Published May 1974
| Version v1
Report
Restricted
Statistical analysis and modeling of gap conductance data for reactor fuel rods containing UO2 pellets
Description
no abstract available
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR, Bessel code
Publishing Information
- Imprint Pagination
- v p.
- Report number
- BNWL--1842
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 6171764
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- B CODES; COMPUTER CODES; CONFIGURATION; DATA; DISTRIBUTION; FUEL CANS; FUEL PELLETS; FUEL RODS; MATHEMATICAL MODELS; PWR TYPE REACTORS; SPATIAL DISTRIBUTION; STATISTICS; THERMAL CONDUCTION; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY TRANSFER; FUEL ELEMENTS; HEAT TRANSFER; INFORMATION; MATHEMATICS; OXIDES; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS