Le, T. L.; Penzhorn, R. D.; Simon, K. H.
2002. Fusion Science and Technology, Proc.of the 6th Internat.Conf.on Tritium Science and Technology, Tsukuba, J, November 11-16, 2001, 41, 617–20
The behaviour of zirconium-cobalt as a material for tritium storage
Besserer, U.; Penzhorn, R. D.; Brandt, R.
2002. Fusion Science and Technology, Proc.of the 6th Internat.Conf.on Tritium Science and Technology, Tsukuba, J, November 11-16, 2001, 41, 793–96
Investigation of separation performances of various isotope exchange catalysts for the deuterium-hydrogen system
Cristescu, I.; Cristescu, I. R.; Tamm, U.; Penzhorn, R. D.; Caldwell-Nichols, C.
2002. Fusion Science and Technology, Proc.of the 6th Internat.Conf.on Tritium Science and Technology, Tsukuba, J, November 11-16, 2001, 41, 1087–91
Tritium inventories in the high vacuum pumps of ITER
Day, C.; Mack, A.; Glugla, M.; Murdoch, D. K.
2002. Fusion Science and Technology, 6th Internat.Conf.on Tritium Science and Technology (TRITIUM 2001), Tsukuba, J, November 11-16, 2001, 41, 602–06
2001
Tritium in plasma facing components
Penzhorn, R. D.; Coad, J. P.; Bekris, N.; Doerr, L.; Friedrich, M.; Pilz, W.
2001. Fusion engineering and design, 21st Symp.on Fusion Technology (SOFT), Madrid, E, September 11-15, 2000,(2001), 56-57, 105–116. doi:10.1016/S0920-3796(01)00576-2
Tritium depth profiling by AMS in carbon samples from fusion experiments
Friedrich, M.; Pilz, W.; Sun, G.; Penzhorn, R. D.; Bekris, N.; Behrisch, R.; Garcia-Rosales, C.
2001. Physica Scripta, Proc.of the 5th Internat.Workshop on Hydrogen Isotopes in Solids, Stockholm, S, May 17-19, 2000, T94, 98–101
Enhanced Raman sensitivity using an actively stabilized external resonator
Taylor, D. J.; Glugla, M.; Penzhorn, R. D.
2001. Review of Scientific Instruments, 72, 1970–76. doi:10.1063/1.1353190
Tritium depth profiles in graphite and carbon fibre composite material exposed to tokamak plasmas
Penzhorn, R. D.; Bekris, N.; Berndt, U.; Coad, J. P.; Ziegler, H.; Nägele, W.
2001. Journal of Nuclear Materials, 288, 170–78
Model for the simulation of catalytic isotope exchange between tritiated water and hydrogen/deuterium
Cristescu, I. R.; Cristescu, I.; Penzhorn, R. D.; Tamm, U.
2001. Jahrestagung Kerntechnik 2001, Dresden, 15.-17.Mai 2001 Bonn : INFORUM GmbH, 2001 (Auch auf CD-ROM), 593–96
A Permcat reactor for impurity processing in the JET active gas handling system
Glugla, M.; Perevezentsev, A.; Niyongabo, D.; Penzhorn, R. D.; Bell, A.; Herrmann, P.
2001. Fusion Engineering and Design, Proc.of the 5th Internat.Symp.on Fusion Nuclear Technology (ISFNT), Roma, I, September 19-24, 1999 Part A,(2000), 49-50, 817–23
Experience gained during the modification of the Caprice system to Gaper
Glugla, M.; Lässer, R.; Le, T. L.; Penzhorn, R. D.; Simon, K. H.
2001. Fusion Engineering and Design, Proc.of the 5th Internat.Symp.on Fusion Nuclear Technology (ISFNT), Roma, I, September 19-24, 1999 Part A,(2000), 49-50, 811–16
Tritium technology for blankets of fusion power plants
Fütterer, M. A.; Albrecht, H.; Giroux, P.; Glugla, M.; Kawamura, H.; Kveton, O. K.; Murdoch, D. K.; Sze, D. K.
2001. Fusion Engineering and Design, Proc.of the 5th Internat.Symp.on Fusion Nuclear Technology (ISFNT), Roma, I, September 19-24, 1999 Part A,(2000), 49-50, 735–43
Fuel cycle design evolution from FDR-ITER to RTO/RC-ITER
Murdoch, D. K.; Glugla, M.; Kveton, O.
