Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD

Author:

Park Ho JinORCID,Lee Dong Hyuk,Jeon Byoung KyuORCID,Shim Hyung Jin

Funder

Brain Korea 21 Plus Project

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference20 articles.

1. Users Manual, Version 1.00 for MONTEBURNS, Version 3.01, LA-UR—98-2718;Poston,1998

2. Validation of a continuous-energy Monte Carlo burn-up code MVP-BURN and its application to analysis of post irradiation experiment;Okumura;J. Nucl. Sci. Technol.,2000

3. Comparison of MCNPX-C90 and TRIPOLI-4-d for fuel depletion calculations of a gas-cooled fast reactor;Reyes-Ramírez;Ann. Nucl. Energy,2010

4. McCARD: Monte Carlo code for advanced reactor design and analysis;Shim;Nucl. Eng. Tech.,2012

5. Serpent–a Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code;Leppänen,2013

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