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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2017.1
- 수록면
- 1,226 - 1,233 (8page)
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Measurements of the isotopic contents of spent nuclear fuel provide experimental data that are a prerequisitefor validating computer codes and nuclear data for many spent fuel applications. Under theauspices of the Organisation for Economic Co-operation and Development (OECD) Nuclear EnergyAgency (NEA) and guidance of the Expert Group on Assay Data of Spent Nuclear Fuel of the NEAWorkingParty on Nuclear Criticality Safety, a new database of expanded spent fuel isotopic compositions has beencompiled. The database, Spent Fuel Compositions (SFCOMPO) 2.0, includes measured data for more than750 fuel samples acquired from 44 different reactors and representing eight different reactor technologies.
Measurements for more than 90 isotopes are included. This new database provides data essentialfor establishing the reliability of code systems for inventory predictions, but it also has broader potentialapplication to nuclear data evaluation. The database, together with adjoint based sensitivity and uncertaintytools for transmutation systems developed to quantify the importance of nuclear data onnuclide concentrations, are described.
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참고문헌 (23)
참고문헌 신청
/ / SFCOMPO 2.0 - Database of Measured Isotopic Concentrations of Spent Nuclear Fuel, with Operational Histories and Design Data
/ / WPNCS Expert Group on Assay Data of Spent Nuclear Fuel (ADSNF)
/ 2000 / The JEF-2.2 Nuclear Data Library
/ 2013 / Validation of the JEFF-3.1 Nuclear Data Library
/ 2014 / International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)03/I-IX
/ / WPNCS Expert Group on Assay Data of Spent Nuclear Fuel (ADSNF)
/ 2000 / The JEF-2.2 Nuclear Data Library
/ 2013 / Validation of the JEFF-3.1 Nuclear Data Library
/ 2014 / International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)03/I-IX
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