2001. Fusion Engineering and Design, Proc.of the 5th Internat.Symp.on Fusion Nuclear Technology (ISFNT), Roma, I, September 19-24, 1999 Part A,(2000), 49-50, 893–98
Tritium release from catalytic breeder materials
Munakata, K.; Yokoyama, Y.; Baba, A.; Kawagoe, T.; Takeishi, T.; Nishikawa, M.; Penzhorn, R. D.; Moriyma, H.; Kawamoto, K.; Morimoto, Y.; Okuno, K.
2001. Fusion engineering and design, Proc.of the 21st Symp.on Fusion Technology (SOFT), Madrid, E, September 11-15, 2000, 58-59, 683–687. doi:10.1016/S0920-3796(01)00530-0
Erosion/deposition issues at JET
Coad, J. P.; Bekris, N.; Elder, J. D.; Erents, S. K.; Hole, D. E.; Lawson, K. D.; Matthews, G. F.; Penzhorn, R. D.; Stangeby, P. C.
2001. Journal of Nuclear Materials, Proc.of the 14th Internat.Conf.on Plasma Surface Interactions in Controlled Fusion Devices, Rosenheim, May 22-26, 2000, 290-293, 224–30. doi:10.1016/S0022-3115(00)00479-7
2000
Determination of tritium profiles in tiles from the first wall of fusion machines and development of techniques for their detritiation
Haigh, A.; Bekris, N.; Hellriegel, W.; Nägele, W.; Noppel, H. E.; Peacock, A.; Penzhorn, R. D.; Rolli, R.; Werle, H.; Ziegler, H.
2000. JET-P(99)53 (January 2000)
Tritium profiles in tiles from the first wall of fusion machines and techniques for their detritiation
Penzhorn, R. D.; Bekris, N.; Hellriegel, W.; Noppel, H. E.; Nägele, W.; Ziegler, H.; Rolli, R.; Werle, H.; Haigh, A.; Peacock, A.
2000. Journal of Nuclear Materials, 279, 139–52
Tritium inventory in the first wall of JET
Peacock, A. T.; Andrew, P. A.; Brennan, D.; Coad, J. P.; Hemmerich, H.; Knipe, S.; Penzhorn, R. D.; Pick, M.
2000. Fusion engineering and design, Proc.of the 5th Internat.Symp.on Fusion Nuclear Technology (ISFNT), Roma, I, September 19-24, 1999 Part A,(2000), 49-50, 745–752. doi:10.1016/S0920-3796(00)00340-9
Tritium depth profiling in carbon by accelerator mass spectrometry
Friedrich, M.; Pilz, W.; Sun, G.; Behrisch, R.; Garcia-Rosales, C.; Bekris, N.; Penzhorn, R. D.
2000. Nuclear Instruments and Methods B, Proc.of the 14th Internat.Conf.on Ion Beam Analysis (IBA-14), Dresden, July 26-30, 1999, 161-163, 216–20
On the thermal stability of the zirconium/cobalt-hydrogen system
Bekris, N.; Besserer, U.; Sirch, M.; Penzhorn, D.
2000. Fusion engineering and design, Proc.of the 5th Internat.Symp.on Fusion Nuclear Technology (ISFNT), Roma, I, September 19-24, 1999 Part A,(2000), 49-50, 781–789. doi:10.1016/S0920-3796(00)00186-1
Process control under safety aspects
Vollmer, T.; Borcherding, K.; Hellriegel, G.; Penzhorn, R. D.
2000. Fusion Engineering and Design, 2nd IAEA Technical Committee Meeting on Control, Data Acquisition and Remote Participation on Fusion Research, Lisboa, P, July 19-21, 1999, 48, 57–61
Radiochemistry of an equimolar deuterium-tritium mixture or of T₂ with CO
Penzhorn, R. D.; Berndt, U.; Caldwell-Nichols, C.; Grünhagen, S.; Kirste, E.; Lässer, R.; Wendel, J.
