Author:
Chiba Go,Kawamoto Yosuke,Narabayashi Tadashi
Subject
Nuclear Energy and Engineering
Reference12 articles.
1. Uncertainty quantification of neutronic parameters of light water reactor fuel cells with JENDL-4.0 covariance data;Chiba;J. Nucl. Sci. Technol.,2013
2. Photon transport effect on intra-subassembly thermal power distribution in fast reactor;Chiba;Ann. Nucl. Energy,2014
3. Important fission product nuclides identification method for simplified burnup chain construction;Chiba;J. Nucl. Sci. Technol.,2015
4. Katakura, J., Kataoka, M., Suyama, K., Jin, T., Ohki, S. 2004. A set of ORIGEN2 cross section libraries based on JENDL-3.3 library: ORLIBJ33, JAERI-Data/Code 2004-015, Japan Atomic Energy Research Institute.
5. Numerical solution of matrix exponential in burn-up equation using mini-max polynomial approximation;Kawamoto;Ann. Nucl. Energy,2015
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