Computational design and optimization of a neutron imaging beamline using Monte Carlo and deterministic SN radiation transport for the Utah TRIGA reactor

Author:

Hartos Michael J.ORCID,Wang Meng-Jen (Vince),Sjoden Glenn E.ORCID

Funder

USNRC

The University of Utah

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

Reference18 articles.

1. Al-Basheer, Ahmad & Sjoden, Glenn. (2006). SU‐FF‐T‐81: Adaptive Differencing Schemes with Parallel Computing for Detailed SN Solutions of a Co‐60 Radiotherapy Unit. Medical Physics. 33. 2067-2067. 10.1118/1.2241007.

2. Advanced methodology for selecting group structures for multigroup cross-section Generation;Alpan;Proc. PHYSOR.,2000

3. ENDF/B-VII. 0: Next generation evaluated nuclear data library for nuclear science and technology;Chadwick;Nucl. Data Sheets,2006

4. 3D Neutron Transport and HPC: A PWR Full Core Calculation Using PENTRAN SN Code and IBM BLUEGENE/P Computers;Courau;Prog. Nuc. Sci. and Tech. J.,2011

5. ICRP, 2007. The 2007 Recommendations of the International Commission on Radiological Protection. ICRP Publication 103, Elsevier, Oxford, UK.

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