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Radiation Monitoring of Nuclear Material in Process for Reducing Environmental Burden

  • YongDeok Lee (Korea Atomic Energy Research Institute) ;
  • Seong-Kyu Ahn (Korea Atomic Energy Research Institute)
  • Received : 2024.04.25
  • Accepted : 2024.06.03
  • Published : 2024.09.30

Abstract

A procedure for minimizing the environmental burden and maximizing the efficiency of storage sites used for the final disposal of spent fuel has been proposed. In this procedure, fission products (highly mobile and producing heat) are collected, and uranium and TRU-RE (transuranium-rare earth) oxide are independently stored. The possibility and applicability of radiation measurement for monitoring the nuclear materials effectively throughout the process has been simulated and evaluated. For the simulation, the properties of the chemical processes were analyzed, the major radiation emitters were determined, and the production of nuclear materials by chemical reactions were evaluated. In each process, the content of nuclear material was changed by up to 20% to represent abnormal conditions. The results showed that the plutonium peak was matched with the change in the TRU content and the measured signal was changed linearly with respect to the content change of the plutonium. From the neutron measurement, a linear response of the TRU content variation was obtained. In addition, a logic diagram was developed for the nuclear monitoring. The integration of radiation detections is recommended for monitoring the process effectively and efficiently.

Keywords

Acknowledgement

This work was supported by the Nuclear Research Foundation of Korea (NRF) grant funded by the Korea government (MSIP) (NRF-2021M2E3A3040093).

References

  1. J.M. Hur. Analysis on Options of Nuclides Management Process, Korea Atomic Energy Research Institute Technical Report, 25-71, KAERI/TR8743 (2021). 
  2. Y.D. Lee. Analysis of Solidified Waste and Nuclear Monitoring, Korea Atomic Energy Research Institute Technical Report, 31-35, KAERI/TR9694 (2023). 
  3. A.M. Bolind and M. Seya. The State of the Art of the Nondestructive Assay of Spent Nuclear Fuel Assemblies. A Critical Review of the Spent Fuel NDA Project of the U.S. Department of Energy's Next Generation Safeguards Initiative, JAEA Report, 87-94, JAEA-REVIEW--2015-027 (2015). 
  4. A.N. Williams, A. Shigrekar, G.G. Galbreth, and J. Sanders, "Application and Testing of a Triple Bubbler Sensor in Molten Salts", Nucl. Eng. Technol., 52(7), 1452-1461 (2020). 
  5. A.N. Williams, G. Cao, and M.R. Shaltry, "Voltammetry Measurements in Lithium Chloride-Lithium Oxide(LiCl-Li2O) Salt: An Evaluation of Working Electrode Materials", Nucl. Eng. Technol., 546, 152760 (2021). 
  6. D.H. Kim, S.E. Bae, T.H. Park, J.Y. Kim, C.W. Lee, and K. Song, "Real-Time Monitoring of Metal Ion Concentration in LiCl-KCl Melt Using Electrochemical Techniques", Microchem. J., 114, 261-265 (2014). 
  7. N.J. Gese, J.F. Jue, B.E. Serrano, and G.L. Fredrickson, "Potentiometric Sensor for Real-Time Remote Surveillance of Actinides in Molten Salts", Conference: Institute of Nuclear Materials Management (INMM) 53rd Annual Meeting, INL/CON-12-24475, INL, Idaho (2012). 
  8. S.H. Park, S.K. Han, and S.K. Ahn, "Monitoring of Oxygen in Simulated Electrolytic Reduction Salt of Pyroprocessing Using Laser-Induced Breakdown Spectroscopy", Appl. Spectrosc., 75(11), 1358-1363 (2021). 
  9. A.G. Croff, ORIGEN2 Isotope Generation and Depletion Code: Matrix Exponential Method, Oak Ridge National Laboratory (1983). 
  10. E. Branger, S. Grape, and P. Jansson, "Partial Detect Detection Using the DCVD and a Segmented Region-Of-Interest", J. Instrum., 15, P07009 (2020). 
  11. Z. Elter and S. Grape, "A Methodology to Identify Partial Defects in Spent Fuel Using Gamma Spectroscopy Data", Esarda Bulletin, 61, 22-31 (2020). 
  12. Y. Ham, P. Kerr, S. Sitaraman, R. Swan, R. Rossa, and H. Liljenfeldt, "Partial Defect Verification of Spent Fuel Assemblies by PDET: Principle and Field Testing in Interim Spent Fuel Storage Facility (CLAB) in Sweden", Proc. of the 2015 4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications, 10.1109/ANIMMA.2015.7465608, IEEE, Lisbon (2015). 
  13. D.B. Pelowitz, ed., MCNP: A General Monte Carlo Code for Neutron and Photon Transport, Los Alamos National Laboratory, LACP-05-0369 (2005).