2000. Fusion engineering and design, Proc.of the 5th Internat.Symp.on Fusion Nuclear Technology (ISFNT), Roma, I, September 19-24, 1999 Part A,(2000), 49-50, 927–937. doi:10.1016/S0920-3796(00)00343-4
Status and research progress at the tritium laboratory Karlsruhe
Penzhorn, R. D.; Bekris, N.; Coad, P.; Dörr, L.; Friedrich, L.; Glugla, M.; Haigh, A.; Lässer, R.; Peacock, A.
2000. Fusion engineering and design, Proc.of the 5th Internat.Symp.on Fusion Nuclear Technology (ISFNT), Roma, I, September 19-24, 1999 Part A,(2000), 49-50, 753–767. doi:10.1016/S0920-3796(00)00344-6
Tritium recovery from an ITER ceramic test blanket module : Process options and critical R and D issues
Albrecht, H.; Hutter, E.
2000. Fusion engineering and design, Proc.of the 5th Internat.Symp.on Fusion Nuclear Technology (ISFNT), Roma, I, September 19-24, 1999 Part A,(2000), 49-50, 769–773. doi:10.1016/S0920-3796(00)00183-6
1999
Basic research on nuclear track microfilters for gas separation
Sudowe, R.; Vater, P.; Ensinger, W.; Vetter, J.; Penzhorn, R. D.; Brandt, R.
1999. Radiation Measurements, 31, 691–96
Experimental plan to investigate critical R&D issues of a cryogenic cold trap
Albrecht, H.; Hutter, E.; Wendel, J.
1999. Wissenschaftliche Berichte, FZKA-6397 (Dezember 99). doi:10.5445/IR/270046648
Generation of hydrogen isotopes with an electric pulse hydride injector
Glushkov, I. S.; Kareev, Y. A.; Petrov, Y. V.; Savotkin, A. N.; Frunze, V. V.; Hutter, E.; Müller, G.; Penzhorn, R. D.; Tamm, U.
1999. International Journal of Hydrogen Energy, 24, 105–09
European helium cooled pebble bed (HCPB) test blanket. ITER design description document. Status 1.12.1998
Boccaccini, L. V.; Albrecht, H.; Boccaccini, L. V.; Berardinucci, L.; Dalle Donne, M.; Fiek, H. J.; Fischer, U.; Gordeev, S.; Hermsmeyer, S.; Hutter, E.; Kleefeldt, K.; Lechler, T.; Lenartz, M.; Norajitra, P.; Piazza, G.; Reimann, G.; Ruatto, P.; Scaffidi-Argentina, F.; Schleisiek, K.; Schmuck, I.; Schnauder, H.; Tsige-Tamirat, H.
1999. Wissenschaftliche Berichte, FZKA-6127 (März 99). doi:10.5445/IR/270045399
Long-term performance tests of components for fusion machine tritium plants
Penzhorn, R. D.; Berndt, U.; Besserer, U.; Glugla, M.; Kirste, E.; Murdoch, D.
1999. Jahrestagung Kerntechnik ’99, Karlsruhe, 18.-20.Mai 1999 Bonn : INFORUM GmbH, 1998, 557–60
Tritium inventory issues for future reactors: choices, parameters, limits
Murdoch, D. K.; Day, C.; Gierszewski, P.; Penzhorn, R. D.; Wu, C. H.
1999. Beaumont, B. [Hrsg.] Proc.of the 20th Internat.Symp.on Fusion Technology (SOFT), Marseille, F, September 7-11, 1998 Vol.1 S.18 Fusion Engineering and Design, 46(1999) S.255-71
Tritium inventory issues for future reactors: choices, parameters, limits
Murdoch, D. K.; Day, C.; Gierszewski, P.; Penzhorn, R. D.; Wu, C. H.
1999. Fusion Engineering and Design, Beaumont, B. [Hrsg.] Proc.of the 20th Internat.Symp.on Fusion Technology (SOFT), Marseille, F, September 7-11, 1998 Vol.1 S.18, S.255-71, 46
1998
Development of tritium technology for fusion at the tritium laboratory Karlsruhe
Penzhorn, R. D.; Besserer, U.; Doerr, L.; Glugla, M.; Hellriegel, W.; Röhrig, D.; Schubert, K.; Vollmer, T.; Wendel, J.
