REFERENCES
- R.J. HOWERTON, “A Review of Nuclear Reaction Data Evaluation in the United States,” Trans. Am. Nucl. Soc. 49, 192 (1985)
- Sol Pearlstein, “The International Scope of Data Evaluation,” ibid., p. 193.
- J.L. ROWLANDS and N. TUBBS, “The Joint Evaluated File: A New Nuclear Data Library for Reactor Applications.” Proc. Intl. Conf. Nuclear Data for Basic and Applied Science, May 13–17, 1985, Santa Fe, NM, USA
- C.G. CAMPBELL and E. FORT, “JEF: A New Nuclear Data File for Reactor Calculations,” Trans. Am. Nucl. Soc. 49, 194 (1985)
- F. MANN, Hanford Engineering Development Laboratory, private communication, May 1985.
- D.L. SMITH, et al. “Overview of the Blanket Comparison and Selection Study,” Fusion Technology, 8, 10 (1985)
- R.E. MacFarlane, D.W. MUIR, and R.M. BOICOURT, “The NJOY Nuclear Data Processing System, Volume 1 User’s Manual,” LA-9303-M, ENDF-324, Los Alamos National Laboratory, May 1982.
- S. PELLONI, C. HIGGS, and J. STEPANEK, “The NJOY Nuclear Data Processing System: The COLLGR, ECOMBR, SEPR, DICTR, MANAGR, EPLOTR, CPLOTR and ACOMBR Modules,” Swiss Federal Institute for Reactor Research, EIR—Report No. 566, August 1985.
- C.R. WEISBIN, et al. “VITAMIN-E: An ENDF/B-V Multigroup Cross Section Library for LMFBR Core and Shield, LWR Shield, Dosimetry and Fusion Blanket Technology,” ORNL-5505, Oak Ridge National Laboratory (1980)
- M.R.E. MacFarlane, “TRANSX-CTR: A Code for Interfacing MATXS Cross-Section Libraries to Nuclear Transport Codes for Fusion Systems Analysis, Los Alamos National Laboratory report, LA-9863-MS, March 1984.
- J. BRIESMEISTER, Los Alamos National Laboratory, private communication, March 22, 1984.
- Los Alamos Monte Carlo Group, “MCNP—A General Monte Carlo Code for Neutron and Photon Transport,” LA-7396-M, Rev., Los Alamos National Laboratory (1981)
- P.G. YOUNG, “Evaluation of n + 7Li Reactions Using Variance-Covariance Techniques,” Trans. Am. Nucl. Soc. 39, 272 (1981); note this evaluation was formally adopted as the version V of ENDF/B-V file for 7Li in 1984.
- J. STEPANEK, “The DPN Surface Flux Integral Transport Method with General P Polynomial Approximation,” EIR Report No. 365, Swiss Federal Institute for Reactor Research, Würenlingen, Switzerland (1979)
- S. PELLONI and E.T. CHENG, “The Effect of Self-Shielding of Resonance Cross-Sections on LOTUS Fusion-Fission Device,” Fusion Technology, 8, 1063 (1985)