Application of curium measurements for safeguarding at reprocessing plants. Study 1: High-level liquid waste and Study 2: Spent fuel assemblies and leached hulls
In large-scale reprocessing plants for spent fuel assemblies, the quantity of plutonium in the waste streams each year is large enough to be important for nuclear safeguards. The wastes are drums of leached hulls and cylinders of vitrified high-level liquid waste. The plutonium amounts in these wastes cannot be measured directly by a nondestructive assay (NDA) technique because the gamma rays emitted by plutonium are obscured by gamma rays from fission products, and the neutrons from spontaneous fissions are obscured by those from curium. The most practical NDA signal from the waste is the neutron emission from curium. A diversion of waste for its plutonium would also take a detectable amount of curium, so if the amount of curium in a waste stream is reduced, it can be inferred that there is also a reduced amount of plutonium. This report studies the feasibility of tracking the curium through a reprocessing plant with neutron measurements at key locations: spent fuel assemblies prior to shearing, the accountability tank after dissolution, drums of leached hulls after dissolution, and canisters of vitrified high-level waste after separation. Existing pertinent measurement techniques are reviewed, improvements are suggested, and new measurements are proposed. The authors integrate these curium measurements into a safeguards system.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 212480
- Report Number(s):
- LA-13134-MS; ON: DE96008723; TRN: 96:010580
- Resource Relation:
- Other Information: PBD: Mar 1996
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
FUEL REPROCESSING PLANTS
NUCLEAR MATERIALS MANAGEMENT
CURIUM
NONDESTRUCTIVE ANALYSIS
PLUTONIUM
HIGH-LEVEL RADIOACTIVE WASTES
FUEL CANS
NEUTRON DETECTION
ON-LINE MEASUREMENT SYSTEMS
FEASIBILITY STUDIES
LIQUID WASTES
SPENT FUEL ELEMENTS
HEAD END PROCESSES
SPECIFICATIONS
DIAGNOSTIC TECHNIQUES
COMPARATIVE EVALUATIONS
RADIOACTIVE WASTE MANAGEMENT
CONTAINERS