Published 1991
| Version v1
Report
Open
Evaluation and validation of criticality codes for fuel dissolver calculations
- 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France)
- 2. Oak Ridge National Lab., TN (USA)
Description
Short communication
Availability note (English)
MF available from INIS under the Report Number; Available from OSTI as DE91007839; NTIS; INIS; US Govt. Printing Office Dep.Files
22091958.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 2 p.
- Report number
- CONF-910993--1-Extd.Abst
Conference
- Title
- International conference on nuclear criticality (ICNC) safety.
- Dates
- 9-13 Sep 1991.
- Place
- Oxford (UK).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22091958
- Subject category
- S98: NUCLEAR DISARMAMENT, SAFEGUARDS AND PHYSICAL PROTECTION; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, No Abstract
- Descriptors DEI
- COMPUTER CODES; CRITICALITY; DISSOLUTION; EVALUATION; FUEL PELLETS; NUCLEAR FUELS; VERIFICATION
- Descriptors DEC
- ENERGY SOURCES; FUELS; MATERIALS; REACTOR MATERIALS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Funding organization
- USDOE, Washington, DC (USA).