Detailed neutronic analysis of a MOX-fueled metal-cooled reactor

Author:

Jamil ZeeshanORCID,Wu Bin,Yu Shengpeng,Yang Qi,Khan Muhammad Salman,Ali Muhammad Younas,Hu Liqin

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference25 articles.

1. A survey report, World Energy Resources, World Energy Council (2013), ISBN: 978-0-946121-29-8.

2. Aziz, M. et al., 2017. Burnup Analysis for BN-600 Reactor Core Fuelled with MOX Fuel and Minor Actinides, FR17 2017, June 26–29, Russia.

3. An overview of the experiments performed at the BFS facilities and evaluated for the international reactor physics experiment evaluation project;Dulin;Nucl. Sci. Eng.,2014

4. Modeling of SFR cores with Serpent–DYN3D codes sequence;Fridman;Ann. Nucl. Energy,2013

5. Verification of a nuclear analysis system for fast reactors using BFS-62 critical experiment;Hazama;Nucl. Sci. Technol.,2004

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1. SuperMC Model of the TRIGA Vienna Reactor and its Confirmation;2019 International Conference on Power Generation Systems and Renewable Energy Technologies (PGSRET);2019-08

2. Benchmarking the HENDL-3.0 data library by simulating a sodium-cooled test reactor;Annals of Nuclear Energy;2018-12

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