You need JavaScript to view this

Thorium fuel for light water reactors - reducing proliferation potential of nuclear power fuel cycle

Abstract

The proliferation potential of the light water reactor fuel cycle may be significantly reduced by utilization of thorium as a fertile component of the nuclear fuel. The main challenge of Th utilization is to design a core and a fuel cycle, which would be proliferation-resistant and economically feasible. This challenge is met by the Radkowsky Thorium Reactor (RTR) concept. So far the concept has been applied to a Russian design of a 1,000 MWe pressurized water reactor, known as a WWER-1000, and designated as VVERT. The following are the main results of the preliminary reference design: * The amount of Pu contained in the RTR spent fuel stockpile is reduced by 80% in comparison with a VVER of a current design. * The isotopic composition of the RTR-Pu greatly increases the probability of pre-initiation and yield degradation of a nuclear explosion. An extremely large Pu-238 content causes correspondingly large heat emission, which would complicate the design of an explosive device based on RTR-Pu. The economic incentive to reprocess and reuse the fissile component of the RTR spent fuel is decreased. The once-through cycle is economically optimal for the RTR core and cycle. To summarize all the items above: the replacement  More>>
Authors:
Galperin, A; Radkowski, A [1] 
  1. Ben-Gurion Univ. of the Negev, Beersheba (Israel)
Publication Date:
Dec 01, 1996
Product Type:
Conference
Report Number:
INIS-mf-15507; CONF-961252-
Reference Number:
SCA: 210200; PA: AIX-28:023771; EDB-97:072351; SN: 97001788862
Resource Relation:
Journal Volume: 6; Journal Issue: 3; Conference: 19. conference of the Israel Nuclear Societies, Herzliya (Israel), 9-10 Dec 1996; Other Information: PBD: Dec 1996; Related Information: Is Part Of Program and book of abstracts; PB: 149 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; WWER-5 REACTOR; THORIUM CYCLE; NUCLEAR FUELS; PROLIFERATION; REACTOR LATTICES
OSTI ID:
475975
Research Organizations:
Israel Nuclear Society, Yavne (Israel)
Country of Origin:
Israel
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 0892--9882; Other: ON: DE97616259; TRN: IL9606203023771
Availability:
INIS; OSTI as DE97616259
Submitting Site:
INIS
Size:
pp. 1-7
Announcement Date:

Citation Formats

Galperin, A, and Radkowski, A. Thorium fuel for light water reactors - reducing proliferation potential of nuclear power fuel cycle. Israel: N. p., 1996. Web. doi:10.1080/08929889708426440.
Galperin, A, & Radkowski, A. Thorium fuel for light water reactors - reducing proliferation potential of nuclear power fuel cycle. Israel. doi:10.1080/08929889708426440.
Galperin, A, and Radkowski, A. 1996. "Thorium fuel for light water reactors - reducing proliferation potential of nuclear power fuel cycle." Israel. doi:10.1080/08929889708426440. https://www.osti.gov/servlets/purl/10.1080/08929889708426440.
@misc{etde_475975,
title = {Thorium fuel for light water reactors - reducing proliferation potential of nuclear power fuel cycle}
author = {Galperin, A, and Radkowski, A}
abstractNote = {The proliferation potential of the light water reactor fuel cycle may be significantly reduced by utilization of thorium as a fertile component of the nuclear fuel. The main challenge of Th utilization is to design a core and a fuel cycle, which would be proliferation-resistant and economically feasible. This challenge is met by the Radkowsky Thorium Reactor (RTR) concept. So far the concept has been applied to a Russian design of a 1,000 MWe pressurized water reactor, known as a WWER-1000, and designated as VVERT. The following are the main results of the preliminary reference design: * The amount of Pu contained in the RTR spent fuel stockpile is reduced by 80% in comparison with a VVER of a current design. * The isotopic composition of the RTR-Pu greatly increases the probability of pre-initiation and yield degradation of a nuclear explosion. An extremely large Pu-238 content causes correspondingly large heat emission, which would complicate the design of an explosive device based on RTR-Pu. The economic incentive to reprocess and reuse the fissile component of the RTR spent fuel is decreased. The once-through cycle is economically optimal for the RTR core and cycle. To summarize all the items above: the replacement of a standard (U-based) fuel for nuclear reactors of current generation by the RTR fuel will provide an inherent barrier for nuclear weapon proliferation. This inherent barrier, in combination with existing safeguard measures and procedures is adequate to unambiguously disassociate civilian nuclear power from military nuclear power. * The RTR concept is applied to existing power plants to assure its economic feasibility. Reductions in waste disposal requirements, as well as in natural U and fabrication expenses, as compared to a standard WWER fuel, provide approximately 20% reduction in fuel cycle (authors).}
doi = {10.1080/08929889708426440}
issue = {3}
volume = {6}
place = {Israel}
year = {1996}
month = {Dec}
}