Published 1991
| Version v1
Book
Dissolution of spent water reactor fuels at the UP3 plant: criticality safety options
Creators
- 1. CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire
- 2. Compagnie Generale des Matieres Nucleaires (COGEMA), 50 - Cherbourg (France). Etablissement de La Hague
Description
The criticality control mode, retained for the UP3 dissolver, that is, ''fissile material mass limitation in limited geometry'', associated in the major part to the burn-up credit, is exposed. The optimisation of the geometrical dimensions of the apparatus, and of the operating conditions in normal running, relating to this control mode, are shown. The various controls associated with the guarantee of minimum fuel irradiation, which are performed before the shearing of the fuel assemblies, are described. Also the principle of the control of the fissile material mass loaded into the dissolver, versus the burn-up, is explained. (author)
Additional details
Additional titles
- Original title (French)
- La dissolution dans l'usine UP3 des combustibles de reacteurs a eau irradies: options de surete-criticite
Publishing Information
- Publisher
- AEA Technology.
- Imprint Place
- Winfrith (United Kingdom)
- Imprint Title
- ICNC '91: international conference on nuclear criticality safety
- Imprint Pagination
- 374 p.
- Journal Page Range
- v. 2 p. V.8-V.1
Conference
- Title
- international conference on nuclear criticality safety.
- Acronym
- ICNC '91
- Dates
- 9-13 Sep 1991.
- Place
- Oxford (United Kingdom).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 24049223
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CHEMICAL DECLADDING; CRITICALITY; FISSILE MATERIALS; FUEL ASSEMBLIES; GEOMETRY; OPTIMIZATION; REPROCESSING; SAFETY ANALYSIS; SPENT FUELS
- Descriptors DEC
- DECLADDING; ENERGY SOURCES; FISSIONABLE MATERIALS; FUELS; HEAD END PROCESSES; MATERIALS; MATHEMATICS; NUCLEAR FUELS; REACTOR MATERIALS; SEPARATION PROCESSES
Optional Information
- Notes
- Imprint:Conference published in 3 v.