Decay heat uncertainty for BWR used fuel due to modeling and nuclear data uncertainties

Author:

Ilas Germina,Liljenfeldt Henrik

Funder

U.S. Department of Energy

US Department of Energy NGSI-SF Program

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

Reference29 articles.

1. Ade, B.J., Marshall, W., Martinez-Gonzales, J., and Bowman, S.M., 2016. Effects of control blade history, axial coolant density profiles, and axial burnup profiles on BWR burnup credit, CD Proceedings of PHYSOR 2016, Sun Valley, USA.

2. SCALE 6: comprehensive nuclear safety analysis code system;Bowman;Nucl. Technol.,2011

3. Bratton, R.N., Ivanov, K., Jessee, M.A., Wieselquist, W.A., 2014. Bias and uncertainty assessment of Pressurized Water Reactor fuel iotopics using SCALE. In: CD Proceedings of PHYSOR 2014, Kyoto, Japan.

4. Reactor physics methods and analysis capabilities in SCALE;DeHart;Nucl. Technol.,2011

5. Fission yield covariance generation and uncertainty propagation through fission pulse decay heat calculation;Fiorito;Ann. Nucl. Energy,2014

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