References
- A. P. FRAAS, “Conceptual Design of the Blanket and Shield Region and Related Systems for a Full Scale Toroidal Fusion Reactor,” ORNL-TM-3096, Oak Ridge National Laboratory (1973).
- R. W. CONN, T. Y. SUNG, and M. A. ABDOU, “Comparative Study of Radioactivity and Afterheat in Several Fusion Reactor Blanket Designs,” FDM-113, University of Wisconsin (1974).
- WILLIAM G. PRICE, Jr., “Blanket Neutronic Studies for a Fusion Power Reactor,” Proc. Fifth Symp. Engineering Problems of Fusion Research, Princeton University, November 5–9, 1973, IEEE Publication No. 73CH0843-3-NPS, p. 75 (1974).
- D. STEINER, Nucl. Fusion, 14, 33 (1974).
- W. W. ENGLE, Jr., “A User’s Manual for ANISN, A One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering,” K-1693, Computing Technology Center, Union Carbide Corporation (1967).
- D. M. PLASTER, R. T. SANTORO, and W. E. FORD, III, “Coupled 100-Group Neutron and 21-Group Gamma-Ray Cross Sections for EPR Calculations,” ORNL-TM-4872, Oak Ridge National Laboratory (1975).
- M. A. ABDOU and R. W. ROUSSIN, “MACKLIB-100 Group Neutron Fluence-to-Kerma Factors and Reaction Cross Sections Generated by the MACK Computer Program from Data in ENDF Format,” ORNL-TM-3995, Oak Ridge National Laboratory (1974).
- N. M. GREENE et al., “AMPX: A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B,” ORNL-TM-3706, Oak Ridge National Laboratory (to be published).
- D. W. MUIR, “DLC-33 Data Library MONTAGE,” Radiation Shielding Information Center, Oak Ridge National Laboratory (1975).
- W. E. ALLEY and R. M. LESSLER, “Neutron Activation Cross Sections,” Nucl. Data Tables, 11, 8-9 (1973).
- H. C. CLAIBORNE and D. K. TRUBEY, Nucl. Am. Tech., 8,5,450 (1970).
- T. A. GABRIEL, J. D. AMBURGEY, and N. M. GREENE, “Recoil Spectra, Damage Energy, and Displacement Cross Sections,” Trans. Am. Nucl. Soc., 21, 67 (1975).
- G. L. KULCINSKI, D. G. DORAN, and M. A. ABDOU, “Comparison of Displacement and Gas Production Rates in Current Fission and Future Fusion Reactors,” UWFDM-15, University of Wisconsin (1974).