Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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DETERMINATION OF BURNUP AND PU/U RATIO OF PWR SPENT FUELS BY GAMMA-RAY SPECTROMETRY

  • Published : 2009.12.31
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Abstract

The isotope ratio of $^{134}Cs/^{137}Cs$ in a spent PWR fuel sample was obtained with a newly developed gamma/neutron combined measuring system at KAERI. Burnup and Pu/U ratio of the spent fuel sample were determined by using the measured isotope ratio and the burnup-isotope ratio correlation equations calculated from the ORIGEN-ARP computer code. The results were compared and evaluated with the chemically determined burnup and Pu/U ratio. As a result of the comparative evaluation, the nondestructively determined burnup and Pu/U ratio values showed a good agreement with the chemically obtained results to within a 4.5% and 0.8% difference, respectively.

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References

  1. W.D. Ruhter, R.S. Lee, H. Ottmar and S. Guardini, “Nondestructive assay measurements applied to reprocessing plants,” Proceedings of the tripartite seminar on Nuclear Material Accounting and Control at Radiochemical Plants, Obninsk, Russia, 135~155(1988)
  2. R. Gunnink, “MGA: A Gamma-Ray Spectrum Analysis Code for Determining Plutonium Isotopic Abundances,” Volume 1, Lawrence Livermore National Laboratory, Livermore, CA, UCRL-LR-103220, (1990)
  3. T.E. Sampson et al., “Test and Evaluation of the FRAM Isotopic Analysis Code for EURATOM Applications,” LAUR-98-2007, (2007)
  4. DOE, “Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages,” DOE/RW-0472 Rev. 2, 1-1~1-13 (1988)
  5. B.L. Broadhead et al., “Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel,” ORNL/TM-12742, 1~25 (1995)
  6. A.S. Chesterman and P.A. Clark, “Spent Fuel and Residue Measurement Instrumentation at the Sellafield Nuclear Fuel Reprocessing Facility,” BNFL Instruments Ltd., UK, (1995)
  7. Y. Nakahara, J. Inagawa, T. Suzuki, N. Kohno, R. Nagaishi, M. Ohnuki and T. Suzaki, “Experimental Verification of Availability of $(^{134}Cs/^{137}Cs)/ (^{106}Ru/^{137}Cs)$ Gamma-ray Intensity Ratio as a Burnup Monitor for LWR Fuels,” Proceeding of $6^{th}$ International Conference on Nuclear Criticality Safety, 1693 (1999)
  8. C.V. Parks, J.C. Wagner and C.J. Withee, “U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Casks,” IAEA Technical Committee Meeting on Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, London, UK, (2005)
  9. D. Reilly, N. Ensslin, and H. Smith, Jr., “Passive Nondestructive Assay of Nuclear Materials (PANDA),” LA-UR-90-732, 153-157(1991)
  10. K. Way, L.W. Rose et al., “Atomic Data & Nuclear Data Tables”, Academic Press, Volume 20, Number 3, (1977)
  11. I.C. Gauld, S.M. Bowman, J.E.Horwedel, L.C. Leal, “ORIGEN-ARP: Automatic Rapid Processing for Spent Fual Depletion, Decay, and Source Term Analysis,” ORNL/NUREG/CSD-2/V1/R7, Volume 1, Revision 7, (2004)
  12. ASTM, "ASTM-E321-96 Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method)," American Society for Testing and Materials, Vol.12.01, (2000)
  13. T.R. England and B.F. Rider, “Evaluation and Compilation of Fission Product Yields 1993,” LA-UR-94-3106, 1-29 (1994)

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