1998. Jahrestagung Kerntechnik ’98, München, 26.-28.Mai 1998 Bonn : INFORUM GmbH, 1998, 581–84
The european HCPB test blanket module to be tested in ITER
Boccaccini, L. V.; Albrecht, H.; Berardinucci, L.; Dalle Donne, M.; Fischer, U.; Gordeev, S.; Hermsmeyer, H.; Hutter, E. R.; Kleefeldt, K.; Lechler, T.; Lenartz, M.; Norajitra, P.; Piazza, G.; Reimann, G.; Ruatto, P.; Scaffidi-Argentina, F.; Schleisik, K.; Schmuck, I.; Schnauder, H.; Tsige-Tamirat, H.
1998. Beaumont, B. [Hrsg.] Proc.of the 20th Internat.Symp.on Fusion Technology (SOFT), Marseille, F, September 7-11, 1998 Vol.2, 1255–58
Helium loops of an ITER HCPB test blanket module
Albrecht, H.; Hutter, E.; Kleefeldt, K.; Penzhorn, R. D.
1998. 17th Symp.on Fusion Engineering (SOFE), San Diego, Calif., October 6-10, 1997 Proceeding Vol. 1 Piscataway, N.J. : Institute of Electrical and Electronics Engineers, Inc., 1998, 983–986
Development of an improved ceramic tritium breeder
Munakata, K.; Baba, A.; Nishikawa, M.; Penzhorn, D.
1998. Journal of Nuclear Science and Technology, 35, 511–14
European helium cooled pebble bed blanket: Design of blanket: module to be tested in ITER
Dalle Donne, M.; Albrecht, H.; Boccaccini, L. V.; Fischer, U.; Gordeev, S.; Hutter, E.; Kleefeldt, K.; Norajitra, P.; Reimann, G.; Ruatto, P.; Schleisiek, K.; Schnauder, H.
1998. Fusion Engineering and Design, Proc.of the 4th Internat.Symp.on Fusion Nuclear Technology (ISFNT-4), Tokyo, J, April 6-11, 1997 Part A, 39-40, 825–33
Routine operation of the gas chromatographic isotope separation system of the tritium laboratory Karlsruhe
Neffe, G.; Besserer, U.; Dehne, J.; Hutter, E.; Kissel, H.; Penzhorn, R. D.; Wendel, J.; Brunnader, H.
1998. Fusion Engineering and Design, Proc.of the 4th Internat.Symp.on Fusion Nuclear Technology (ISFNT-4), Tokyo, J, April 6-11, 1997 Part A, 39-40, 987–93
1997
Plasma exhaust gas processing for fusion reactors: developments and problems
Penzhorn, R. D.; Glugla, M.
1997. Internat.Tritium Workshop on Present Status and Prospect of Tritium-Material Interaction Studies, Toyama, J, July 18-19, 1996 Extended Abstracts, 17–28
AMOR facility: regeneration of molecular sieve beds used for the retention of tritium in the Tritium Laboratory Karlsruhe
Hutter, E.; Adami, H. D.; Besserer, U.; Penzhorn, R. D.
1997. Varandas, C. [Hrsg.] Fusion Technology 1996 : Proc.of the 19th Symp., Lisboa, P, September 16-20, 1996 Amsterdam [u.a.] : Elsevier, 1997 Vol.2, 1189–92
Results from tritium operation of the clean-up facility CAPRICE
Glugla, M.; Kraemer, R.; Le, T.; Simon, K. H.; Günther, K.; Wendel, J.; Penzhorn, R. D.
1997. Varandas, C. [Hrsg.] Fusion Technology 1996 : Proc.of the 19th Symp., Lisboa, P, September 16-20, 1996 Amsterdam [u.a.] : Elsevier, 1997 Vol.2, 1197–1200
Tritium tests with a PERMCAT reactor for isotopic swamping
Glugla, M.; Miller, J.; Herrmann, P.; Iseli, M.; Penzhorn, R. D.
1997. Varandas, C. [Hrsg.] Fusion Technology 1996 : Proc.of the 19th Symp., Lisboa, P, September 16-20, 1996 Amsterdam [u.a.] : Elsevier, 1997 Vol.2, 1193–96
Tritium experience at the tritium laboratory Karlsruhe
Besserer, U.; Dehne, J.; Doerr, L.; Glugla, M.; Hellriegel, W.; Le, T.; Schmitt, F.; Simon, K. H.; Vollmer, T.; Wendel, J.; Penzhorn, R. D.
