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Fissile Measurement in Various Types Using Nuclear Resonances

  • Received : 2023.01.04
  • Accepted : 2023.02.20
  • Published : 2023.06.30

Abstract

Neutron resonance transmission technique was applied for assaying isotopic fissile materials produced in the pyro-process. In each process of the pyro-process, a different composition of the fissile material is produced. Simulation was basically performed on 235U and 239Pu assay for TRU-RE product, hull waste, and uranium addition. The resonance energies were evaluated for uranium and plutonium in the simulation, and the linearity in the detection response was examined on the fissile content variation. The linear resonance energies were determined for the analysis of 235U and 239Pu on the different fissile materials. For enriched TRU-RE assay, the sample condition was suggested; The sample density, content, and thickness are the key factors to obtain accurate fissile content. The detection signal is discriminated for uranium and plutonium in neutron resonance technique. The transmitted signal for fissile resonance has a direct relation with the content of fissile. The simulation results indicated that the neutron resonance technique is promising to analyze 235U and 239Pu for various types of the pyro-process material. An accurate fissile assay will contribute toward safeguarding the pyro-processing system.

Keywords

Acknowledgement

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

References

  1. S. Ahn. Preliminary Conceptual Design of Safeguards System for KAPF, Korea Atomic Energy Research Institute Report, 119-150, KAERI-TR6585 (2016). 
  2. S.J. Tobin, H.R. Trellue, and H. Liljenfeldt, "Spent Fuel NDA Research Path for the Sweden Encapsulation-Repository", Conference: IAEA/ASTOR, LA-UR13-24580, 4-25, May 19-21, 2015, Sweden. 
  3. A.M. Bolind and M. Seya. JAEA, The State of the Art of the Nondestructive Assay of Spent Fuel Assembly; A Critical Review of the Spent Fuel NDA Project of the U.S. Department of Energy's Next Generation Safeguards Initiative, Japan Atomic Energy Agency Report, 87-94, JAEA-Review 2015-027 (2015). 
  4. Y.D. Lee and S.K. Ahn, "Sensitivity Simulation on Isotopic Fissile Measurement Using Neutron Resonance", Nucl. Eng. Technol., 54(2), 637-643 (2022).  https://doi.org/10.1016/j.net.2021.08.017
  5. S. Frank, W. Ebert, B. Riley, H.S. Park, Y.Z. Cho, C.H. Lee, M.K. Jeon, J.H. Yang, and H.C. Eun. Waste Stream Treatment and Waste Form Fabrication for Pyroprocessing of Used Nuclear Fuel, Idaho National Laboratory Technical Report, 3-28, INL/EXT-14-34014 (2014). 
  6. T. Hayakawa, N. Kikuzawa, R. Hajima, T. Shizuma, N. Nishimori, M. Fujiwara, and M. Seya, "Nondestructive Assay of Plutonium and Minor Actinide in Spent Fuel Using Nuclear Resonance Fluorescence With Laser Compton Scattering γ-rays", Nucl. Instrum. Methods Phys. Res. A, 621(1-3), 695-700 (2010).  https://doi.org/10.1016/j.nima.2010.06.096
  7. J.W. Behrens, R.G. Johnson, and R.A. Schrack, "Neutron Resonance Transmission Analysis of Reactor Fuel Samples", Nucl. Technol., 67(1), 162-168 (1984).  https://doi.org/10.13182/NT84-A33538
  8. B.J. Quiter, T. Laplace, and B.A. Ludewigt, Examining 239Pu and 240Pu Nuclear Resonance Fluorescence Measurements on Spent Fuel for Nuclear Safeguards, 1-10, LBNL-5721 (2012). 
  9. M. Seya, H. Harada, F. Kitatani, M. Koizuma, H. Tsuchiya, R. Hajima, T. Hayakawa, T. Shizuma, C. Angell, and A. Bolind, "Promising NDA Technologies for Material Accountancy of Nuclear Material in Debris of Melted Fuel of Fukushima-Daiichi NPP", Proc. of the 35th ESARDA Symposium on Safeguards and Nuclear Non-proliferation, 221-229, Joint Research Centre, Belgium (2013). 
  10. J.W. Sterbentz and D.L. Chichester. Neutron Resonance Transmission Analysis (NRTA): A Nondestructive Assay Technique for the Next Generation Safeguards Initiative's Plutonium Assay Challenge, Idaho National Laboratory Technical Report, INL/EXT-10-20620 (2010). 
  11. D.B. Pelowitz, ed., MCNP: A General Monte Carlo Code for Neutron and Photon Transport, Los Alamos National Laboratory, LACP-05-0369 (2005). 
  12. A.G. Croff, ORIGEN2 Isotope Generation and Depletion Code: Matrix Exponential Method, Oak Ridge National Laboratory (1983). 
  13. Y.D. Lee and S.G. Ahn, "Nuclear Measurement in Pyro-processed Wastes", Ann. Nucl. Energy, 143, 107457 (2020).