Cargando…

Feasibility Study of Thorium-Plutonium Mixed Oxide Assembly In Light Water Reactors

Thorium-plutonium mixed oxide, (Th,Pu)OX, is currently used as an alternative fuel in the light water reactors in the world. The main objective of this paper is not only to show the benefits of using the thorium, but mainly to study how the way thorium is introduced in the fuel affects the neutron p...

Descripción completa

Detalles Bibliográficos
Autores principales: Mustafa, S. S., Amin, E. A.
Formato: Online Artículo Texto
Lenguaje:English
Publicado: Nature Publishing Group UK 2019
Materias:
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC6842006/
https://www.ncbi.nlm.nih.gov/pubmed/31704959
http://dx.doi.org/10.1038/s41598-019-52560-4
_version_ 1783467979120312320
author Mustafa, S. S.
Amin, E. A.
author_facet Mustafa, S. S.
Amin, E. A.
author_sort Mustafa, S. S.
collection PubMed
description Thorium-plutonium mixed oxide, (Th,Pu)OX, is currently used as an alternative fuel in the light water reactors in the world. The main objective of this paper is not only to show the benefits of using the thorium, but mainly to study how the way thorium is introduced in the fuel affects the neutron parameters. Among these benefits is the possibility of extending the operating cycle length and the reduction of the increasing stockpiles of plutonium. The first investigated method is introducing thorium as (Th,Pu)OX. The second one is a homogeneous model of thorium plutonium oxide. It is carried out by adding an amount of plutonium separated from the uranium oxide cycle at 50 GWd/ton of heavy metal to the same amount of thorium. Thus, we studied three assemblies; the reference assembly is uranium oxide of 4.2% enrichment containing borated water as a moderator of concentration 500 ppm (part per million) of B-10. The second is a (Th,Pu)OX and the third one is an assembly with homogenized thorium plutonium. All three assemblies are modeled using MCNPX. A comparison is held between the results of the three lattices. The factors compared are the effective multiplication factor, the inventory of plutonium and uranium isotopes, and the depletion of B-10, the pin by pin power distribution at 0 and 60 GWd/ton and the relative pin radial power for the three lattices. The comparison is aimed to show the effect on the cycle length, the reduction in the Pu content and the power flattening across the assembly. It is found that the evolution of the multiplication factors shows a similar behaviour using (Th-Pu)OX fuel in the assembly as UOX cycle inspite of lowering the K-eff of fresh (Th-Pu)OX fuel (1.19847). The power flattening which is favorable in reactor operation is clearer in (Th,Pu)OX fuel. It is noticed that the mass of Pu-239 decreases by 1.07% from its initial value at the end of life. For homogeneous (Th,Pu)OX, the mass decreases by 0.0832%. The high power peaking factor for (Th,Pu)OX is not expected to cause significant effects during reactor operation but it can be reduced by adding burnable poisons.
format Online
Article
Text
id pubmed-6842006
institution National Center for Biotechnology Information
language English
publishDate 2019
publisher Nature Publishing Group UK
record_format MEDLINE/PubMed
spelling pubmed-68420062019-11-14 Feasibility Study of Thorium-Plutonium Mixed Oxide Assembly In Light Water Reactors Mustafa, S. S. Amin, E. A. Sci Rep Article Thorium-plutonium mixed oxide, (Th,Pu)OX, is currently used as an alternative fuel in the light water reactors in the world. The main objective of this paper is not only to show the benefits of using the thorium, but mainly to study how the way thorium is introduced in the fuel affects the neutron parameters. Among these benefits is the possibility of extending the operating cycle length and the reduction of the increasing stockpiles of plutonium. The first investigated method is introducing thorium as (Th,Pu)OX. The second one is a homogeneous model of thorium plutonium oxide. It is carried out by adding an amount of plutonium separated from the uranium oxide cycle at 50 GWd/ton of heavy metal to the same amount of thorium. Thus, we studied three assemblies; the reference assembly is uranium oxide of 4.2% enrichment containing borated water as a moderator of concentration 500 ppm (part per million) of B-10. The second is a (Th,Pu)OX and the third one is an assembly with homogenized thorium plutonium. All three assemblies are modeled using MCNPX. A comparison is held between the results of the three lattices. The factors compared are the effective multiplication factor, the inventory of plutonium and uranium isotopes, and the depletion of B-10, the pin by pin power distribution at 0 and 60 GWd/ton and the relative pin radial power for the three lattices. The comparison is aimed to show the effect on the cycle length, the reduction in the Pu content and the power flattening across the assembly. It is found that the evolution of the multiplication factors shows a similar behaviour using (Th-Pu)OX fuel in the assembly as UOX cycle inspite of lowering the K-eff of fresh (Th-Pu)OX fuel (1.19847). The power flattening which is favorable in reactor operation is clearer in (Th,Pu)OX fuel. It is noticed that the mass of Pu-239 decreases by 1.07% from its initial value at the end of life. For homogeneous (Th,Pu)OX, the mass decreases by 0.0832%. The high power peaking factor for (Th,Pu)OX is not expected to cause significant effects during reactor operation but it can be reduced by adding burnable poisons. Nature Publishing Group UK 2019-11-08 /pmc/articles/PMC6842006/ /pubmed/31704959 http://dx.doi.org/10.1038/s41598-019-52560-4 Text en © The Author(s) 2019 Open Access This article is licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons license, and indicate if changes were made. The images or other third party material in this article are included in the article’s Creative Commons license, unless indicated otherwise in a credit line to the material. If material is not included in the article’s Creative Commons license and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this license, visit http://creativecommons.org/licenses/by/4.0/.
spellingShingle Article
Mustafa, S. S.
Amin, E. A.
Feasibility Study of Thorium-Plutonium Mixed Oxide Assembly In Light Water Reactors
title Feasibility Study of Thorium-Plutonium Mixed Oxide Assembly In Light Water Reactors
title_full Feasibility Study of Thorium-Plutonium Mixed Oxide Assembly In Light Water Reactors
title_fullStr Feasibility Study of Thorium-Plutonium Mixed Oxide Assembly In Light Water Reactors
title_full_unstemmed Feasibility Study of Thorium-Plutonium Mixed Oxide Assembly In Light Water Reactors
title_short Feasibility Study of Thorium-Plutonium Mixed Oxide Assembly In Light Water Reactors
title_sort feasibility study of thorium-plutonium mixed oxide assembly in light water reactors
topic Article
url https://www.ncbi.nlm.nih.gov/pmc/articles/PMC6842006/
https://www.ncbi.nlm.nih.gov/pubmed/31704959
http://dx.doi.org/10.1038/s41598-019-52560-4
work_keys_str_mv AT mustafass feasibilitystudyofthoriumplutoniummixedoxideassemblyinlightwaterreactors
AT aminea feasibilitystudyofthoriumplutoniummixedoxideassemblyinlightwaterreactors