A new arrangement for the air cleanup system to recover tritiumNISHIKAWA, M; TAKAHASHI, K; MUNAKATA, K et al.Fusion technology. 1997, Vol 31, Num 2, pp 175-184, issn 0748-1896Article

Performance of a large-scale glovebox-stripper systemHEUNG, L. K; RHODEN, M. L.Fusion science and technology. 2002, Vol 41, Num 3, pp 583-587, 5 p., 2Conference Paper

Removal and control of tritium in lithium target for international fusion materials irradiation facility (IFMIF)NAKAMURA, H; IDA, M; SUGIMOTO, M et al.Fusion science and technology. 2002, Vol 41, Num 3, pp 845-849, 5 p., 2Conference Paper

The rate process of tritium recovery from Li₁₇Pb₈₃ alloyTSUCHIYA, K; AIDA, M; FUJII, Y et al.Journal of nuclear materials. 1993, Vol 207, pp 339-344, issn 0022-3115Article

Adsorption isotherm and separation factor for multicomponent hydrogen isotopes in cryosorption method for recovery of tritium from blanket sweep gasNISHIKAWA, M; TANAKA, K; UETAKE, M et al.Fusion technology. 1995, Vol 28, Num 3, pp 711-716, issn 0748-1896, 1Conference Paper

Commissioning of the catalytic plasma exhaust clean-up facility CAPRICE and first experimental resultsGLUGLA, M; KRAEMER, R; PENZHORN, R.-D et al.Fusion technology. 1995, Vol 28, Num 3, pp 625-629, issn 0748-1896, 1Conference Paper

Design study of sweep gas system for fusion blanket development in the JMTRSAGAWA, H; KAWAMURA, H; IKEJIMA, Y et al.Fusion technology. 1995, Vol 28, Num 3, pp 732-735, issn 0748-1896, 1Conference Paper

Tritium removal from JET and TFTR tiles by a scanning laserSKINNER, C. H; BEKRIS, N; COAD, J. P et al.Journal of nuclear materials. 2003, Vol 313-16, pp 496-500, issn 0022-3115, 5 p.Conference Paper

Optimization of a thermal cycling absorption process design by dynamic simulationLAQUERBE, C; DUCRET, D; BALLANGER, A et al.Fusion science and technology. 2002, Vol 41, Num 3, pp 1121-1125, 5 p., 2Conference Paper

Study on a method to recover tritium from blanket sweep gasNISHIKAWA, M; TANAKA, K.-I; UETAKE, M et al.Fusion technology. 1994, Vol 26, Num 1, pp 17-26, issn 0748-1896Article

Development of a heavy water detritiation plant for PIK reactorALEKSEEV, I. A; BONDARENKO, S. D; FEDORCHENKO, O. A et al.Fusion science and technology. 2005, Vol 48, Num 1, pp 286-289, 4 p.Conference Paper

Recent palladium membrane reactor development at the tritium systems test assemblyWILLMS, R. S; BIRDSELL, S. A; WILHELM, R. C et al.Fusion technology. 1995, Vol 28, Num 3, pp 772-777, issn 0748-1896, 1Conference Paper

Recovery of hydrogen isotopes and impurity mixture by cryogenic molecular sieve bed for GDC gas cleanupENOEDA, M; KAWAMURA, Y; OKUNO, K et al.Fusion technology. 1995, Vol 28, Num 3, pp 591-596, issn 0748-1896, 1Conference Paper

Development of solid breeder blanker at JAERIENOEDA, Mikio; HATANO, Toshihisa; TSUCHIYA, Kunihiko et al.Fusion science and technology. 2005, Vol 47, Num 4, pp 1060-1067, 8 p.Conference Paper

Testing of a prototype saes st909 getter bed for conditioning gas to a trituim stripper systemHSU, Robert H; HOLDER, Jeffrey S.Fusion science and technology. 2005, Vol 48, Num 1, pp 171-174, 4 p.Conference Paper

Design of the OMEGA laser target chamber tritium removal systemNOBILE, Arthur; REICHERT, Heidi; JANEZIC, Roger T et al.Fusion science and technology. 2003, Vol 43, Num 4, pp 522-539, 18 p.Article

Behavior of tritium in the TSTA test cell combined with operation of the Experimental Tritium Cleanup (ETC) systemWILLMS, R. S; KOBAYASHI, K; IWAI, Y et al.Fusion engineering and design. 2002, Vol 61-62, pp 575-583, issn 0920-3796, 9 p.Conference Paper

Recovery of tritium from pharmaceutical mixed waste liquidsSHMAYDA, W. T; GALLAGHER, R. D.Fusion science and technology. 2002, Vol 41, Num 3, pp 726-730, 5 p., 2Conference Paper

Correlation between tritium release and thermal annealing of damages in neutron-irradiated Li₄SiO₄MORIMOTO, Y; AKAHORI, S; KAWAMOTO, K et al.Fusion technology. 2001, Vol 39, Num 2, pp 634-638, issn 0748-1896, 2Conference Paper

Design and qualification of an on-line permeator for the recovery of tritium from lead―lithium eutectic breeding alloyVEREDAS, G; FRADERA, J; SEDANO, L et al.Fusion engineering and design. 2011, Vol 86, Num 9-11, pp 2365-2369, issn 0920-3796, 5 p.Conference Paper

Recovery of hydrogen from gas mixture by an intermediate-temperature type proton conductorTANAKA, M; OHSHIMA, T.Fusion engineering and design. 2010, Vol 85, Num 7-9, pp 1038-1043, issn 0920-3796, 6 p.Conference Paper

Tritium isotope separation using adsorption-distillation columnFUKADA, Satoshi.Fusion science and technology. 2005, Vol 48, Num 1, pp 140-143, 4 p.Conference Paper

Computer simulation of tritium inventory and leakage of the fusion experimental reactor FEB-EBAIQUAN DENG; ZAIXIN LI; JINHUA HUANG et al.Fusion science and technology. 2004, Vol 46, Num 4, pp 548-560, 13 p.Article

Computer simulation of the processing of tritium in exhaust gas from the LHDKAWANO, T; SAKUMA, Y; KABUTOMORI, T et al.Fusion engineering and design. 2002, Vol 61-62, pp 543-551, issn 0920-3796, 9 p.Conference Paper

Screen test of tritium recovery from stainless steel type 316PEREVEZENTSEV, A; WATANABE, K; MATSUYAMA, M et al.Fusion science and technology. 2002, Vol 41, Num 3, pp 706-710, 5 p., 2Conference Paper