Analysis of uranium oxide fuel transmutation in VVER-1000 reactor using VISTA and WIMS-D4 codes

Author:

Abbasi Akbar

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

Reference22 articles.

1. Burnup-dependent core neutronics analysis and calculation of actinide and fission product inventories in discharged fuel of a material test research reactor;Ahmad;Prog. Nucl. Energy,2006

2. Impact of PWR spent fuel variations on back-end features of advanced fuel cycles with tru-fueled VHTR;Alajo;Ann. Nucl. Energy,2011

3. Fuel burnup analysis for IRIS reactor using MCNPX and WIMS-D5 codes;Amin;Radiat. Phys. Chem.,2017

4. Ceyhan, M., 2007. Modelling for nuclear material flows in the nuclear fuel cycle. InFissile material management strategies for sustainable nuclear energy. Proceedings of a technical meeting.

5. Actinide evolution and equilibrium in fast thorium reactors;Coates;Ann. Nucl. Energy,2010

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