Inter-comparison of JEF-2.2 and JEFF-3.1 evaluated nuclear data through Monte Carlo analysis of VVER-1000 MOX Core Computational Benchmark

Author:

Thilagam L.,Karthikeyan R.,Jagannathan V.,Subbaiah K.V.,Lee S.M.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference14 articles.

1. Plutonium build-up credits for a material test research reactor and influence of cross-section differences on actinide production;Ahmad;Nucl. Eng. Des.,2006

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

3. Gehin, J.C., Carbajo, J.J., Ellis, R.J., 2004. Issues in the Use of Weapons-Grade MOX Fuel in VVER-1000 Nuclear Reactors: Comparison of UO2 and MOX Fuels, ORNL.

4. IAEA-NDS, 2009. Evaluated Nuclear Data File (ENDF) Database plotter Version of August 10, 2009, Software Version of 2009.10.06. .

5. JEF-2.2, 2000. .

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