1997. Varandas, C. [Hrsg.] Fusion Technology 1996 : Proc.of the 19th Symp., Lisboa, P, September 16-20, 1996 Amsterdam [u.a.] : Elsevier, 1997 Vol.2, 1261–64
Tritiumlabor: Arbeiten zur Brennstoffrückgewinnung und Abgasreinigung für ITER
Glugla, M.; Penzhorn, R. D.
1997. Nachrichten - Forschungszentrum Karlsruhe, 29, 71–80
Performance tests of palladium/silver permeators with tritium at the tritium laboratory Karlsruhe
Penzhorn, R. D.; Berndt, U.; Kirste, E.; Chabot, J.
1997. Fusion Technology, 32, 232–45
1995
Status of design of the ITER tritium plant
Haange, R.; Yoshida, H.; Kveton, O.; Koonce, J.; Horikiri, H.; Penzhorn, R. D.; Sood, S.; Okuno, K.; Konishi, S.; Yamanishi, T.; Hayashi, T.; Tebous, V. N.; Kapychev, V. K.; Perevezentsev, A. N.; Anderson, J. L.; Willms, S.; Sze, D. K.
1995. Herschbach, K. [Hrsg.] Fusion Technology 1994 : Proc.of the 18th Symp., Karlsruhe, August 22-26, 1994 Vol. 2 Amsterdam [u.a.] : Elsevier, 1995, 1047–50
Comparative study of Pd/Ag permeator concepts and their optimization for different applications in tritium facilities
Chabot, J.; Glugla, M.; Penzhorn, R. D.; Boisset, L.; Latge, C.; Leger, D.
1995. Herschbach, K. [Hrsg.] Fusion Technology 1994 : Proc.of the 18th Symp., Karlsruhe, August 22-26, 1994 Vol. 2 Amsterdam [u.a.] : Elsevier, 1995, 1067–70
Safety concept for the tritium laboratory Karlsruhe (TLK)
Vollmer, T.; Besserer, U.; Borcherding, K.; Dehne, J.; Dilger, H.; Dörr, L.; Glugla, M.; Hellriegel, W.; Hutter, E.; Kraemer, R.; Penzhorn, R. D.; Reinhardt, B.; Röhrig, D.; Schubert, K.
1995. Fusion Technology, Proc.of the 5th Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications, Belgirate, I, May 28 - June 3, 1995, 28, 988–94
Quantitative analysis of hydrogen isotopes with a mordenite column at 173 K by radio gas chromatography
Wendel, J.; Wertenbach, H.; Glugla, M.; Penzhorn, R. D.; Spelta, B.; Ricapito, I.; Baratti, G.; Dworschak, H.
1995. Fusion Technology, Proc.of the 5th Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications, Belgirate, I, May 28 - June 3, 1995, 28, 1090–94
Long-term permeator experiment PETRA at the Tritium Laboratory Karlsruhe: Commissioning tests with tritium
Penzhorn, R. D.; Berndt, U.; Kirste, E.; Hellriegel, W.; Jung, W.; Pejsa, R.; Romer, O.
1995. Fusion Technology, Proc.of the 5th Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications, Belgirate, I, May 28 - June 3, 1995, 28, 723–31
Hydrogen sorption rate by intermetallic compounds suitable for tritium storage
Penzhorn, R. D.; Sirch, M.; Perevezentsev, A. N.; Borisenko, A. N.
1995. Fusion Technology, Proc.of the 5th Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications, Belgirate, I, May 28 - June 3, 1995, 28, 1399–1403
Commissioning of the catalytic plasma exhaust clean-up facility CAPRICE and first experimental results
Glugla, M.; Kraemer, R.; Penzhorn, R. D.; Le, T.; Simon, K. H.; Günther, K.; Besserer, U.; Schäfer, P.; Hellriegel, W.; Geissler, H.
1995. Fusion Technology, Proc.of the 5th Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications, Belgirate, I, May 28 - June 3, 1995, 28, 625–29
Tritium related fusion R and D activities in Europe
Andreani, R.; Bell, A.; Murdoch, D.; Penzhorn, R. D.; Vassallo, G.
