The ENDF71x Library

Released: 2011-07-25

ENDF71x is a continuous-energy neutron data library for use with MCNP versions 5 and later. The library contains data from 423 ENDF/B-VII.1 evaluated nuclear data files. The data were processed using the NJOY99.393 code (except ³⁵Cl which was processed with NJOY 2012) and include, as appropriate, data for

• delayed-neutron spectra,
• unresolved-resonance probability tables,
• detailed charged-particle production,
• and using tabular angular distributions.

The ENDF71x library contains data for 7 temperatures:

• .80c - 293.6 K
• .81c - 600 K
• .82c - 900 K
• .83c - 1200 K
• .84c - 2500 K
• .85c - 0.1 K
• .86c - 250 K

The ENDF71x library is the ACE library release based on the ENDF/B-VII.1 library. It supersedes the ENDF70 library (based on ENDF/B-VII.0), ACTI library (based on ENDF/B-VI, Release 8), ENDF66 library (based on ENDF/B-VI, Release 6), URESA library (based on ENDF/B-VI, Release 4), and ENDF60 library (based on ENDF/B-VI, Release 2). The ENDF/B-VII.1 library represents an update of data in the ENDF/B-VII.0 release five years earlier. ENDF/B-VII is based on a revised set of international standard cross sections, includes major updates for almost all the actinides, an entirely new set of fission product data, and updates to many of the light isotopes and structural materials.

Documentation

1. "Release of ENDF/B-VII.1-based Continuous Energy Neutron Cross Section Data Tables for MCNP," Conlin, J.L., Gardiner, S.J., Parsons, D.K., Kahler, A.C., Lee, B., White, M.C., LA-UR-20240 (Report) LA-UR-13-24077 (Presentation)
2. "Verification and Validation of the ENDF/B-VII.1-based Continuous Energy Data Tables for MCNP6," Conlin, J.L., Parsons, D.K., Gardiner, S.J., Gray, M.G., Lee, B., Kahler, A.C., White, M.C., LA-UR-13-26742
3. "Data Processing for Criticality Safety at LANL: ENDF/B-VII.1 and Beyond," Conlin, J.L., Parsons, D.K., Gardiner, S.J., Gray, M.G., Lee, B., Kahler, A.C., White, M.C., (2014) LA-UR-14-21821
4. "Continuous Energy Neutron Cross Section Data Tables Based upon ENDF/B-VII.1," Conlin, J.L., Parsons, D.K., Gardiner, S.J., Gray, M.G., Lee, B., Kahler, A.C., White, M.C., (2013) LA-UR-13-20137
5. "LANL Data Testing Support for ENDF/B-VII.1," Kahler, A.C., MacFarlane, R.E., Mosteller, R.D., Kiedrowski, B.C., Chadwick, M.B., (2012) LA-UR-12-20002
6. "LANL Data Evaluation Support for ENDF/B-VII.1," Chadwick, M.B., Talou, P., Kawano, T., Hale, G., Lestone, J., MacInnes, M., Parsons, D.K., Conlin, J.L., Kahler, A.C., (2012) LA-UR-12-20003

Benchmarking

7. "ENDF/B-VII.1 Neutron Cross Section Data Testing with Critical Assembly Benchmarks," A. C. Kahler, R. E. MacFarlane, R. D. Mosteller, B. C. Kiedrowski, M. B. Chadwick, R. D. McKnight, R. M. Lell, G. Palmiotti, H. Hiruta, M. Herman, R. Arcilla, J. C. Sublet, A. Trkov, M. Dunn, T. H. Trumbull, M.L. Zerkle, R. R. Gouw, (2011) LA-UR-11-11271
8. "Comparison of ENDF71x and ENDF70 Using ICSBEP Criticality Benchmarks in MCNP6," Gardiner, S.J., Conlin, J.L., Kahler, A.C., Parsons, D.K., (2013), LA-UR-13-28503
9. "Comparison of ENDF71x and ENDF70 Using ICSBEP Criticality Benchmarks in MCNP6," Gardiner, S.J., Conlin, J.L., Kahler, A.C., Parsons, D.K., LA-UR-13-24647
10. "Validation of MENDF71x," Conlin, J.L., Gardiner, S.J., Parsons, D.K., (2013), LA-UR-13-28346
11. "Verification and Validation of MENDF71x," Conlin, J.L., Dahl, J.A., Gardiner, S.J., Parsons, D.K., Gray, M.G., Lee, M.B., While, M.C., LA-UR-13-27412