Published 2008
| Version v1
Miscellaneous
Analysis of the performance of fuel cells BWR with a single enrichment and radial distribution of enrichments
Creators
- Gonzalez, J. A.1
- Vargas, S.1
- Alonso, G.1
- Del Valle, E.1
- Xolocostli M, J. V.2
- Sociedad Nuclear Mexicana (SNM), Mexico D.F. (Mexico)
- Comision Federal de Electricidad (Mexico)
- Comision Nacional de Seguridad Nuclear y Salvaguardias (Mexico)
- Instituto de Investigaciones Electricas (Mexico)
- Instituto Nacional de Investigaciones Nucleares (Mexico)
- Instituto Politecnico Nacional (Mexico)
- Universidad Autonoma de Zacatecas (Mexico)
- Universidad Nacional Autonoma de Mexico (Mexico)
- Academia de Ingenieria de Mexico (Mexico)
- Asociacion de Jovenes por la Energia Nuclear en Mexico (Mexico)
- Secretaria de Fomento Turistico, Gobierno del Estado de Yucatan (Mexico)
- 1. IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Col. Lindavista, Mexico D. F. 07738 (Mexico)
- 2. ININ, 52750 La Marquesa, Estado de Mexico (Mexico)
Description
The efficient use of the fuel is one of the objectives in the assemblies design of type BWR. The present tendency in the assemblies design of type BWR is through a radial distribution of enrichments. The present work has like object showing the because of this decision, for what a comparison of the neutronic performance of two fuel cells with the same enrichment average but one of them with radial distribution of enrichment and the other with a single enrichment equal to the average. The cells were analyzed with the CASMO-4 code and the obtained results of the behavior of the neutron flow and the power sustain the because of the radial distribution of enrichments. (Author)
Availability note (English)
Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion Nuclear, 52045 Ocoyoacac, Estado de Mexico (MX). e-mail: claudio.fernandez@inin.gob.mxAdditional details
Additional titles
- Original title (Spanish)
- Analisis del desempeno de celdas combustibles BWR con un solo enriquecimiento y con distribucion radial de enriquecimientos
Publishing Information
- ISBN
- 978-968-9353-01-1
- Imprint Pagination
- 11 p.
Conference
- Title
- 19. Annual SNM Congress
- Original Conference Title
- Atoms for the development of Mexico
- Dates
- 6-9 Jul 2008
- Place
- Merida, Yuc. (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 40014769
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- BURNOUT; BURNUP; BWR TYPE REACTORS; C CODES; COMPARATIVE EVALUATIONS; COMPUTER CODES; COMPUTERIZED SIMULATION; EVALUATED DATA; FLUID FLOW; FUEL ASSEMBLIES; FUEL CELLS; GADOLINIUM; ISOTOPE SEPARATION; NEUTRON FLUX; NEUTRON TRANSPORT; NUCLEAR FUELS; PERFORMANCE; REACTOR LATTICES; SPATIAL DISTRIBUTION; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; COMPUTER CODES; DATA; DIRECT ENERGY CONVERTERS; DISTRIBUTION; ELECTROCHEMICAL CELLS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EVALUATION; EVEN-ODD NUCLEI; FUELS; HEAVY NUCLEI; INFORMATION; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; METALS; MINUTES LIVING RADIOISOTOPES; NEUTRAL-PARTICLE TRANSPORT; NUCLEI; NUMERICAL DATA; POWER REACTORS; RADIATION FLUX; RADIATION TRANSPORT; RADIOISOTOPES; RARE EARTHS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; SIMULATION; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES