A neutronic evaluation of the (Pu-U) and (Am-Pu-U) insertion in a typical fuel of Angra-I
Creators
- 1. Departamento de Eng. Nuclear - Universidade Federal de Minas Gerais, PCA1, Anexo Engenharia, Av. Antonio Carlos, 6627, 31270-901 Belo Horizonte, MG (Brazil)
Description
The goal is to evaluate the neutronic behavior when (Pu-U) and (Am-Pu-U) mixed oxide are inserted in a typical cell of a Pressurized Water Reactor (PWR) such as Angra-I. Four types of fuels were studied: (1) MOX fuel enriched at 3.1% and Vm/Vf = 1.15; (2) MOX fuel enriched at 4.5% and Vm/Vf = 1.15; (3) MOX fuel enriched at 4.5% and Vm/Vf = 2.0 and (4) MOX fuel enriched at 4.5%, with 1% of Americium insertion in its composition (62.8% of Am241, 0.1% of Am242m and 37.1% of Am243) and with Vm/Vf = 2.0. The first case represents the standard state of Angra I, but with Pu. The second case is similar to the first but the enrichment is increased. To evaluate the Americium insertion, a study of the Vm/Vf was made and better results were obtained with Vm/Vf = 2.0 and to compare, this case was too evaluated to (Pu-U) in the third and fourth cases. The idea is to verify the possibility of using these fuels in Angra-I analyzing neutronic parameters such as infinite multiplication factor, hardening spectrum, Boron worth and reactivity temperature coefficients. The results show that it is possible to use all the studied fuels in Angra-I as well as to burn Am inserted in the MOX fuel by a considerable quantity during PWR operation. The WIMS-D5 code was used to perform a simplified neutronic and burnup simulations to evaluate this possibility
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2008.11.006Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2008.11.006;
- PII
- S0306-4549(08)00287-9;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 36
- Journal Issue
- 1
- Journal Page Range
- p. 1-6
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40045547
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- AMERICIUM; AMERICIUM 241; AMERICIUM 242; AMERICIUM 243; BORON; BURNUP; ENRICHMENT; HARDENING; MIXED OXIDE FUELS; MULTIPLICATION FACTORS; OXIDES; PWR TYPE REACTORS; REACTIVITY; SIMULATION; TEMPERATURE COEFFICIENT
- Descriptors DEC
- ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; AMERICIUM ISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CHALCOGENIDES; DIMENSIONLESS NUMBERS; ELECTRON CAPTURE RADIOISOTOPES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HEAVY NUCLEI; HOURS LIVING RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; METALS; NUCLEAR FUELS; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; OXYGEN COMPOUNDS; POWER REACTORS; RADIOISOTOPES; REACTIVITY COEFFICIENTS; REACTOR MATERIALS; REACTORS; SEMIMETALS; SOLID FUELS; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.