Development of a CASMO-4/SIMULATE-3/MCNPX calculation scheme for PWR fast neutron fluence analysis and validation against RPV scraping test data

Author:

Vasiliev Alexander,Ferroukhi Hakim,Zimmermann Martin A.,Chawla Rakesh

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference19 articles.

1. Barz, H.-U., Boehmer, B., Konheiser, J., Stephan, I., 2000. Monte Carlo neutron fluence calculations, activation measurements and spectrum adjustment for the KORPUS dosimetry experiment. Forshungszentrum Rossendorf Annual Report 1999/Institute of Safety Research, FZR-284, 95-102. Available from: .

2. Briesmeister, J.F. (Ed.), 2000. MCNP™ – A General Monte Carlo N-Particle Transport Code. Version 4C, LA-13709-M, Manual. Los Alamos National Laboratory.

3. DiGiovine, A.S., Rhodes, J.D. III, 2005. SIMULATE-3. Advanced Three-Dimensional Two-group Reactor Analysis Code. User’s Manual. Studsvik Scandpower SSP-95/15 Rev. 3.

4. Evaluation of the uncertainties in the source distribution for pressure vessel neutron fluence calculations;Haghighat;Nucl. Technol.,1995

5. Calculation and benchmarking of an azimuthal pressure vessel neutron fluence distribution using the BOXER code and scraping experiments;Holzgrewe;Nucl. Technol.,1995

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