A three-dimensional criticality safety analysis code for spent fuel solution system

Author:

Wang Yongping,Yin Huabei,Shi Chen,Wu HongchunORCID,Xu Mengxia,Gou Junli,Liu Guoming,Sheng Huiming,Zu Tiejun

Funder

China National Nuclear Corporation

Publisher

Elsevier BV

Reference14 articles.

1. Development of a new simulation code for evaluation of criticality transients involving fissile solution boiling;Basoglu;Japan Atomic Energy Research Institute,1998

2. Accuracy of a predictor-corrector quasi-static method for space-time reactor dynamics;Dulla,2006

3. SILENE Reactor: Results of Selected Typical Experiments;Francis,1994

4. FLUID FUEL REACTORS: Molten Salt Reactors, Aqueous Homogeneous Reactors, Fluoride Reactors, Chloride Reactors, Liquid Metal Reactors and Why Liquid Fission. V20181227c;Lane,2018

5. Inter-code comparison exercise for criticality excursion analysis;Miyoshi;Nuclear Science,2009

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