Comparative validation of Monte Carlo codes for the conversion of a research reactor

Author:

Alferov V.P.,Radaev A.I.,Shchurovskaya M.V.,Tikhomirov G.V.,Hanan N.A.,van Heerden F.A.

Funder

U.S. Department of Energy, the National Nuclear Security Administration, the Office of Defense Nuclear Nonproliferation

Ministry of Education and Science of the Russian Federation

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference11 articles.

1. MCU-PTR program for high-precision calculations of pool and tank type research reactors;Alekseev;Atom. Energy,2011

2. The status of MCU-5;Alekseev;Phys. Atom. Nucl.,2012

3. Hanan, N.A., Olson, A.P., Pond, R.B., Matos, J.E., 1998. A Monte Carlo burnup code linking MCNP and REBUS. In: Proceedings of the 20th International Meeting on Reduced Enrichment for Research and Test Reactors RERTR 1998, October 18–23, 1998, São Paulo, Brazil. .

4. Izhutov, A.L., Starkov, V.A., Pimenov, V.V., Fedoseev, V.E., et al., 2008. The status of testing LEU U-Mo full-size IRT type fuel elements and mini-elements in the MIR reactor. In: Proceedings of the 30th International Meeting on Reduced Enrichment for Research and Test Reactors RERTR 2008, October 5–9, 2008, Washington, DC, USA. .

5. Leppänen, J., 2005. A new assembly-level Monte Carlo neutron transport code for reactor physics calculations. In: M&C 2005, September 12–15, 2005, Avignon, France.

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