Assessment of shielding analysis methods, codes, and data for spent fuel transport/storage applications. [Radiation dose rates from shielded spent fuels and high-level radioactive waste]

Technical Report · Fri Jul 01 04:00:00 EDT 1988

DOI:https://doi.org/10.2172/6783967· OSTI ID:6783967

Parks, C V; Broadhead, B L; Hermann, O W; Tang, J S; Cramer, S N; Gauthey, J C; Kirk, B L; Roussin, R W

This report provides a preliminary assessment of the computational tools and existing methods used to obtain radiation dose rates from shielded spent nuclear fuel and high-level radioactive waste (HLW). Particular emphasis is placed on analysis tools and techniques applicable to facilities/equipment designed for the transport or storage of spent nuclear fuel or HLW. Applications to cask transport, storage, and facility handling are considered. The report reviews the analytic techniques for generating appropriate radiation sources, evaluating the radiation transport through the shield, and calculating the dose at a desired point or surface exterior to the shield. Discrete ordinates, Monte Carlo, and point kernel methods for evaluating radiation transport are reviewed, along with existing codes and data that utilize these methods. A literature survey was employed to select a cadre of codes and data libraries to be reviewed. The selection process was based on specific criteria presented in the report. Separate summaries were written for several codes (or family of codes) that provided information on the method of solution, limitations and advantages, availability, data access, ease of use, and known accuracy. For each data library, the summary covers the source of the data, applicability of these data, and known verification efforts. Finally, the report discusses the overall status of spent fuel shielding analysis techniques and attempts to illustrate areas where inaccuracy and/or uncertainty exist. The report notes the advantages and limitations of several analysis procedures and illustrates the importance of using adequate cross-section data sets. Additional work is recommended to enable final selection/validation of analysis tools that will best meet the US Department of Energy's requirements for use in developing a viable HLW management system. 188 refs., 16 figs., 27 tabs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6783967
• Report Number(s): ORNL/CSD/TM-246; ON: DE89001308
• Country of Publication: United States
• Language: English

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63 RADIATION, THERMAL, AND OTHER ENVIRON. POLLUTANT EFFECTS ON LIVING ORGS. AND BIOL. MAT.
CASKS
CONTAINERS
DOSE RATES
DOSES
ENERGY SOURCES
FORECASTING
FUELS
HIGH-LEVEL RADIOACTIVE WASTES
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MATHEMATICAL MODELS
MONITORING
NUCLEAR FUELS
RADIATION DOSES
RADIATION MONITORING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE STORAGE
RADIOACTIVE WASTES
REACTOR MATERIALS
SHIELDING MATERIALS
SPENT FUEL CASKS
SPENT FUELS
STORAGE
TRANSPORT
WASTE MANAGEMENT
WASTE STORAGE
WASTES