References
- General Atomic Company Project Staff, “300 MW(e) Gas Cooled Fast Breeder Reactor Demonstration Plant,” GA-A13045, General Atomic Company (1974).
- R. G. PERKINS and R. J. CERBONE, “Physics Design of the 300-MW(e) Gas-Cooled Fast Breeder Reactor Demonstration Plant Grid Plate Shielding,” GA-A14124, General Atomic Company (1976).
- Reference to A. D. Little Report, “Gas-Cooled Reactor Assessment,” in R. G. PERKINS and R. J. CERBONE, “Grid Plate Shielding Design Confirmation Experiment Test Requirements” (1977); attachment to letter from J. H. Broido to D. E. Emon dated March 11, 1977.
- F. J. MUCKENTHALER, J. L. HULL, and J. J. MANNING, “The GCFR Grid Plate Shield Design Confirmation Experiment,” ORNL/TM-6580, Oak Ridge National Laboratory (1979).
- C. O. SLATER and M. B. EMMETT, “Analysis of a Fuel-Pin Neutron-Streaming Experiment to Test Methods for Calculating Neutron Damage to the GCFR Grid Plate,” in Proc. Fifth Int. Conf. Reactor Shielding, pp. 873–880, Science Press, Princeton, New Jersey (1977).
- R. E. MAERKER, Personal Communication.
- H. GOLDSTEIN, Fundamental Aspects of Reactor Shielding, Addison-Wesley Publishing Company, Inc., Reading, Massachusetts (1959).
- R. E. MAERKER and F. J. MUCKENTHALER, “The Absolute Neutron Spectrum Emerging Through the Large Beam Collimator from the TSR-II Reactor at the Tower Shielding Facility,” ORNL/TM-5183, Oak Ridge National Laboratory (1976).
- C. O. SLATER, S. N. CRAMER, and D. T. INGERSOLL, “Analysis of the ORNL/TSF GCFR Grid-Plate Shield Design Confirmation Experiment,” ORNL-5551, Oak Ridge National Laboratory (1979).
- W. A. RHOADES and F. R. MYNATT, “The DOT-III Two-Dimensional Discrete Ordinates Transport Code,” ORNL/TM-4280, Oak Ridge National Laboratory (1973).
- M. L. GRITZNER, W. W. ENGLE, Jr., W. A. RHOADES, D. R. VONDY, and L. R. WILLIAMS, “FACT: A Computer Code to Process the Neutron and Gamma Angular Flux and Fold Regular and Adjoint Results on a Coupling Surface for Response Analysis,” draft report.
- W. A. RHOADES, D. B. SIMPSON, R. L. CHILDS, and W. W. ENGLE, Jr., “The DOT-IV Two-Dimensional Discrete Ordinales Transport Code with Space-Dependent Mesh and Quadrature,” ORNL/TM-6529, Oak Ridge National Laboratory (1979).
- M. B. EMMETT, “The MORSE Monte Carlo Radiation Transport Code System,” ORNL-4972, Oak Ridge National Laboratory (1975).
- M. L. WILLIAMS and W. W. ENGLE, Jr., “The Concept of Spatial Channel Theory Applied to Reactor Shielding Analysis,” ORNL/TM-5467, Oak Ridge National Laboratory (1976).
- P. KÖHLER and J. LIGOU, “Axial Neutron Streaming in Gas-Cooled Fast Reactors,” Nucl. Sci. Eng., 54, 357 (1974).