Large-scale Monte Carlo neutron transport calculations with thermal hydraulic feedback

Author:

Ivanov A.,Sanchez V.,Stieglitz R.,Ivanov K.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference35 articles.

1. Bernnat, W., 2012. Coupled monte carlo neutronics and thermal hydraulics for power reactors. In: Proc. Int. Conf. PHYSOR 2012, Knoxville, Tennessee, USA CD-ROM.

2. Brown, F., 2007. Wielandt acceleration for MCNP5 monte carlo eigenvalue calculations. In: Proc. Int. Conf. PHYSOR 2007, Monterey, California CD-ROM.

3. Brown, F.B., 2006. The makxsf code with doppler broadening, Technical Report LA-UR-06-7002. Los Alamos National Laboratory, Los Alamos, NM.

4. Cabellos, O., 2006. Processing of the JEFF-3.1 Cross Section Library into Continuous Energy Monte Carlo Radiation Transport and Criticality Data Library. NEA-NSC-DOC 18.

5. Compassion of global variance reduction techniques for monte carlo radiation transport simulation of iter;Davis;Fusion Eng. Des.,2011

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