Transition cycle analysis of light water-cooled SMR core loaded with MOX (TRU) and FCM (TRU) fueled PWR assemblies-Reference-Cited by-同舟云学术

Transition cycle analysis of light water-cooled SMR core loaded with MOX (TRU) and FCM (TRU) fueled PWR assemblies

Published:2021-04 Issue: Volume:375 Page:111103
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Hwang Dae Hee,Hong Ser Gi

Funder

National Research Foundation of Korea

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference24 articles.

1. Cho, J. Y. et al., 2016. DeCART2D v1.1 User’s Manual. Korea Atomic Energy Research Institute, KAERI/UM-40/2016.

2. Cho, J. Y. et al., 2004. MASTER v3.0 User’s Manual. Korea Atomic Energy Research Institute, KAERI/UM-8/2004.

3. Physics analysis of new TRU recycling options using FCM and MOX fueled PWR assemblies;Cho;Nucl. Eng. Technol.,2020

4. Gastaldi, B., Eschbach, R., 2019. Void Effects in Reactor Charged with Plutonium. In: Global 2019, Seattle, WA, September 22-27.

5. Groff, A. G. et al., 1980. A User’s Manual for the ORIGEN2 Computer Code. Oak Ridge Natioanl Laboratory, ORNL/TM-7175.

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Navigating the Path of Least Resistance to Sustainable, Widespread Adoption of Nuclear Power;Sustainability;2024-03-05

2. Neutronic analysis on TRU multi-recycling in PWR-based SMR core loaded with MOX (U-TRU) and FCM (TRU) fueled assemblies;Annals of Nuclear Energy;2022-12

3. Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC;Kerntechnik;2022-02-01

4. Analysis of thorium and transuranium utilization in a small modular reactor;Nuclear Technology and Radiation Protection;2022