Published 1979
| Version v1
Journal article
Monte Carlo calculational design of an NDA instrument for the assay of waste products from highly enriched spent fuels
Description
no abstract available
Additional details
Publishing Information
- Journal Title
- Trans. Am. Nucl. Soc., Suppl.
- Journal Volume
- 33
- Journal Issue
- 1
- Series
- Trans. Am. Nucl. Soc., Suppl.
- Journal Page Range
- 36-37
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11521186
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
- Resource subtype / Literary indicator
- No Abstract
- Descriptors DEI
- COMPUTER CODES; CONTAINERS; DELAYED NEUTRON ANALYSIS; M CODES; MONTE CARLO METHOD; PACKAGING; RADIOACTIVE WASTES; REPROCESSING; SPECIFICATIONS; SPENT FUELS
- Descriptors DEC
- CHEMICAL ANALYSIS; ENERGY SOURCES; FUELS; NONDESTRUCTIVE ANALYSIS; NUCLEAR FUELS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; SEPARATION PROCESSES; WASTES
Optional Information
- Notes
- Published in summary form only.