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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.10
- 수록면
- 3,151 - 3,157 (7page)
- DOI
- https://doi.org/10.1016/j.net.2021.04.029
이용수
초록· 키워드
오류제보하기
Copper is an important structural material in various nuclear energy applications, therefore the correctknowledge of copper cross sections is crucial. The presented paper deals with a validation of differentcopper transport libraries by means of activation of selected samples. An intense 252Cf(sf) source with areference neutron spectrum was used as a neutron source. After irradiation, the samples were measuredusing a high purity germanium detector and the dosimeter reaction rates were inferred. These experimental data were compared with MCNP6 calculations using CENDL-3.1, JENDL-4.0, ENDF/B-VII.1, ENDF/BVIII.0, JEFF-3.2 and JEFF-3.3 evaluated Cu transport libraries. The experiment specifically focuses on 58Ni(n,p)58Co, 93Nb(n,2n)92mNb, 197Au(n,g)198Au and 55Mn(n,g)56Mn dosimetry reactions. Evaluatedactivation cross sections of these dosimetric reactions were taken from the IRDFF-II library. The bestlibrary performance depends on the energy region of interest.
목차
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참고문헌 (20)
참고문헌 신청
S. Singh / 2018 / Development of thick copper claddings on SS316L steel for In-vessel components of fusion reactors and copper-cast iron canisters / Fusion Eng. Des 128:126~137
B. Rosborg / 2008 / The Swedish nuclear waste program and the long-term corrosion behaviour of copper / J. Nucl. Mater 379(1-3):142~153
M. Zinet / 2019 / Spent fuel transportation cask under accidental fire conditions : numerical analysis of gas transport phenomena affecting heat transfer in shielding materials / Prog. Nucl. Energy 117:103045
A. Trkov / 2020 / IRDFF-II : an updated neutron metrology library / Nucl. Data Sheets 163:1~108
W. Mannhart / Status of the Evaluation of the Neutron Spectrum of 252Cf(sf), IAEA Technical Report INDC(NDS)-0540
B. Rosborg / 2008 / The Swedish nuclear waste program and the long-term corrosion behaviour of copper / J. Nucl. Mater 379(1-3):142~153
M. Zinet / 2019 / Spent fuel transportation cask under accidental fire conditions : numerical analysis of gas transport phenomena affecting heat transfer in shielding materials / Prog. Nucl. Energy 117:103045
A. Trkov / 2020 / IRDFF-II : an updated neutron metrology library / Nucl. Data Sheets 163:1~108
W. Mannhart / Status of the Evaluation of the Neutron Spectrum of 252Cf(sf), IAEA Technical Report INDC(NDS)-0540
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