Conditions for effective utilization of the electronuclear blanket system as a neutron sourceVASIL'EV, V. V; SHVEDOV, O. V.Atomic energy (New York, N.Y.). 1999, Vol 87, Num 4, pp 710-716, issn 1063-4258Article

Lithium blanket module (LBM) dosimetry measurements at the LOTUS 14-MeV neutron source facilityTSANG, F. Y; LEO, W; SAHRAOUI, C et al.Fusion technology. 1986, Vol 10, Num 3, pp 962-971, issn 0748-1896, 2A-BConference Paper

THE EFFECT OF WATER ON TRITIUM RELEASE BEHAVIOR FROM SOLID BREEDER CANDIDATESSUEMATSU, K; NISHIKAWA, M; FUKADA, S et al.Fusion science and technology. 2008, Vol 54, Num 2, pp 561-564, 4 p.Conference Paper

Fusion reactor blanketTANAKA, Satoru.Journal of Nuclear Science and Technology. 2001, Vol 38, Num 11, issn 0022-3131, 101 p.Serial Issue

Initial corrosion evaluation of zirconium alloy candidate materials for the ASCB conceptBOGAERTS, W. F; DEUTSCH, L; EMBRECHTS, M. J et al.Fusion technology. 1986, Vol 10, Num 3, pp 995-999, issn 0748-1896, 2A-BConference Paper

EFFECT OF OXYGEN ON CORROSION OF ERBIUM OXIDE IN LITHIUMNAGURA, Masaru; SUZUKI, Akihiro; MUROGA, Takeo et al.Fusion science and technology. 2009, Vol 56, Num 2, pp 841-845, issn 1536-1055, 5 p.Article

Extending ITER materials design to welded jointsTAVASSOLI, A.-A. F.Journal of nuclear materials. 2007, Vol 367-370, pp 1316-1324, issn 0022-3115, 9 p., bConference Paper

Preliminary neutronics design of the dual-cooled lithium lead blanket for FDS-IIJINGJING LI; SHANLIANG ZHENG; QIN ZENG et al.Fusion engineering and design. 2005, Vol 75-79, pp 715-719, issn 0920-3796, 5 p.Conference Paper

Isotope effect in cryosorption of tritium to molecular sieves and activated carbon at 77 KNISHIKAWA, M; TANAKA, K.-I; UETAKE, M et al.Fusion technology. 1998, Vol 34, Num 3, pp 234-240, issn 0748-1896, 1Article

LIBRETTO-3 : performance of tritium permeation barriers under irradiation at the HFR PettenCONRAD, R; FÜTTERER, M. A; GIANCARLI, L et al.Journal of nuclear materials. 1994, Vol 212-15, Num B, pp 998-1002, issn 0022-3115Conference Paper

First wall tile attachment using carbon-carbon composite fittingsLUTZ, G. R; TARASEN, W. L.Fusion technology. 1986, Vol 10, Num 3, pp 1000-1005, issn 0748-1896, 2A-BConference Paper

INFLUENCE OF OXYGEN ON PERMEATION OF HYDROGEN ISOTOPES THROUGH GROUP 5 METALSHATANO, Yuji; BUSNYUK, Andrei; ALIMOV, Vasily et al.Fusion science and technology. 2008, Vol 54, Num 2, pp 526-529, 4 p.Conference Paper

Les modules de test de couverture tritigène : un pas vers l'autosuffisance en tritium = Test Blanket Modules : a Step toward Fuel ProductionGIANCARLI, L.Revue générale nucléaire. 2007, Num 1, pp 67-68, issn 0335-5004, 2 p.Conference Paper

Breeding Blanket Modules testing in ITER : An international program on the way to DEMOGIANCARLI, L; CHUYANOV, V; ABDOU, M et al.Fusion engineering and design. 2006, Vol 81, Num 1-7, pp 393-405, issn 0920-3796, 13 p.Conference Paper

On the nuclear response of the helium-cooled lithium lead test blanket module in ITERCHIOVARO, P; DI MAIO, P. A; VELLA, G et al.Fusion engineering and design. 2005, Vol 75-79, pp 725-730, issn 0920-3796, 6 p.Conference Paper

ANFIBE : A comprehensive model for swelling and tritium release from neutron-irradiated beryllium-II : Comparison of model predictions with experimental resultsSCAFFIDI-ARGENTINA, F; DALLE DONNE, M; RONCHI, C et al.Fusion technology. 1998, Vol 33, Num 2, pp 146-163, issn 0748-1896Article

Magnetohydrodynamic pressure-driven flows in the HCLL blanketBÜHLER, L.Fusion engineering and design. 2005, Vol 75-79, pp 923-926, issn 0920-3796, 4 p.Conference Paper

Blanket handling concepts for future fusion power plantsBOGUSCH, E; GOTTFRIED, R; MAISONNIER, D et al.Fusion engineering and design. 2003, Vol 69, Num 1-4, pp 135-139, issn 0920-3796, 5 p.Conference Paper

Thermodynamic performance of ceramic tritium breeding blanket materialJOHNSON, C. E; FISCHER, A. K.Fusion technology. 1986, Vol 10, Num 3, pp 985-989, issn 0748-1896, 2A-BConference Paper

Application of multiband Sn method to fast reactor blanket analysisYAMAMOTO, T; KATAGI, Y; OHYA, K et al.Technology reports of the Osaka University. 1997, Vol 47, Num 226782, pp 21-27, issn 0030-6177Article

Seventeenth Topical Meeting on the Technology of Fusion Energy (Part 2), Albuquerque, New Mexico, November 12-16, 2006Fusion science and technology. 2007, Vol 52, Num 4, 372 p.Conference Proceedings

Solving the stand-off problem for magnetized target fusion : Plasma streams as disposable electrodes, together with a local spherical blanketRYUTOV, D. D; THIO, Y. C. F.Journal of fusion energy. 2007, Vol 26, Num 1-2, pp 173-177, issn 0164-0313, 5 p.Conference Paper

Numerical study of magnetic field configuration for FFHR from a viewpoint of divertor and edge field structureMORISAKI, T; IMAGAWA, S; SAGARA, A et al.Fusion engineering and design. 2006, Vol 81, Num 23-24, pp 2749-2754, issn 0920-3796, 6 p.Conference Paper

The HFR Petten high dose irradiation programme of beryllium for blanket applicationHEGEMAN, J. B. J; VAN DER LAAN, J. G; KAWAMURA, H et al.Fusion engineering and design. 2005, Vol 75-79, pp 769-773, issn 0920-3796, 5 p.Conference Paper

Progetto concettuale di un mantello a breeder solido raffreddato ad acqua di tipo BOT per il reattore a fusione NET = Conceptual design of a solid breeder, water cooled BOT type blanket for the NET fusion reactorCERULLO, N; MANFREDI, E; ROSATELLI, F et al.Termotecnica (Milano). 1989, Vol 43, Num 10, pp 49-57, issn 0040-3725, 9 p.Article