Burnup Sensitivity Analysis in a Fast Breeder Reactor—Part II: Prediction Accuracy of Burnup Characteristics
Author:
Affiliation:
1. Nippon Atomic Industry Group Company, Ltd., NAIG Nuclear Research Laboratory, 4-1, Ukishima-cho, Kawasaki-ku, 210 Kawasaki-shi, Japan
2. Osaka University, Faculty of Engineering, Nuclear Engineering, Yamada-oka, Suita-shi, 565 Osaka, Japan
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE85-A17126
Reference9 articles.
1. Error Due to Nuclear Data Uncertainties in the Prediction of Large Liquid-Metal Fast Breeder Reactor Core Performance Parameters
2. P. HAMMER, “Proposal for Burnup Calculation Applied to the NEACRP Fast Breeder Benchmark,” NEACRP-A-439, Nuclear Energy Agency Committee on Reactor Physics (1980).
3. Determination and Application of Generalized Bias Operators Using an Inverse Perturbation Approach
4. Methods of Adjustment and Error Evaluation of Neutron Capture Cross Sections; Application to Fission Product Nuclides
5. J. D. DRISCHLER and C. R. WEISBIN, “Compilation of Multigroup Cross Section Covariance Matrices for Several Important Reactor Materials,” ORNL-5318, Oak Ridge National Laboratory (1977).
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1. Build-up of actinides in irradiated fuel rods of the ET-RR-1 reactor;Annals of Nuclear Energy;2001-09
2. Prediction Uncertainty Analysis of Neutronic Properties of Fast Breeder Reactor by Use of Sensitivity-Based Methodology;Journal of Nuclear Science and Technology;1992-10
3. Uncertainty in the Burnup Reactivity Swing of Liquid-Metal Fast Reactors;Nuclear Science and Engineering;1991-11
4. Uncertainty Evaluation of Burnup Properties of Large Fast Reactors Using Data Adjustment Method;Journal of Nuclear Science and Technology;1991-04
5. Burnup Sensitivity Analysis in a Fast Breeder Reactor—Part I: Sensitivity Calculation Method with Generalized Perturbation Theory;Nuclear Science and Engineering;1985-09
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