Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

DESIGN OF LSDS FOR ISOTOPIC FISSILE ASSAY IN SPENT FUEL

  • Received : 2013.06.04
  • Accepted : 2013.08.06
  • Published : 2013.12.20
Download PDF
⟨ Previous Next ⟩

Abstract

A future nuclear energy system is being developed at Korea Atomic Energy Research Institute (KAERI), the system involves a Sodium Fast Reactor (SFR) linked with the pyro-process. The pyro-process produces a source material to fabricate a SFR fuel rod. Therefore, an isotopic fissile content assay is very important for fuel rod safety and SFR economics. A new technology for an analysis of isotopic fissile content has been proposed using a lead slowing down spectrometer (LSDS). The new technology has several features for a fissile analysis from spent fuel: direct isotopic fissile assay, no background interference, and no requirement from burnup history information. Several calculations were done on the designed spectrometer geometry: detection sensitivity, neutron energy spectrum analysis, neutron fission characteristics, self shielding analysis, and neutron production mechanism. The spectrum was well organized even at low neutron energy and the threshold fission chamber was a proper choice to get prompt fast fission neutrons. The characteristic fission signature was obtained in slowing down neutron energy from each fissile isotope. Another application of LSDS is for an optimum design of the spent fuel storage, maximization of the burnup credit and provision of the burnup code correction factor. Additionally, an isotopic fissile content assay will contribute to an increase in transparency and credibility for the utilization of spent fuel nuclear material, as internationally demanded.

Keywords

References

  1. M. E. Abhold et al., "Survey of Seven Measurement Techniques for Quantifying the Fissile Content of Spent Fuel," LA-UR-07-3336, LANL (2007).
  2. YongDeok Lee, et al., "Development of LSDS spectrometer for nuclear fissile assay," Global2009, Paris, France, Sept. 7-10, 2009.
  3. YongDeok Lee, et al., "Design of Lead Slowing Down Spectrometer for Spent Fuel Fissile Assay," 52nd INMM, Palm Desert, California, July 17-21, 2011.
  4. D. Rochman, R.C. Haight, J.M. O'Donnel, A. Michaudon, S.A. Wender, D.J. Vieira, E.M. Bond, T.A. Bredeweg, A. Kronenberg, J.B. Wilhelmy, T. Ethvignot, T. Granier, M. Petit, and Y. Danon, "Characteristics of a Lead Slowing-Down Spectrometer Coupled to the LANSCE Accelerator," Nuclear Instruments and Methods in Physical Research A, 550, pp.397 (2005). https://doi.org/10.1016/j.nima.2005.04.075
  5. A. Gavron, et al., "Analysis of Spent Fuel Assay with a Lead Slowing Down Spectrometer," Global 2009, Paris, France, Sept. 6-11, 2009.
  6. A. G. Croff, "ORIGEN2 Isotope generation and depletion code matrix exponential method," ORNL/NUREG/CSD-2/V2/R6, Oak Ridge National Laboratory (1985).
  7. MCNP, D. B. Pelowitz, ed., "MCNP: A General Monte Carlo Code for Neutron and Photon Transport," LA-CP-05-0369, Los Alamos National Laboratory (2005).
  8. Horia R. Radulescu et al., "Pulsed Neutron Generator Facility for Slowing Down Time Spectrometry," ANRCP-1999-29, Texas at Austin (1999).
  9. N. Baltateanu, M. Jurba, V. Calian, G. Stoenescu, "Optimal Fast Neutron Sources Using Linear Electron Accelerators," Proceedings of EPAC 2000, Vienna, Austria, Oct. 7-10, 2000.
  10. P. C. Durst et al., "Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities," PNNL-17151, Pacific North Western National Lab. (2007).