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Thorium fuel cycle analysis

Journal Article:

Abstract

Systems analysis of the thorium cycle, a nuclear fuel cycle accomplished by using thorium, is reported in this paper. Following a brief review on the history of the thorium cycle development, analysis is made on the three functions of the thorium cycle; (1) auxiliary system of U-Pu cycle to save uranium consumption, (2) thermal breeder system to exert full capacity of the thorium resource, (3) symbiotic system to utilize special features of /sup 233/U and neutron sources. The effects of the thorium loading in LWR (Light Water Reactor), HWR (Heavy Water Reactor) and HTGR (High Temperature Gas-cooled Reactor) are considered for the function of auxiliary system of U-Pu cycle. Analysis is made to find how much uranium is saved by /sup 233/U recycling and how the decrease in Pu production influences the introduction of FBR (Fast Breeder Reactor). Study on thermal breeder system is carried out in the case of MSBR (Molten Salt Breeder Reactor). Under a certain amount of fissile material supply, the potential system expansion rate of MSBR, which is determined by fissile material balance, is superior to that of FBR because of the smaller specific fissile inventory of MSBR. For symbiotic system, three cases are treated; i)  More>>
Authors:
Yamaji, K [1] 
  1. Central Research Inst. of Electric Power Industry, Tokyo (Japan)
Publication Date:
Jul 01, 1980
Product Type:
Journal Article
Reference Number:
AIX-13-669404; EDB-82-102514
Resource Relation:
Journal Name: Denryoku Chuo Kenkyusho Hokoku; (Japan); Journal Volume: 580002
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; THORIUM CYCLE; SYSTEMS ANALYSIS; BWR TYPE REACTORS; ENERGY ANALYSIS; ENERGY SOURCES; FBR TYPE REACTORS; HTGR TYPE REACTORS; HYBRIDIZATION; MOLTEN SALT REACTORS; PWR TYPE REACTORS; RESEARCH PROGRAMS; THORIUM; ACTINIDES; BREEDER REACTORS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FUEL CYCLE; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; METALS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 210802* - Nuclear Power Plants- Economics- Fuel Cycle
OSTI ID:
5486512
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Journal ID: CODEN: DCKHD
Submitting Site:
HEDB
Size:
Pages: 1-4, 1-26
Announcement Date:
Apr 01, 1982

Journal Article:

Citation Formats

Yamaji, K. Thorium fuel cycle analysis. Japan: N. p., 1980. Web.
Yamaji, K. Thorium fuel cycle analysis. Japan.
Yamaji, K. 1980. "Thorium fuel cycle analysis." Japan.
@misc{etde_5486512,
title = {Thorium fuel cycle analysis}
author = {Yamaji, K}
abstractNote = {Systems analysis of the thorium cycle, a nuclear fuel cycle accomplished by using thorium, is reported in this paper. Following a brief review on the history of the thorium cycle development, analysis is made on the three functions of the thorium cycle; (1) auxiliary system of U-Pu cycle to save uranium consumption, (2) thermal breeder system to exert full capacity of the thorium resource, (3) symbiotic system to utilize special features of /sup 233/U and neutron sources. The effects of the thorium loading in LWR (Light Water Reactor), HWR (Heavy Water Reactor) and HTGR (High Temperature Gas-cooled Reactor) are considered for the function of auxiliary system of U-Pu cycle. Analysis is made to find how much uranium is saved by /sup 233/U recycling and how the decrease in Pu production influences the introduction of FBR (Fast Breeder Reactor). Study on thermal breeder system is carried out in the case of MSBR (Molten Salt Breeder Reactor). Under a certain amount of fissile material supply, the potential system expansion rate of MSBR, which is determined by fissile material balance, is superior to that of FBR because of the smaller specific fissile inventory of MSBR. For symbiotic system, three cases are treated; i) nuclear heat supply system using HTGR, ii) denatured fuel supply system for nonproliferation purpose, and iii) hybrid system utilizing neutron sources other than fission reactor.}
journal = {Denryoku Chuo Kenkyusho Hokoku; (Japan)}
volume = {580002}
journal type = {AC}
place = {Japan}
year = {1980}
month = {Jul}
}