1995. Fusion Technology, Proc.of the 5th Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications, Belgirate, I, May 28 - June 3, 1995, 28, 449–59
Development of fusion fuel cycle technology at the tritium laboratory Karlsruhe: the experiment CAPRICE
Glugla, M.; Penzhorn, R. D.
1995. Fusion Engineering and Design, Proc.of the 3rd Internat.Symp.on Fusion Nuclear Technology, Los Angeles, Calif., June 27 - July 1, 1994 Part B, 28, 348–56
1993
Long-term permeator test PETRA in the TLK: first results and safety considerations
Penzhorn, R. D.
1993. Albrecht, H. [Hrsg.] Proc.of the 3rd ETHEL-TLK Workshop on Tritium Technology and Safety in Thermonuclear Fusion, Karlsruhe, May 24-25, 1993 Karlsruhe : KfK, 1993, 65–80
First experience with the operation of the TLK basic systems
Besserer, U.
1993. Albrecht, H. [Hrsg.] Proc.of the 3rd ETHEL-TLK Workshop on Tritium Technology and Safety in Thermonuclear Fusion, Karlsruhe, May 24-25, 1993 Karlsruhe : KfK, 1993, 41–45
2nd ETHEL-TLK Workshop on Tritium Technology and Safety in Thermonuclear Fusion, Ispra, I, February 6-7, 1992 Proc
Mannone, F.; Penzhorn, R. D.
1993. Commission of the European Communities, 1993
Tritium technology: tests with a TLK tritium retention system
Albrecht, H.; Berndt, U.; Glugla, M.; Noppel, H. E.; Kuhnes, U.; Simon, K. H.; Sirch, M.
1993. 2nd ETHEL-TLK Workshop on Tritium Technology and Safety in Thermonuclear Fusion, Ispra, I, February 6-7, 1992 Proc. Commission of the European Communities, 1993 /82, 3/75–3
Tritium technology: the integral plasma exhaust clean-up experiment CAPRICE
Glugla, M.
1993. 2nd ETHEL-TLK Workshop on Tritium Technology and Safety in Thermonuclear Fusion, Ispra, I, February 6-7, 1992 Proc. Commission of the European Communities, 1993 /20, 3/11–3
Research and development program at the TLK
Penzhorn, R. D.
1993. 2nd ETHEL-TLK Workshop on Tritium Technology and Safety in Thermonuclear Fusion, Ispra, I, February 6-7, 1992 Proc. Commission of the European Communities, 1993 /9, 3/3–3
Succint description and status of TLK
Jourdan, G.; Penzhorn, R. D.
1993. 2nd ETHEL-TLK Workshop on Tritium Technology and Safety in Thermonuclear Fusion, Ispra, I, February 6-7, 1992 Proc. Commission of the European Communities, 1993 /9, 2/5–2
The role of KfK-TLK
Penzhorn, R. D.
1993. 2nd ETHEL-TLK Workshop on Tritium Technology and Safety in Thermonuclear Fusion, Ispra, I, February 6-7, 1992 Proc. Commission of the European Communities, 1993 /5, 1/4–1
On the way to commissioning the tritium laboratory Karlsruhe (TLK)
Besserer, U.; Jourdan, G.; Hutter, E.
1993. Ferro, C. [Hrsg.] Fusion Technology 1992 : Proc.of the 17th Symp., Roma, I, September 14-18, 1992 Vol. 2 Amsterdam [u.a.] : North Holland, 1993, 1123–27
1992
The tritium laboratory Karlsruhe: laboratory design and equipment
Schira, P.; Hutter, E.; Jourdan, G.; Penzhorn, R. D.
1992. Fusion Engineering and Design, Proc.of the 2nd Internat.Symp.on Fusion Nuclear Technology, Karlsruhe, June 2-7, 1991 Part C,(1991), 18, 19–26
1990
The tritium laboratory Karlsruhe: R and D work and laboratory layout
Ache, H. J.; Glugla, M.; Hutter, E.; Jourdan, G.; Penzhorn, R. D.; Roehrig, D.; Schubert, K.; Sebening, H.; Vetter, J. E.
1990. Fusion Engineering and Design, 12, 331–41