Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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POSCA: A computer code for fission product plateout and circulating coolant activities within the primary circuit of a high temperature gas-cooled reactor

  • Received : 2019.03.12
  • Accepted : 2020.02.11
  • Published : 2020.09.25
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Abstract

Numerical prediction of fission product plateout and circulating coolant activities under normal operating conditions is crucial in the design of a high temperature gas-cooled reactor (HTGR). The results are used for the maintenance and repair of the components as well as the safety analysis regarding early source terms under loss of coolant accident scenarios. In this work, a new computer code named POSCA (Plate-Out Surface and Circulating Activities) was developed based on a one-dimensional model to evaluate fission product plateout and circulating coolant activities within the primary circuit of a HTGR. The verification and validation of study for the POSCA code was done using available analytical results and two in-pile experiments (i.e., OGL-1 and VAMPYR-1). The results of the POSCA calculations show that POSCA is able to simulate plateout and circulating coolant activities in a HTGR with fast computation and reasonable accuracy.

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References

  1. N. Iniotakis, C.B. von der Decken, K. Roellig, H.J. Schlesinger, Plate-out fission products and its effect on maintenance and repair, Nucl. Eng. Des. 78 (1984) 273-284. https://doi.org/10.1016/0029-5493(84)90311-X
  2. K. Sawa, I. Murata, S. Shiozawa, M. Matsumoto, A study of plateout fission product behavior during a large-scale pipe rupture accident in a hightemperature gas-cooled reactor, Nucl. Technol. 106 (1994) 265-273. https://doi.org/10.13182/NT94-A34957
  3. IAEA, Fuel Performance and Fission Product Behaviour in Gas Cooled Reactor, IAEA, 1997. IAEA-TECDOC-978.
  4. D. Hanson, Plateout Phenomena in Direct-Cycle High Temperature Gas-Cooled Reactors, EPRI, 2002, 1003387.
  5. M.P. Kissane, A review of radionuclide behaviour in the primary system of a very-high-temperature reactor, Nucl. Eng. Des. 239 (2009) 3076-3091. https://doi.org/10.1016/j.nucengdes.2009.09.012
  6. C.E. Apperson, SUVIUS : A Circulating and Plateout Activity Program for Gas-Cooled Reactors with Arbitrary Radioactive Chains, Los Alamos Scientific Laboratory, 1978. NUREG/CR-0060, LA-7239-MS.
  7. D. Hanson, A Review of Radionuclide Release from HTGR Cores during Normal Operation, EPRI, 2004, 1009382.
  8. Y. Liu, J. Cao, Fission product release and its environment impact for normal reactor operations and for relevant accidents, Nucl. Eng. Des. 218 (2002) 81-90. https://doi.org/10.1016/S0029-5493(02)00200-5
  9. N. Iniotakis, J. Malinowski, K. Muenchow, Initial results of investigations into fission product deposition in in-pile experiments, Nucl. Eng. Des. 34 (1975) 169-180. https://doi.org/10.1016/0029-5493(75)90165-X
  10. M. Richards, Support for HTGR Fuel Performance and Fission Product Transport, Progress Report, Ultra Safe Nuclear Corporation, 2014. USNC-KAERIG00002, Rev. 0.
  11. O. Baba, N. Tsuyuzaki, K. Sawa, Fission Products Plate-Out Analysis Code in the HTGR, PLAIN, Japan Atomic Energy Research Institute (JAERI), 1989. JAERI-M 88-266.
  12. C.C. Stoker, L.D. Olivier, E. Stassen, F. Reitsma, J.J. van der Merwe, PBMR radionuclide source term analysis validation based on AVR operating experience, Nucl. Eng. Des. 240 (2010) 2466-2484. https://doi.org/10.1016/j.nucengdes.2009.10.011
  13. J.S. Yoo, N.I. Tak, H.S. Lim, J.H. Chun, Numerical prediction of the fission product plate-out for a VHTR application, Ann. Nucl. Energy 37 (2010) 471-481. https://doi.org/10.1016/j.anucene.2010.01.009
  14. C. Yoon, J.S. Yoo, H.S. Lim, Preliminary Theory Manual for GAMMA-FP (Fission Products Module of the Transient Gas Multicomponent Mixture Analysis), Korea Atomic Energy Research Institute (KAERI), 2013. KAERI-TR-4933/2013.
  15. N.I. Tak, C. Yoon, Simulation of COMEDIE fission product plateout experiment using GAMMA-FP, in: Transactions of the Korean Nuclear Society Autumn Meeting, Pyeongchang, Korea, Oct. 30-31, 2014.
  16. S. Branney, The Adsorption of Fission Products on VHTR Structural Materials, Ph.D. Dissertation, University of Missouri-Columbia, 2010.
  17. J.D. Seelig, Measurements of Fission Product Sorption on Graphite, Ph.D. Dissertation, University of Missouri-Columbia, 2017.
  18. K.W. Skrable, C. French, G. Chabot, A. Major, A general equation for the kinetics of linear first order phenomena and suggested applications, Health Phys. 27 (1974) 155-157.
  19. N. I. Tak, S. N. Lee, C. K. Jo, One-dimensional model for fission product plateout and circulating coolant activities in a HTGR, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 17-18, 2018.
  20. N.I. Tak, S.N. Lee, C.K. Jo, Verification of the POSCA code using analytic benchmark examples, in: Transactions of the Korean Nuclear Society Autumn Meeting Yeosu, Korea, October 25-26, 2018.
  21. K. Sawa, S. Shiozawa, O. Baba, Analysis of the Plate-Out Distribution in the VAMPYR-1 Experiments by PLAIN Code, Japan Atomic Energy Research Institute (JAERI), 1993. JAERI-M 93-097.
  22. K. Sawa, O. Baba, The Verification of Fission Products Plate-Out Analysis Code for HTGR, PLAIN, Japan Atomic Energy Research Institute (JAERI), 1991. JAERIM 91-084.