3
Views
0
CrossRef citations to date
0
Altmetric
Technical Note

A Hybrid Sn-Diffusion Theory Computational Scheme for Efficient Neutronic Calculations of Externally Moderated Gas Core Reactors

&
Pages 417-425 | Published online: 10 May 2017

References

  • R. E. HYLAND, “Evaluation of Critical Mass for Open Cycle Gas Core Rocket Reactors,” Nucl. Technol., 12, 152 (1971).
  • J. F. KUNZE and J. H. LOFTHOUSE, “Flow and Criticality in the Open Cycle Gas Core Reactor,” Proc. 2nd Symp. Uranium Plasmas, Atlanta, Georgia, November 15–17, 1971, p. 197, American Institute of Aeronautics and Astronautics.
  • J. F. KUNZE, J. H. LOFTHOUSE, and C. G. COOPER, “Benchmark Gas Core Critical Experiments,” Nucl. Sci. Eng., 47, 59 (1972).
  • R. D. O’DELL, F. W. BRINKLEY, Jr., and D. R. MARR, “User’s Manual for ONEDANT: A Code Pacakge for One-Dimensional, Diffusion Accelerated, Neutral-Particle Transport,” LA-9184-M, Los Alamos National Laboratory (Feb. 1982).
  • L. M. PETRIE, N. M. GREENE, J. L. LUCIUS, and J. E. WHITE, “NITAWL: AMPX Module for Resonance Self-Shielding and Working Library Production,” AMPX: A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B, ORNL-TM-3706, Oak Ridge National Laboratory (Mar. 1976).
  • L. M. PETRIE and N. M. GREENE, “XSDRNPM: AMPX Module with One-Dimensional S„ Capability for Spatial Weighting,” AMPX: A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B, ORNL-TM-3706, Oak Ridge National Laboratory (Mar. 1976).
  • M. ALFAKHAR, “Gas Core Reactors: Development of an Effective Acceleration Method for S„ Transport Theory Calculations and Fundamental Shielding Analysis,” PhD Dissertation, University of Florida (1991).
  • S. KAHOOK, “Static and Dynamic Neutronic Analysis of the Uranium Tetra-Fluoride, Ultrahigh Temperature, Vapor Core Reactor System,” PhD Dissertation, University of Florida (1991).
  • N. J. DIAZ, E. T. DUGAN, C. C. OLIVER, E. D. WHITNEY, and E. E. CARROLL, Jr., “Basic Feasibility Studies of Pulsed Gaseous Core Nuclear Systems,” National Science Foundation Final Report, Grant ENG-7728034, University of Florida (1983).
  • “SCALE 4: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation,” NUREG/CR-0200, Rev. 4 (ORNL/NUREG/CSD-2/R4), Vol. II, Oak Ridge National Laboratory (1990).
  • U.K. KUTIKKAD, “Startup and Stability of a Gaseous Core Nuclear Reactor System,” PhD Dissertation, University of Florida (1991).
  • R. E. ALCOUFFE, F. W. BRINKLEY, D. R. MARR, and R. D. O’DELL, “User’s Guide for TWODANT: A Code Package for Two Dimensional, Diffusion-Accelerated, Neutron Particle Transport,” LA-10049-M, Rev. 1.2, Los Alamos National Laboratory (1985).
  • J. F. BRIESMEISTER, Ed., “MCNP-A General Monte Carlo Code for Neutron and Photon Transport, Version 3A,” LA-7396, Rev. 2, Los Alamos National Laboratory (1986).
  • E. T. DUGAN, M. M. PANICKER, and N. J. DIAZ, “Gas Core Nuclear Analysis and Design,” Annual Report, Vol. 2, INSPI-PUB-91-110, University of Florida (1991).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.