Fuel design with low peak of local power for BWR reactors with increased nominal power
Creators
- Perusquia C, R.1
- Montes, J.L.1
- Hernandez, J.L.1
- Ortiz, J.J.1
- Castillo, A.1
- International Radiation Protection Association (IRPA) (France)
- Sociedad Mexicana de Seguridad Radiologica A.C. (SMSR), Mexico D.F. (Mexico)
- Sociedad Nuclear Mexicana (SNM), Mexico D.F. (Mexico)
- Organismo Internacional de Energia Atomica (OIEA), Vienna (Australia)
- Federacion de Radioproteccion de America Latina y el Caribe (FRALC), Zacatecas (Mexico)
- Organizacion Panamericana de la Salud (OPS), Washington, D.C. (United States)
- 1. ININ, 52750 Ocoyoacac, Estado de Mexico (Mexico)
Description
The Federal Commission of Electricity recently announcement the beginning of the works related with the increase of the power to 120% of the original nominal one in the Boiling Water Reactors (BWR) of the Laguna Verde Central (CLV): In the National Institute of Nuclear Research (ININ) are carried out studies of the impact on the design of the recharge of derived fuel of this increase. One of the main effects of the power increase type that it is promoting, is the increment of the flow of generated vapor, what takes, to a bigger fraction of vacuum in the core presenting increased values of the maximum fraction to the limit, so much of the ratio of lineal heat generation (XFLPD) as of the ratio of critic power (MFLCPR). In the made studies, it is found that these fractions rise lineally with the increase of the nominal power. Considering that the reactors of the CLV at the moment operate to 105% of the original nominal power, it would imply an increment of the order of 13.35% in the XFLPD and in the MFLCPR operating to a nominal power of 120% of the original one. This would propitiate bigger problems to design appropriately the fuel cycle and the necessity, almost unavoidable, of to resort to a fuel assembly type more advanced for the recharges of the cores. As option, in the ININ the feasibility of continuing using the same type of it fuel assembles that one has come using recently in the CLV, the type GE12 is analyzed. To achieve it was outlined to diminish the peak factor of local power (LPPF) of the power cells that compose the fuel recharge in 13.35%. It was started of a fuel design previously used in the recharge of the unit 1 cycle 12 and it was re-design to use it in the recharge design of the cycle 13 of the unit 1, considering an increase to 120% of the original power and the same requirements of cycle extension. For the re-design of the fuel assembly cell it was used the PreDiCeldas computer program developed in the ININ. It was able to diminish the LPPF 14% of an original value from 1.43 to 1.24 that which was confirmed with the cells calculation code best estimate HELIOS. In later studies the acting of the re-designed fuel assemblies in the recharges simulation for the cycle 13 will be examine. (Author)
Availability note (English)
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Additional details
Additional titles
- Original title (Spanish)
- Diseno de un combustible con bajo pico de potencia local para reactores BWR con potencia nominal aumentada
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- INIS-MX--2141
Conference
- Title
- 1. american congress of the IRPA; 7. regional congress of radiological and nuclear safety; 24. annual meeting of the SMSR; 17. annual congress of the SNM
- Original Conference Title
- Retos y tendencias para el continente americano respecto a la proteccion radiologica, la seguridad nuclear y el ambiente
- Dates
- 3-8 Sep 2006
- Place
- Acapulco, Gro. (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 38013745
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; DATA; DESIGN; DIAGRAMS; FUEL ASSEMBLIES; LAGUNA VERDE-1 REACTOR; MEGAWATT POWER RANGE; NUCLEAR FUELS; REACTOR FUELING; SIMULATION
- Descriptors DEC
- BWR TYPE REACTORS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; INFORMATION; MATERIALS; POWER RANGE; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS