Criticality and burnup analyses of a PBMR-400 full core using Monte Carlo calculation method

Author:

Acır Adem,Coşkun Hasan,Şahin Hacı Mehmet,Erol Özgür

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference11 articles.

1. A simulation of a pebble bed reactor core by the MCNP-4C computer code;Bakhshayesh;Nucl. Technol. Radiat. Prot.,2009

2. In-core fuel management optimization of pebble-bed reactors;Boer;Ann. Nucl. Energy,2009

3. Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices;Bomboni;Nucl. Eng. Des.,2010

4. Coşkun, H., (Supervisor: Assoc. Prof. Dr. Adem Acır), 2010. Neutronic Analysis of Pebble Bed Modular Reactor with Alternative Fuels by Using Monte Carlo Method, Gazi University, Institute of Science and Technology, M.Sc. Thesis, Turkey (in Turkish).

5. Croff, A.G., 1980. A User’s Manual for the ORIGEN2, Computer Code, ORNL/TM-7175.

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2. Development and application of optimal burnup estimation methodology for pebble bed reactor;Annals of Nuclear Energy;2018-07

3. Analysis of a HTR using OpenFOAM® with Porous Media Approach for Turbulent, Compressible Flow;Proceeding of THMT-18. Turbulence Heat and Mass Transfer 9 Proceedings of the Ninth International Symposium On Turbulence Heat and Mass Transfer;2018

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5. Burnup instabilities in the full-core HTR model simulation;Annals of Nuclear Energy;2015-11

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