Radiation dose rate distributions of spent fuel dry casks estimated with MAVRIC based on detailed geometry and continuous-energy models

Author:

Gao Yuan,Hughes Christopher R.,Greulich Christopher R.,Tulenko James E.,Enqvist Andreas,Baciak James E.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference19 articles.

1. U.S. Department of Energy, Fuel Cycle Research & Development, Nuclear Fuels Storage & Transportation (FCRD-NFST), 2013 Commercial Spent Nuclear Fuel and High-Level Radioactive Waste Inventory Report, FCRD-NFST-2013-263, Rev. 4

2. Automated variance reduction of Monte Carlo shielding calculations using the discrete ordinates adjoint function;Wagner;Nucl. Sci. Eng.,1998

3. Monte Carlo variance reduction with deterministic importance functions;Haghighat;Prog. Nucl. Ener.,2003

4. SCALE Code System, ORNL/TM-2005/39, Version 6.2.1,2016

5. Monte Carlo shielding analysis capabilities with MAVRIC;Peplow;Nucl. Technol.,2011

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