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Title: Deployment Scenario of Heavy Water Cooled Thorium Breeder Reactor

Abstract

Deployment scenario of heavy water cooled thorium breeder reactor has been studied. We have assumed to use plutonium and thorium oxide fuel in water cooled reactor to produce {sup 233}U which will be used in thorium breeder reactor. The objective is to analysis the potential of water cooled Th-Pu reactor for replacing all of current LWRs especially in Japan. In this paper, the standard Pressurize Water Reactor (PWR) has been designed to produce 3423 MWt; (i) Th-Pu PWR, (ii) Th-Pu HWR (MFR = 1.0) and (iii) Th-Pu HWR (MFR 1.2). The properties and performance of the core were investigated by using cell and core calculation code. Th-Pu PWR or HWR produces {sup 233}U to introduce thorium breeder reactor. The result showed that to replace all (60 GWe) LWR by thorium breeder reactor within a period of one century, Th-Pu oxide fueled PWR has insufficient capability to produce necessary amount of {sup 233}U and Th-Pu oxide fueled HWR has almost enough potential to produce {sup 233}U but shows positive void reactivity coefficient.

Authors:
;  [1]
  1. Course of Applied Science, School of Engineering, Tokai University (Japan)
Publication Date:
OSTI Identifier:
21410479
Resource Type:
Journal Article
Journal Name:
AIP Conference Proceedings
Additional Journal Information:
Journal Volume: 1244; Journal Issue: 1; Conference: ICANSE 2009: 2. international conference on advances in nuclear science and engineering 2009, Bandung (Indonesia), 3-4 Nov 2009; Other Information: DOI: 10.1063/1.3462748; (c) 2010 American Institute of Physics; Journal ID: ISSN 0094-243X
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BREEDER REACTORS; COOLING SYSTEMS; HEAVY WATER; NUCLEAR FUELS; PERFORMANCE; PLUTONIUM; PWR TYPE REACTORS; REACTIVITY COEFFICIENTS; THORIUM; THORIUM OXIDES; THORIUM REACTORS; URANIUM 233; ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; CHALCOGENIDES; DEUTERIUM COMPOUNDS; ELEMENTS; ENERGY SOURCES; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; FUELS; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; HYDROGEN COMPOUNDS; ISOTOPES; MATERIALS; METALS; NEON 24 DECAY RADIOISOTOPES; NUCLEI; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; THORIUM COMPOUNDS; TRANSURANIUM ELEMENTS; URANIUM ISOTOPES; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES

Citation Formats

Mardiansah, Deby, and Takaki, Naoyuki. Deployment Scenario of Heavy Water Cooled Thorium Breeder Reactor. United States: N. p., 2010. Web. doi:10.1063/1.3462748.
Mardiansah, Deby, & Takaki, Naoyuki. Deployment Scenario of Heavy Water Cooled Thorium Breeder Reactor. United States. https://doi.org/10.1063/1.3462748
Mardiansah, Deby, and Takaki, Naoyuki. 2010. "Deployment Scenario of Heavy Water Cooled Thorium Breeder Reactor". United States. https://doi.org/10.1063/1.3462748.
@article{osti_21410479,
title = {Deployment Scenario of Heavy Water Cooled Thorium Breeder Reactor},
author = {Mardiansah, Deby and Takaki, Naoyuki},
abstractNote = {Deployment scenario of heavy water cooled thorium breeder reactor has been studied. We have assumed to use plutonium and thorium oxide fuel in water cooled reactor to produce {sup 233}U which will be used in thorium breeder reactor. The objective is to analysis the potential of water cooled Th-Pu reactor for replacing all of current LWRs especially in Japan. In this paper, the standard Pressurize Water Reactor (PWR) has been designed to produce 3423 MWt; (i) Th-Pu PWR, (ii) Th-Pu HWR (MFR = 1.0) and (iii) Th-Pu HWR (MFR 1.2). The properties and performance of the core were investigated by using cell and core calculation code. Th-Pu PWR or HWR produces {sup 233}U to introduce thorium breeder reactor. The result showed that to replace all (60 GWe) LWR by thorium breeder reactor within a period of one century, Th-Pu oxide fueled PWR has insufficient capability to produce necessary amount of {sup 233}U and Th-Pu oxide fueled HWR has almost enough potential to produce {sup 233}U but shows positive void reactivity coefficient.},
doi = {10.1063/1.3462748},
url = {https://www.osti.gov/biblio/21410479}, journal = {AIP Conference Proceedings},
issn = {0094-243X},
number = 1,
volume = 1244,
place = {United States},
year = {Tue Jun 22 00:00:00 EDT 2010},
month = {Tue Jun 22 00:00:00 EDT 2010}
}