Abstract
FENDL-2, the latest version of Fusion Evaluated Nuclear Data Library, had been developed based on selection of evaluated data from ENDF/B-VI, JENDL-3, JENDL-FF, BROND-2 and EFF-3 and distributed for benchmark analysis recently. Integral data test of FENDL-2 has been performed to qualify and validate the working library with a variety of neutronic integral experiments. Calculations and analyses of neutron leakage spectra and reaction rates have been performed with the three dimensional Monte Carlo transport code MCNP and FENDL-2 data library. The results have been compared with the measured results as well as the results obtained previously with FENDL-1, EFF, JENDL-FF.
| Original language | English |
|---|---|
| Pages (from-to) | 697-702 |
| Number of pages | 6 |
| Journal | Journal of Nuclear Science and Technology |
| Volume | 37 |
| DOIs | |
| State | Published - Mar 2000 |
Keywords
- 14 MeV neutron
- Benchmark
- Calculation
- Combined assembly
- Data evaluation
- Fusion
- Integral data test
- Neutron spectrum
- Neutronic experiment
- Nuclear data library
- Reaction rate
- Spherical shell
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