Localized neutron flux assessment and verification studies using MCNPX PWR full core model

Author:

Vasiliev A.,Ferroukhi H.,Pecchia M.,Pautz A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference14 articles.

1. Dewes, P., Roppelt, A. The role of cladding material for performance of LWR control assemblies. In: IAEA Technical Committee Meeting on Control Assembly Materials for Water Reactors, Vienna, Austria, October 1998.

2. Ferroukhi, H., Hofer, K., Hollard, J.-M., Vasiliev, A., Zimmermann, M.A., 2008. Core modelling and analysis of the swiss nuclear power plants for qualified R&D applications. In: Proceedings of International Conference on the Physics of Reactors, PHYSOR’08, Interlaken, Switzerland, September 14–19, 2008.

3. Estimation of the fast neutron fluence at control rod tips using a 3-D diffusion/2-D transport calculation scheme;Ferroukhi;Ann. Nucl. Energy,2009

4. Ferroukhi, H., Vasiliev, A., Dufresne, A., Chawla, R., 2012. Towards a reference numerical scheme using MCNPX for PWR control rod tip fluence estimations. In; Proceedings of International Conference on Advances in Reactor Physics, PHYSOR2012, Knoxville, Tennessee, USA, April 15–20, 2012.

5. Goto, K., Sasaki, Y., 1993. Countermeasures for PWR control rod degradation in Japan. In: IAEA Technical Committee Meeting on Advances in Control Assembly Materials for Water Reactors, Vienna, Austria, 29 November–2 December 1993.

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