Evaluation of Neutron Streaming and Future Shielding Measurement Plan in the Prototype FBR Monju

Sasaki, Katsuhiko; Usami, Shin; Deshimaru, Takehide; Nakashima, Fumiaki

doi:10.1080/00223131.2000.10874855

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Future Problem For Mcnp Calculation1

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2000

2014

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“…The verification and validation of this Monte Carlo methodology will be performed for the future shielding measurements plan in the prototype FBR Monju [11]. These results will be useful to improve the shielding analysis methods for future FBRs.…”

Section: Future Problem For Mcnp Calculationmentioning

confidence: 99%

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

Sasaki¹,

Naito²,

Ohki

et al. 2014

Progress in Nuclear Science and Technology

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This paper evaluates the secondary sodium activation in Direct Heat Exchanger (DHX), the radioactivity density and the dose rate around the secondary sodium pipes in Direct Reactor Auxiliary Cooling System (DRACS) of the Japan Sodium-cooled Fast Reactor (JSFR), by improving the exactness of a shielding calculation model with the Monte Carlo methodology. From this result, the prospects to meet the shielding design requirements for radioactivity free areas are obtained.

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Section: Future Problem For Mcnp Calculationmentioning

confidence: 99%