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Technical Paper

Development of a Low-Enriched-Uranium Core for the MIT Reactor

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Pages 264-279 | Published online: 10 Apr 2017

REFERENCES

  • U.S. DEPARTMENT OF ENERGY, “Reduced Enrichment for Research and Test Reactors,” available on the Internet at http://www.nnsa.doe.gov/na-20/rertr.shtml.
  • J. R. CLARK, S. L. HAYES, M. K. MEYER, G. L. HOFFMAN, and J. L. SNELGROVE, “Update on U-Mo Monolithic and Dispersion Fuel Development,” Proc. Int. Topl. Mtg. Research Reactor Fuel Management Conference, Munich, Germany, March 22–23, 2004, European Nuclear Society (2004).
  • T. NEWTON, “Development of a Low Enrichment Uranium Core for the MIT Reactor,” PhD Thesis, Department of Nuclear Science and Engineering, Massachusetts Institute of Technology (Feb. 2006).
  • E. L. REDMOND II, J. C. YANCH, and O. K. HARLING, “Monte Carlo Simulation of the Massachusetts Institute of Technology Research Reactor,” Nucl. Technol., 106, 1 (1994).
  • T. NEWTON, X. ZU, E. PILAT, and M. KAZIMI, “Modeling the MIT Reactor Neutronics for LEU Conversion Studies,” Proc. Topl. Mtg. Reactor Phys. (PHYSOR 2004), Chicago, Illinois, April 25–29, 2004, American Nuclear Society (2004) (CD-ROM).
  • T. NEWTON, M. KAZIMI, and E. PILAT, “Development of a Low Enrichment Uranium Core for the MIT Reactor,” MIT-NFC-TR-83, Center for Advanced Nuclear Energy Systems, Department of Nuclear Science and Engineering, Massachusetts Institute of Technology (2006).
  • Z. XU, P. HEJZLAR, M. DRISCOLL, and M. KAZIMI, “An Improved MCNP-ORIGEN Depletion Program (MCODE) and Its Verification for High-Burnup Applications,” Proc. Topl. Mtg. Reactor Physics (PHYSOR 2002), Seoul, Korea, October 7–10, 2002, American Nuclear Society (2002) (CD-ROM).
  • L. HU and J. BERNARD, “Thermal-Hydraulic Analysis for the Upgraded MIT Nuclear Research Reactor,” IEEE Trans. Nucl. Sci., 45, 3 (June 1998).
  • L. W. HU, J. A. BERNARD, and M. J. McGUIRE, “Development and Benchmarking of a Thermal-Hydraulics Code for the MIT Nuclear Research Reactor,” Proc. Joint Int. Conf. Mathematical Methods and Supercomputing for Nuclear Applications, Saratoga Springs, New York, October 5–7, 1997, Vol. 2, p. 1117, American Nuclear Society (1997).
  • C. OBENCHAIN, “PARET—A Program for the Analysis of Reactor Transients,” IDO-17282, U.S. Atomic Energy Commission (Jan. 1969).
  • C. CLARK, S. HAYES, D. WACHS, M. MEYER, T. WIENCEK, G. HOFMAN, and M. FINLAY, “Irradiation Testing of Monolithic Fuel at Argonne National Laboratory,” Proc. Research Reactor Fuel Management Conf., Budapest, Hungary, March 2005.
  • W. KENNEDY, “Analysis of the MIT Research Reactor Fission Product and Actinide Radioactivity Inventories,” SB Thesis, Nuclear Engineering Department, Massachusetts Institute of Technology (2004).
  • M. McGUIRE, “An Analysis of the Proposed MITR-III Core to Establish Thermal-Hydraulic Limits at 10 MW,” PhD Thesis, Department of Nuclear Engineering, Massachusetts Institute of Technology (1995).
  • M. ABDELRAHMAN and N. M. ABDURRAHMAN, “Cross Section Libraries for Studies of Plutonium Disposition in LWRs,” ANRCP-1999-28, Amarillo National Resource Center for Plutonium (Oct. 1999).
  • “MCNP 4B, Monte-Carlo N-Particle Transport Code System,” J. BREISMEISTER, Ed., Radiation Shielding Information Center, Los Alamos National Laboratory (1997).
  • “Safety Analysis Report for the MIT Research Reactor (MITR-II),” Section 3.3.1, MITNE-115, Department of Nuclear Engineering, Massachusetts Institute of Technology (Oct. 1970).
  • “Technical Specifications for the MIT Research Reactor,” Section 3.9, Massachusetts Institute of Technology Nuclear Reactor Laboratory (July 1975).

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