Benchmark test of JEFF-3.2, FENDL-3.0 and TENDL-2015 with TOF experiments for graphite, silicon carbide, uranium and multiple-slab samples

Author:

Luo F.,Han R.,Chen Z.,Nie Y.,Sun Q.,Zhang S.,Shi F.,Tian G.,Ruan X.,Ren J.,Ye M.

Funder

National Natural Science Foundation of China

CAS Light of West China

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference20 articles.

1. Modeling of mechanical behavior and design criteria for SiCf/SiC composite structures in fusion reactors;Aiello;Fusion Eng. Des.,2003

2. Benchmark analysis of neutronics performances of a SiC block irradiated with 14 MeV neutrons;Angelone;Fusion Eng. Des.,2002

3. Briesmeister, J.F., (Ed.), MCNPA General Monte Carlo N-Particle Transport Code Version 4C, Los Alamos National Laboratory Report LA-13709-M, 2000 March.

4. Dietze, G., Klein, H., 1982. Physikalisch-Technische Bundesanstalt, NRESP4 and NEFF4 - Monte Carlo codes for the calculation of neutron response functions and detection efficiencies for NE 213 scintillation detectors. PTB-ND-22, 1982.

5. Forrest, R.A., Capote, R., Otsuka, N., et al., FENDL-3.0: Fusion Evaluated Nuclear Data Library, INDC (NDS-0628) (2012).https://www-nds.iaea.org/fendl30/.

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