Published May 1971
| Version v1
Journal article
Non-destructive determination of reactor fuel element burn-up by measurement of fission neutrons
Creators
- 1. National Tsing Hua Univ., Hsinchu (China). Inst. of Nuclear Science
Description
no abstract available
Additional details
Identifiers
- DOI
- 10.3327/jnst.8.285;
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology
- Journal Volume
- 8
- Journal Issue
- 5
- Series
- J. Nucl. Sci. Technol. (Tokyo).
- Journal Page Range
- 285-287
- ISSN
- 1881-1248
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 3017052
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- No Abstract
- Descriptors DEI
- ALUMINUM; COLLIMATORS; FISSION NEUTRONS; FUEL PLATES; KERNELS; LEAST SQUARE FIT; PROPORTIONAL COUNTERS; SHUTTERS; SPENT FUEL ELEMENTS; URANIUM OXIDES; URANIUM 235; URANIUM 238; WATER MODERATOR
- Descriptors DEC
- BEAM OPTICS; BURNUP; CLOSURES; DIFFERENTIAL EQUATIONS; FUEL ELEMENTS; INTEGRAL EQUATIONS; INTEGRALS; MATHEMATICS; NEUTRONS; PLATES
Optional Information
- Notes
- Updated automatically by Metadata and Full-Text Enrichment Agent