Impact of Uncertainty Reduction on Lead-Bismuth Coolant in Accelerator-Driven System Using Sample Reactivity Experiments

Author:

Katano Ryota12ORCID,Oizumi Akito1ORCID,Fukushima Masahiro1ORCID,Pyeon Cheol Ho3ORCID,Yamamoto Akio2ORCID,Endo Tomohiro2ORCID

Affiliation:

1. Japan Atomic Energy Agency, Nuclear Science and Engineering Center, Shirakata 2-4, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan

2. Nagoya University, Department of Applied Energy, Graduate School of Engineering, Furo-cho, Chikusa-ku, Nagoya 464-8603, Japan

3. Kyoto University, Institute for Integrated Radiation and Nuclear Science, Asahiro-nishi, Kumatori-cho, Sennan-gun, Osaka 590-0494, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Reference22 articles.

1. Impact of impurity in transmutation cycle on neutronics design of revised accelerator-driven system

2. Sensitvity and Uncertainty Analysis for a Minor-actinide Transmuter with JENDL-4.0

3. On the importance of target accuracy assessments and data assimilation for the co-development of nuclear data and fast reactors: MYRRHA and ESFR

4. M. L. WILLIAMS et al., “6.6 TSURFER: An Adjustment Code to Determine Biases and Uncertainties in Nuclear System Responses by Consolidating Differential Data and Benchmark Integral Experiments,” in “SCALE Code System,” ORNL/TM-2005/39, Version 6.2.3, p. 6–329, B. T. REARDEN and M. A. JESSEE, Eds., Oak Ridge National Laboratory (Mar. 2018).

5. Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques

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