Published 1995
| Version v1
Journal article
Sensitivity of noise analysis measurements to fission product content of SNL spent-fuel experiment assembly
- 1. Oak Ridge National Lab., TN (United States)
Description
The 212Cf-source-driven noise analysis measurement can be used to characterize spent fuel and to provide data for validation of calculational methods and cross sections. The sensitivity of calculated noise parameters to cross sections for spent fuel has been previously demonstrated. To investigate the sensitivity of the noise parameters to the amount of fission products in spent fuel from the Calvert Cliffs pressurized water reactor, Monte Carlo calculations using KENO-NR have been performed for an experimental assembly being designed at Sandia National Laboratories
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 73
- Journal Page Range
- p. 228-230.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS).
- Dates
- 29 Oct - 1 Nov 1995.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28018958
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CALVERT CLIFFS-1 REACTOR; CROSS SECTIONS; FISSION PRODUCTS; FUEL ASSEMBLIES; K CODES; NOISE; SENSITIVITY; SPENT FUELS
- Descriptors DEC
- COMPUTER CODES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; ISOTOPES; MATERIALS; NUCLEAR FUELS; POWER REACTORS; PWR TYPE REACTORS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-951006--.