Assessment of the traditional neutron-diffusion core-analysis method for the analysis of the Super Critical Water Reactor

Author:

Shen W.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference9 articles.

1. Altiparmakov, D., 2008. New capabilities of the lattice code WIMS-AECL. In: Proceedings of the International Conference on the Physics of Reactors, PHYSOR-2008, Interlaken, Switzerland, September 14–19.

2. Boczar, P.G., Shen, W., Pencer, J., Hyland, B., Chan, P.S.W., Dworshak, R.G., 2010. Reactor physics studies for a pressure-tube SCWR. In: Proceedings of the 2nd Canada–China Joint Workshop on Supercritical Water-Cooled Reactors (CCSC-2010), Toronto, Ontario, Canada, April 25–28.

3. Jenkins, D.A., Rouben, B., Shen, W., 2010. History of RFSP for CANDU fuel management and safety analysis. In: Proceedings of the 31st Annual Conference of the Canadian Nuclear Society, Montreal, Canada, May 24–27.

4. Leppanen, J., 2007. Development of a new Monte Carlo Reactor Physics Code. D. Sc. Thesis, Helsinki University of Technology, VTT Publication 640, Finland, 2007.

5. Phelps, B., Shen W., Varin, E., 2009. MINER: three-dimensional multi-group finite-difference and nodal method for CANDU applications. In: Proceedings of the 30th Annual Conference of Canadian Nuclear Society, Calgary, Canada, May 31–June 3.

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