Comparative studies on plutonium and 233U utilization in miniFUJI MSR

A. Waris, S. Pramuditya, K. Basar, I. K. Aji, R. Wirawan, F. Monado, M. N. Subkhi

研究成果: Contribution to conferencePaper査読

抄録

Molten salt reactor (MSR) has many merits such as safety enhancement and capability to be used for hydrogen production. A comparative evaluation of plutonium and 233U utilization in miniFUJI MSR has been performed. Reactor grade plutonium (RGPu), weapon grade plutonium (WGPu), and super grade plutonium (SGPu) have been utilized in the present study. The reactors can obtain their criticality condition with the 233U concentration in the Th-233U fuel, RGPu concentration in Th-RGPu fuel, WGPu concentration in Th-WGPu fuel, and SGPu concentration in Th-SGPu fuel of 0.52%, 5.76%, 2.16%, and 1.96%, respectively. The Th-233U fuel results in the soft neutron spectra of miniFUJI reactor. The neutron spectra turn into harder with the enlarging of plutonium concentration in loaded fuel where Th-RGPu fuel gives the hardest neutron spectra.

本文言語英語
出版ステータス出版済み - 2014
外部発表はい
イベント2014 International Conference on Physics of Reactors, PHYSOR 2014 - Kyoto, 日本
継続期間: 9 28 201410 3 2014

会議

会議2014 International Conference on Physics of Reactors, PHYSOR 2014
国/地域日本
CityKyoto
Period9/28/1410/3/14

All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 原子力エネルギーおよび原子力工学

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