In-situ HT release behavior from molten Li2BeF4 salt

Fusion Engineering and Design

Volumn 39-40, Issue , 1998, Pages 781-785

  Suzuki, A ^a   Terai, T ^a   Tanaka, S ^a  

^a UNIVERSITY OF TOKYO   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

LITHIUM COMPOUNDS; MASS TRANSFER; MOLTEN MATERIALS; SALTS; TRITIUM;

FLIBE; TRITIUM RELEASE;

BREEDING BLANKETS;

EID: 0032156160     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(98)00381-0     Document Type: Article

References (8)

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2. A. Sagara, O. Motojima, K. Watanabe, et al., Blanket and divertor design for force free helical reactor (FFHR), Fusion Eng. Des. 29 (1995) 51.
3. T. Terai, In-situ tritium release behavior from CTR liquid breeding materials under 14 MeV neutron irradiation, J. Nucl. Sci. Technol. 27 (1990) 667.
4. 2 mixture, J. Nucleic Mater. 148 (1986) 211.
5. J. Oishi, H. Moriyama, S. Maeda, Y. Asaoka, Tritium recovery from molten LiF-BeF, salt, Fusion Eng. Des. 8 (1989) 317.
6. 4 salt under neutron irradiation, Proc. SOFT-19 (1996) 1459.
7. 4 salt under neutron irradiation at elevated temperatures (FNTREXFLIBE), Fusion Technol. 30 (1996) 911.
8. 2 mixtures, MSR Program Prog. Report, Oak Ridge National Laboratory, ORNL-2626, October 1958, p. 94.