Characterization of decommissioned reactor internals: Monte Carlo analysis technique
This study discusses computer analysis techniques for determining activation levels of irradiated reactor component hardware to yield data for the Department of Energy's Greater-Than-Class C Low-Level Radioactive Waste Program. The study recommends the Monte Carlo Neutron/Photon (MCNP) computer code as the best analysis tool for this application and compares the technique to direct sampling methodology. To implement the MCNP analysis, a computer model would be developed to reflect the geometry, material composition, and power history of an existing shutdown reactor. MCNP analysis would then be performed using the computer model, and the results would be validated by comparison to laboratory analysis results from samples taken from the shutdown reactor. The report estimates uncertainties for each step of the computational and laboratory analyses; the overall uncertainty of the MCNP results is projected to be [plus minus]35%. The primary source of uncertainty is identified as the material composition of the components, and research is suggested to address that uncertainty.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 7368778
- Report Number(s):
- DOE/LLW-171; ON: DE93013740
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
LOW-LEVEL RADIOACTIVE WASTES
COMPUTER CALCULATIONS
FORECASTING
REACTOR DECOMMISSIONING
DATA COVARIANCES
MONTE CARLO METHOD
RADIOACTIVATION
RADIOCHEMICAL ANALYSIS
CALCULATION METHODS
CHEMICAL ANALYSIS
DECOMMISSIONING
MATERIALS
QUANTITATIVE CHEMICAL ANALYSIS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
WASTES
220900* - Nuclear Reactor Technology- Reactor Safety
052000 - Nuclear Fuels- Waste Management