Data testing of ENDF/B-VI
Conference
·
OSTI ID:10158897
A number of the fast reactor and thermal reactor benchmarks have been analyzed using nuclear data from ENDF/B-VI Release 2. Data were prepared with the NJOY nuclear data processing system in MATXS and ACE formats. Transport calculations were preformed with ONEDANT and TWODANT using transport tables prepared by the TRANSX code and with the MCNP Monte Carlo code.
- Research Organization:
- Los Alamos National Lab., NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 10158897
- Report Number(s):
- LA-UR--94-1541; CONF-940507--21; ON: DE94013247
- Country of Publication:
- United States
- Language:
- English
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