Spent-fuel composition: a comparison of predicted and measured data
The uncertainty in predictions of the nuclear materials content of spent light-water reactor fuel was investigated to obtain guidelines for nondestructive spent-fuel verification and assay. Values predicted by the reactor operator were compared with measured values from fuel reprocessors for six reactors (three PWR and three BWR). The study indicates that total uranium, total plutonium, fissile uranium, fissile plutonium, and total fissile content can be predicted with biases ranging from 1 to 6% and variabilities (1-sigma) ranging from 2 to 7%. The higher values generally are associated with BWRs. Based on the results of this study, nondestructive assay measurements that are accurate and precise to 5 to 10% (1sigma) or better should be useful for quantitative analyses of typical spent fuel.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6604060
- Report Number(s):
- LA-8764-MS; TRN: 81-008254
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
DATA COVARIANCES
SPENT FUELS
NONDESTRUCTIVE ANALYSIS
ACCOUNTING
ACCURACY
BURNUP
BWR TYPE REACTORS
COMPARATIVE EVALUATIONS
DATA
FISSILE MATERIALS
PLUTONIUM
PWR TYPE REACTORS
SAFEGUARDS
SENSITIVITY
URANIUM
ACTINIDES
CHEMICAL ANALYSIS
ELEMENTS
ENERGY SOURCES
FISSIONABLE MATERIALS
FUELS
INFORMATION
MATERIALS
METALS
NUCLEAR FUELS
REACTOR MATERIALS
REACTORS
TRANSURANIUM ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
055001* - Nuclear Fuels- Safeguards
Inspection
& Accountability- Technical Aspects
400100 - Analytical & Separations Chemistry