Uncertainty Evaluation of Burnup Properties of Large Fast Reactors Using Data Adjustment Method
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/18811248.1991.9731356
Reference10 articles.
1. Error Due to Nuclear Data Uncertainties in the Prediction of Large Liquid-Metal Fast Breeder Reactor Core Performance Parameters
2. Adjustment of Group Cross Sections by Means of Integral Data, (I)
3. Application of Sensitivity and Uncertainty Methodology to Fast Reactor Integral Experiment Analysis
4. Prediction Uncertainty Evaluation Methods of Core Performance Parameters in Large Liquid-Metal Fast Breeder Reactors
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1. Estimation of Error Propagation in Monte-Carlo Burnup Calculations;Journal of Nuclear Science and Technology;1999-09
2. Approximate Calculation Method for Second Order Sensitivity Coefficient;Journal of Nuclear Science and Technology;1994-11
3. A Combined Cross-Section Adjustment and Bias Factor Method for Accurate Prediction of Fast Breeder Reactor Core Performance Parameters;Nuclear Science and Engineering;1993-05
4. Prediction Uncertainty Analysis of Neutronic Properties of Fast Breeder Reactor by Use of Sensitivity-Based Methodology;Journal of Nuclear Science and Technology;1992-10
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