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

Research output: Contribution to conferencePaperpeer-review

Abstract

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.

Original languageEnglish
Publication statusPublished - 2014
Externally publishedYes
Event2014 International Conference on Physics of Reactors, PHYSOR 2014 - Kyoto, Japan
Duration: Sep 28 2014Oct 3 2014

Conference

Conference2014 International Conference on Physics of Reactors, PHYSOR 2014
Country/TerritoryJapan
CityKyoto
Period9/28/1410/3/14

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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