Nuclear data are a main uncertainty source in neutron transport simulations making their consideration in reactor safety necessary. This arises anew with the state-of-the-art reactors known as Generation IV. Some of the reactors suggests providing the reactivity margin below the effective delayed neutron fraction excluding prompt criticality accidents, and the breeding ratio is the key factor in this. Consequently, assessing a degree of the breeding ratio accuracy is of interest. Therefore, in this work, the breeding ratio uncertainties are analyzed by performing a sensitivity and uncertainty analysis of the MET1000 and MOX3600 models with respect to nuclear data using SCALE. As a result, the breeding ratio uncertainties are obtained approximately equal to 2% as the main contributors are 239Pu(n, gamma), 238U(n, gamma), and 238U(n, n'). The uncertainty sources between the models are compared, and 16O preponderantly increases the total uncertainty not directly by its uncertainty but by its impact on the spectrum.
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Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
Wang, Mingjun
Chen, Jing
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Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
Chen, Jing
Zhang, Dalin
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Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
Zhang, Dalin
Zhang, Jing
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Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
Zhang, Jing
Tian, Wenxi
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Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
Tian, Wenxi
Su, G. H.
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Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
Su, G. H.
Qiu, Suizheng
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Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
机构:
Korea Atom Energy Res Inst, Next Generat Fuel Dev Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Next Generat Fuel Dev Div, Taejon 305353, South Korea
Kim, Ki-Hwan
Oh, Seok-Jin
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Korea Atom Energy Res Inst, Next Generat Fuel Dev Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Next Generat Fuel Dev Div, Taejon 305353, South Korea
Oh, Seok-Jin
Kim, Sun-Ki
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Korea Atom Energy Res Inst, Next Generat Fuel Dev Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Next Generat Fuel Dev Div, Taejon 305353, South Korea
Kim, Sun-Ki
Lee, Chong-Tak
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Korea Atom Energy Res Inst, Next Generat Fuel Dev Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Next Generat Fuel Dev Div, Taejon 305353, South Korea
Lee, Chong-Tak
Lee, Chan-Bock
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Korea Atom Energy Res Inst, Next Generat Fuel Dev Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Next Generat Fuel Dev Div, Taejon 305353, South Korea