Comparison of research reactor full-core diffusion calculations with few-group cross sections generated using Serpent and MCU-PTR

Author:

Shchurovskaya M.V.ORCID,Geraskin N.I.,Kruglikov A.E.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference28 articles.

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

2. Comparative validation of Monte Carlo codes for the conversion of a research reactor;Alferov;Ann. Nucl. Energy,2015

3. Analysis of a small PWR core with the PARCS/Helios and PARCS/Serpent code systems;Baiocco;Ann. Nucl. Energy,2017

4. Bretscher, M.M., February 1977. Computing control rod worths in thermal research reactors. Tech. Rep. ANL/RERTR/TM-29. Argonne National Laboratory.

5. Impact of inflow transport approximation on light water reactor analysis;Choi;J. Comput. Phys.,2015

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