Published 1997
| Version v1
Book
Assessment of fuel rod thermomechanical behaviour under normals operating conditions
Description
Using computer code Pin-micro (available in the Nea-Data-Bank and developed for maidenly fuel road thermomechanical behaviour under normals operating conditions in PWR type WWER) and the system developed in MS Access 2.0, FUEL, Juragua NPP, is evaluated. System PIN-FUEL can be used for evaluating other design of nuclear fuel for WWER reactors This work have given the possibility of assessment code's limitation for analyze all phenomena that occurs in the fuel rod during reactors work
Additional details
Additional titles
- Original title (Spanish)
- Evaluacion del comportamiento del combustible nuclear en condiciones de operacion normal
Publishing Information
- Publisher
- Centro de Informacion de la Energia Nuclear.
- Imprint Place
- La Habana (Cuba)
- Imprint Title
- Main scientific technical results of the Nuclear Technology Center. 1996
- Imprint Pagination
- 103 p.
- Journal Page Range
- p. 68-73.
INIS
- Country of Publication
- Cuba
- Country of Input or Organization
- Cuba
- INIS RN
- 28060159
- Subject category
- S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- COMPILED DATA; COMPUTER CALCULATIONS; D CODES; EVALUATION; H CODES; JURAGUA-1 REACTOR; NEUTRON FLUENCE; NUCLEAR FUELS; P CODES; PWR TYPE REACTORS; S CODES
- Descriptors DEC
- COMPUTER CODES; DATA; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; INFORMATION; MATERIALS; NUMERICAL DATA; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- Imprint:Principales resultados Cientificos Tecnicos del Centro de Tecnologia Nuclear. 1996.