Published November 1991
| Version v1
Miscellaneous
Methodology for the analysis of reloads licensing
Creators
- 1. Instituto de Investigaciones Electricas, Cuernavaca (Mexico)
Description
The general process to carry the analysis of reloads licensing for BWR type reactors is described, indicating which one of this events can be analyzed using the transients code of the fuel management system package. Finally some results of the analysis carried out with the aim to qualify the use of the codes and the used methodology for the simulation of transients of the heading of reloads licensing are presented. (Author)
Additional details
Additional titles
- Original title (Spanish)
- Metodologia para el analisis de licenciamiento de recargas
Publishing Information
- Imprint Title
- Transactions of the Second Annual Congress of the Sociedad Nuclear Mexicana A.C.
- Imprint Pagination
- [250 p.].
- Journal Page Range
- p. 171-177.
- Report number
- INIS-mf--14821
Conference
- Title
- 2. Annual Congress of Mexican Nuclear Society C.A.
- Original Conference Title
- Memorias del Segundo Congreso Anual de la Sociedad Nuclear Mexicana A.C
- Dates
- 17-19 Nov 1991.
- Place
- Veracruz, Veracruz (Mexico).
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 27066114
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; LAGUNA VERDE-1 REACTOR; LICENSING; LOSS OF COOLANT; R CODES; REACTIVITY; REACTOR FUELING; REACTOR STABILITY; ROD DROP ACCIDENTS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTIVITY INSERTIONS; REACTOR ACCIDENTS; REACTORS; SIMULATION; STABILITY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Memorias del Segundo Congreso Anual de la Sociedad Nuclear Mexicana A.C.