skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Cell configuration effect on feasibility of water cooled thorium breeder reactor

Abstract

As a fuel candidate, thorium cycle shows some advantages such as good breeding capability, higher performance of burn-up and from proliferation point of view, thorium is more proliferation resistant. The shipping-port reactor and molten salt breeder reactor showed that breeding is possible with thorium in a thermal spectrum. Breeding is made possible by the high value of neutron regeneration ratio {eta} for {sup 233}U in thermal energy region. In the present study, feasibility of water cooled thorium breeder reactor is investigated. A calculation method by coupling the equilibrium fuel cycle burn-up calculation and cell calculation of PIJ module of SRAC2002 code have been performed. The reactor is fueled by {sup 233}U-Th Oxide and it has used the light water coolant and zircaloy-4 as moderator and cladding, respectively. The key properties such as flux, enrichment, criticality and breeding performances are evaluated for different moderator to fuel ratios (MFR) and burn-ups. The different pin cell types have been investigated in order to analyze the effect of different fuel pin diameter. The results show the feasibility of breeding for different fuel pin cell types. The required {sup 233}U enrichment is about 2% - 9% as initial fissile loading. The lower MFR and themore » higher enrichment of {sup 233}U are preferable to improve the average burn-up; however the design feasible window is shrunk. The thicker pin cell shows wider feasible areas and requires lower enrichment than thinner pin cell. It means that thicker fuel pin diameter obtains better performances for breeding and reducing the fissile material utilization. (authors)« less

Authors:
; ;  [1]
  1. Research Laboratory for Nuclear Reactors, Tokyo Inst. of Technology, 2-12-1-N1-17, O-okayama, Meguro-ku, Tokyo 152-8550 (Japan)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
22039668
Resource Type:
Conference
Resource Relation:
Conference: PHYSOR-2006: American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, Vancouver, BC (Canada), 10-14 Sep 2006; Other Information: Country of input: France; 7 refs.
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BREEDER REACTORS; BURNUP; CALCULATION METHODS; CLADDING; CONFIGURATION; CRITICALITY; DESIGN; FUEL PINS; MODERATOR-FUEL RATIO; MOLTEN SALT REACTORS; NEUTRON SPECTRA; PROLIFERATION; REACTOR CELLS; THERMAL NEUTRONS; THORIUM; THORIUM CYCLE; THORIUM OXIDES; URANIUM 233; WATER COOLED REACTORS; ZIRCALOY 4

Citation Formats

Permana, S, Takaki, N, and Sekimoto, H. Cell configuration effect on feasibility of water cooled thorium breeder reactor. United States: N. p., 2006. Web.
Permana, S, Takaki, N, & Sekimoto, H. Cell configuration effect on feasibility of water cooled thorium breeder reactor. United States.
Permana, S, Takaki, N, and Sekimoto, H. Sat . "Cell configuration effect on feasibility of water cooled thorium breeder reactor". United States.
@article{osti_22039668,
title = {Cell configuration effect on feasibility of water cooled thorium breeder reactor},
author = {Permana, S and Takaki, N and Sekimoto, H},
abstractNote = {As a fuel candidate, thorium cycle shows some advantages such as good breeding capability, higher performance of burn-up and from proliferation point of view, thorium is more proliferation resistant. The shipping-port reactor and molten salt breeder reactor showed that breeding is possible with thorium in a thermal spectrum. Breeding is made possible by the high value of neutron regeneration ratio {eta} for {sup 233}U in thermal energy region. In the present study, feasibility of water cooled thorium breeder reactor is investigated. A calculation method by coupling the equilibrium fuel cycle burn-up calculation and cell calculation of PIJ module of SRAC2002 code have been performed. The reactor is fueled by {sup 233}U-Th Oxide and it has used the light water coolant and zircaloy-4 as moderator and cladding, respectively. The key properties such as flux, enrichment, criticality and breeding performances are evaluated for different moderator to fuel ratios (MFR) and burn-ups. The different pin cell types have been investigated in order to analyze the effect of different fuel pin diameter. The results show the feasibility of breeding for different fuel pin cell types. The required {sup 233}U enrichment is about 2% - 9% as initial fissile loading. The lower MFR and the higher enrichment of {sup 233}U are preferable to improve the average burn-up; however the design feasible window is shrunk. The thicker pin cell shows wider feasible areas and requires lower enrichment than thinner pin cell. It means that thicker fuel pin diameter obtains better performances for breeding and reducing the fissile material utilization. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2006},
month = {7}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: