Radionuclide Emission Estimation for the Center for Advanced Energy Studies (CAES)

Bradley J Schrader

关键词: COMPUTER CODES;    DESIGN;    DOSE EQUIVALENTS;    ECONOMIC DEVELOPMENT;    INGESTION;    INHALATION;    NATIONAL GOVERNMENT;    RADIOACTIVE MATERIALS;    RADIOISOTOPES;    RECOMMENDATIONS;    SAFETY;    SAFETY ANALYSIS;    SECURITY Dose Assessment;   

DOI  :  10.2172/986957
RP-ID  :  INL/EXT-10-17755
PID  :  OSTI ID: 986957
Others  :  TRN: US1006636

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

An Radiological Safety Analysis Computer Program (RSAC)-7 model dose assessment was performed to evaluate maximum Center for Advanced Energy Studies (CAES) boundary effective dose equivalent (EDE, in mrem/yr) for potential individual releases of radionuclides from the facility. The CAES is a public/private partnership between the State of Idaho and its academic research institutions, the federal government through the U.S. Department of Energy (DOE), and the Idaho National Laboratory (INL) managed by the Battelle Energy Alliance (BEA). CAES serves to advance energy security for our nation by expanding educational opportunities at Idaho universities in energy-related areas, creating new capabilities within its member institutions, and delivering technological innovations leading to technology-based economic development for the intermountain region. CAES has developed a strategic plan (INL/EXT-07-12950) based on the balanced scorecard approach. At the present time it is unknown exactly what processes will be used in the facility in support of this strategic plan. What is known is that the Idaho State University (ISU) Radioactive Materials License (Nuclear Regulatory Commission [NRC] license 11-27380-01) is the basis for handling radioactive material in the facility. The material in this license is shared between the ISU campus and the CAES facility. There currently are no agreements in place to limit the amount of radioactive material at the CAES facility or what is done to the material in the facility. The scope of this analysis is a summary look at the basis dose for each radionuclide included under the license at a distance of 100, 500, and 1,000 m. Inhalation, ingestion and ground surface dose was evaluated using the NRC design basis guidelines. The results can be used to determine a sum of the fractions approach to facility safety. This sum of the fractions allows a facility threshold value (TV) to be established and potential activities to be evaluated against this TV.