Radioactivity evaluation of the secondary sodium in DRACS of the Japan Sodium-cooled Fast Reactor

Sasaki, Kenji*; Naito, Katsuaki*; Oki, Shigeo; Okubo, Tsutomu; Kotake, Shoji*

Progress in Nuclear Science and Technology (Internet), 4, p.94 - 98, 2014/04

http://www.aesj.or.jp/publication/pnst004/data/094_098.pdf

This paper evaluates the amount of activation of the secondary sodium in Direct Heat Exchanger (DHX) by neutrons leaked from the core, the radioactivity density, and the dose rate around the secondary sodium pipes in Direct Reactor Auxiliary Cooling System (DRACS) and confirms that the requirements in radioactivity free areas are satisfied by improving the exactness of calculation model with Monte Carlo Methodology.

APPLICABILITY OF THE 3D TRANSPORT CODE TORT THE SHIELDING ANALYSIS OF THE REACTOR CAVITY SHIELDING FLOOR IN THE PROTOTYPE FBR MONJU

; Usami, Isao; *

Proceedings of International Conference on the Physics of Reactors (PHYSOR 2000), 0 Pages, 2000/00

None

Results and future plans for shielding measurements in the prototype FBR MONJU

Dai-9-Kai Hoshasen Shahei Kokusai Kaigi (ICRS-9), 0 Pages, 1999/00

None

Reactor physics measurements at start-up of MONJU

Nakashima, Fumiaki; ; Usami, Isao; ; ; 2 of others*

Proceedings of International Conference on the Physics of Reactors (PHYSOR '96), E-76- Pages, 1996/00

None

Reactor shielding design of the High Temperature Engineering Test Reactor; Analysis of radiation streaming through the standpipes by Monte Carlo code MCNP

Murata, Isao; Shindo, Ryuichi; *; *; *

Proc. of the 8th Int. Conf. on Radiation Shielding, p.359 - 364, 1994/00

no abstracts in English

None

International Nuclear Congress ENC'98, , 

Shielding design of JSFR; Evaluation of the ORNL sodium transmission measurements by using Monte Carlo code MCNP

Sasaki, Kenji*; Naito, Katsuaki*; Oki, Shigeo; Okubo, Tsutomu; Kotake, Shoji*

no journal, , 

no abstracts in English