Depletion analysis of control absorber in a small research reactor

Author:

Park Chang Je,Lee Byungchul,Alnajjar Alaaddin Tareq,Talafha Mohammad Abd,Alkhatib Sari Fathi

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference4 articles.

1. Gauld, I.C., Hermann, O.W., Westfall R.M., 2009. ORIGEN-S: SCALE System Module to Calculate Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms, ORNL/TM-2005/39, Ver.6, Vol. II, Sect. F7, 2009.

2. Gibcus, H., De Leege, P., Labohm, F., De Vries, J., Verkooijen, A., Valko, J., Feltes, W., Heinecke, J., 2003. Options for the delft advanced neutron source. In: Proceedings of the 9th Meeting of the International Groups on Research Reactors, IGORR 2003, Sydney, Australia, 2003.

3. Monte Carlo Code for advanced reactor design and analysis;Shim;Nuclear Engineering and Technology,2012

4. X-5 Monte Carlo Team, 2003. MCNP – A General Monte Carlo N-Particle Transport Code, Version 5, LA-CP-03-0245, Los Alamos National Laboratory, 2003.

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