Uncertainty Quantification of 237 Np, 241 Am, and 243 Am Reaction Rates in Highly Enriched Uranium Fuel Cores at Kyoto University Critical Assembly-Reference-Cited by-同舟云学术

Uncertainty Quantification of ²³⁷ Np, ²⁴¹ Am, and ²⁴³ Am Reaction Rates in Highly Enriched Uranium Fuel Cores at Kyoto University Critical Assembly

Published:2024-08-09 Issue: Volume: Page:1-16
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Pyeon Cheol Ho¹^ORCID,Oizumi Akito²,Katano Ryota²,Fukushima Masahiro²

Affiliation:

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

2. Japan Atomic Energy Agency, Nuclear Science and Engineering Center, Tokai-mura, Naka-gun, Ibaraki 319-1194, Japan

Funder

Ministry of Education, Culture, Sports, Science and Technology

Publisher

Informa UK Limited

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2024.2380624

Reference32 articles.

1. International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE) Project NEA/NSC/DOC(2006)1 Organization for Economic Co-operation and Development Nuclear Energy Agency (2018).

2. International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook NEA/NSC/DOC(95)03 Organization for Economic Co-operation and Development Nuclear Energy Agency (2018).

3. Measurement and Analysis of Capture Reaction Rate of237Np in Various Thermal Neutron Fields by Critical Assembly and Heavy Water Thermal Neutron Facility of Kyoto University

4. Measurement of 237Np Fission Rate Ratio Relative to 235U Fission Rate in Cores with Various Thermal Neutron Spectrum at the Kyoto University Critical Assembly.

5. Measurement and Analysis of241Am Fission Rate Ratio Relative to235U Fission Rate in Thermal Neutron Systems Using Kyoto University Critical Assembly