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JAEA Reports

Helium purification system of High Temperature Gas-cooled Reactor

; ; ; Naito, Keiji; ; ;

JAERI 1051, 51 Pages, 1964/01

JAERI-1051.pdf:2.66MB

no abstracts in English

Journal Articles

20% enrihed, UO$$_{2}$$-graphite fuel disks for semi-homogeneous critical assembly

; ; K.Watanabe*; T.Ogra*

ATOMPRAXIS, (9), P. 337, 1961/00

no abstracts in English

Journal Articles

Developmental research on a thermal neutron breeder reactor

; Katsuragi, Satoru; ; ;

Atomu, 6(1), P. 42, 1961/00

no abstracts in English

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