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Optimal Cycle Length of MAGNOX Reactor for Weapons-Grade Plutonium Production

  • Received : 2024.03.26
  • Accepted : 2024.04.30
  • Published : 2024.06.30

Abstract

Democratic People's Republic of Korea (DPRK) has produced weapon-grade plutonium in a graphite-moderated experimental reactor at the Yongbyon nuclear facilities. The amount of plutonium produced can be estimated using the Graphite Isotope Ratio Method (GIRM), even without considering specific operational histories. However, the result depends to some degree on the operational cycle length. Moreover, an optimal cycle length can maximize the number of nuclear weapons made from the plutonium produced. For conservatism, it should be assumed that the target reactor was operated with an optimal cycle length. This study investigated the optimal cycle length using which the Calder Hall MAGNOX reactor can achieve the maximum annual production of nuclear weapons. The results show that lower enrichment fuel produced a greater number of critical plutonium spheres with a shorter optimal cycle length. Specifically, depleted uranium (0.69wt%) produced 5.561 critical plutonium spheres annually with optimal cycle lengths of 251 effective full power days. This research is crucial for understanding DPRK's potential for nuclear weapon production and highlights the importance of reactor operational strategy in maximizing the production of weapons-grade plutonium in MAGNOX reactors.

Keywords

Acknowledgement

This work was supported by a 2-Year Research Grant of Pusan National University.

References

  1. C. Braun, S. Hecker, C. Lawrence, and P. Papadiamantis, "North Korean Nuclear Facilities After the Agreed Framework", Center for International Security and Cooperation, Stanford University (2016). 
  2. J.P. McNeece, B.D. Reid, and T.W. Wood. The Graphite Isotope Ratio Method (GIRM): A Plutonium Production Verification Tool, Pacific Northwest National Laboratory Report, PNNL-12095 (1999). 
  3. C.J. Gesh. A Graphite Isotope Ratio Method Primer-A Method for Estimating Plutonium Production in Graphite Moderated Reactors, Pacific Northwest National Laboratory Report, PNNL-14568 (2004). 
  4. J. Han, J. Jang, and H.C. Lee, "A Suitability Study on the Indicator Isotopes for Graphite Isotope Ratio Method (GIRM)", J. Nucl. Fuel Cycle Waste Technol., 18(1), 83-90 (2020).  https://doi.org/10.7733/jnfcwt.2020.18.1.83
  5. K. Kim, J. Han, H.C. Lee, J. Jang, and D. Lee, "Verification of Graphite Isotope Ratio Method Combined With Polynomial Regression for the Estimation of Cumulative Plutonium Production in a Graphite-Moderated Reactor", J. Nucl. Fuel Cycle Waste Technol., 19(4), 447-457 (2021).  https://doi.org/10.7733/jnfcwt.2021.037
  6. S.E. Jensen and E. Nonbol. Description of the Magnox Type of Gas Cooled Reactor (MAGNOX), Nordic Nuclear Safety Research Technical Report, 12-27, NKS-2 (1999). 
  7. H. Lee, W. Kim, P. Zhang, M. Lemaire, A. Khassenov, J. Yu, Y. Jo, J. Park, and D. Lee, "MCS - A Monte Carlo Particle Transport Code for Large-Scale Power Reactor Analysis", Ann. Nucl. Energy, 139, 107276 (2020). 
  8. N.P. Luciano, B.J. Ade, K.S. Kim, and A.J. Conant, "MPACT Verification With Magnox Reactor Neutronics Progression Problems", EPJ Web of Con., 247, 10031 (2021).