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Technical Paper

Development of the Fission Product Release Analysis Code COPA-FPREL

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Pages 231-243 | Published online: 13 May 2017

References

  • L. YUANZHONG and C. JIANZHU, “Fission Product Release and Its Environment Impact for Normal Reactor Operations and for Relevant Accidents,” Nucl. Eng. Des., 218, 81 (2002).
  • “Fuel Performance and Fission Product Behaviour in Gas Cooled Reactors,” IAEA-TECDOC-978, International Atomic Energy Agency (1997).
  • N. INIOTAKIS, J. MALINOWSKI, and K. MÜNCHOW, “Initial Results of Investigations into Fission Product Deposition in In-Pile Experiments,” Nucl. Eng. Des., 34, 169 (1975).
  • W. KATSCHER, R. MOORMANN, K. VERFONDERN, C. B. v. d. DECKEN, N. INIOTAKIS, and K. HILPERT, “Fission Product Behaviour and Graphite Corrosion Under Accident Conditions in the HTR,” Nucl. Eng. Des., 121, 219 (1990).
  • Y. M. KIM, M. S. CHO, Y. W. LEE, and W. J. LEE, “Development of a Fuel Performance Analysis Code COPA,” Proc. 4th Int. Topl. Mtg. High Temperature Reactor Technology (HTR-2008), Washington D.C., September 28–October 1, 2008.
  • J. H. PARK, D. H. KIM, and W. J. LEE, “The Scope Calculation for the Distribution of the Plateout in the ‘OGL-1’ Experiment Using MIDAS and Its Model Review,” Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 10–11, 2007.
  • J. CHANG, Y. W. KIM, K. Y. LEE, Y. W. LEE, W. J. LEE, J. M. NOH, M. H. KIM, H. S. LIM, Y. J. SHIN, K. K. BAE, and K. D. JUNG, “A Study of a Nuclear Hydrogen Production Demonstration Plant,” Nucl. Eng. Technol., 39, 2, 111 (2007).
  • H. KROHN and R. FINKEN, “FRESCO-II: Ein Rechenprogramm zur Berechnung der Spaltproduktfreisetzung aus kugelformigen HTR-Brennelementen in Bestrahlungsund Ausheizexperimenten,” Jül-Spez-212, Kernforschungsanlage Jülich (1983).
  • B. F. MYERS and W. E. BELL, “Cesium Transport Data for HTGR Systems,” GA-A13990, General Atomic Company (1979).
  • J. APPEL and B. ROOS, “A Study of the Release of Radioactive Metallic Isotopes from High-Temperature Gas-Cooled Reactors,” Nucl. Sci. Eng., 34, 201 (1968).
  • P. D. SMITH, “TRAFIC, A Computer Program for Calculating the Release of Metallic Fission Products from an HTGR Core,” GA-A14721, General Atomic Company (1978).
  • S. NAKAMURA, Computational Methods in Engineering and Science, John Wiley & Sons, New York (1977).
  • R. C. MARTIN, “Compilation of Fuel Performance and Fission Product Transport Models and Database for MHTGR Design,” ORNL/NPR-91/6, Oak Ridge National Laboratory (1993).
  • J. KESHAW and H. MERWE, “GETTER—A Model for Fission Product Release from Spherical HTR Fuel Elements,” Proc. 3rd Int. Topl. Mtg. High Temperature Reactor Technology (HTR 2006), Johannesburg, South Africa, 2006.
  • W. W. HUDRITSCH and P. D. SMITH, “PADLOC, A One-Dimensional Computer Program for Calculating Coolant and Plateout Fission Product Concentrations,” GA-A14401, General Atomic Company (1977).
  • “SCDAP/RELAP5/MOD3.1 Code Manual Volume IV: MATPRO—ALibrary of Materials Properties for Light-Water-Reactor Accident Analysis,” NUREG/CR-6150, D. T. HAGRMAN, Ed., U.S. Nuclear Regulatory Commission (1993).
  • “Development of Improved Models and Designs for Coated-Particle Gas Reactor Fuels,” INEEL/EXT-05-02615, Idaho National Environmental and Engineering Laboratory (2004).
  • M. J. KANIA and H. NICKEL, “Performance Assessment of the (Th,U)O2 HTI-BISO Coated Particle Under PNP/HHT Irradiation Conditions,” Jül-1685, Kernforschungsanlage Jülich (1980).
  • R. J. PRICE, “Review of the Thermal Conductivity of Nuclear Graphite Under HTGR Conditions,” Gulf-GA-A12615, Gulf General Atomic Company (1973).
  • Geschäftsstelle des Kerntechnischen Ausschusses beim Bundesamt für Strahlenschutz, “Auslegung der Reaktorkerne von gasgekühlten Hochtemperaturreaktoren.Teil 2: Wärmeübergang im Kugelhaufen,” KTA 3102.2, Republic of Germany Nuclear Safety Standards Commission (KTA) (1983).
  • D. M. McELIGOT, G. E. McCREERY, R. R. SCHULTZ, J. LEE, P. HEJZLAR, P. STAHLE, and P. SAHA, “Investigation of Fundamental Thermal-Hydraulic Phenomena in Advanced Gas-Cooled Reactors,” INL/EXT-06-11801, Idaho National Laboratory (2006).
  • T. KIKUCHI, K. IWAMOTO, K. IKAWA, and K. ISHIMOTO, “Experimental Determination of Thermal Conductivity and Gap Conductance of Fuel Rod for HTGR,” JAERI-M 84-236, Japan Atomic Energy Research Institute (1985).
  • Geschäftsstelle des Kerntechnischen Ausschusses beim Bundesamt für Strahlenschutz, “Auslegung der Reaktorkerne von gasgekühlten Hochtemperaturreaktoren. Teil 1: Berechnung der Helium-Stoffwerte,” KTA 3102.1, Republic of Germany Nuclear Safety Standards Commission (KTA) (1978).
  • T. R. ENGLAND and B. F. RIDER, “Evaluation and Compilation of Fission Product Yields,” LA-SUB-94-170, Los Alamos National Laboratory (1995).
  • F. GELBARD, “Analytical Modeling of Fission Product Releases by Diffusion from Multicoated Fuel Particles,” SAND2002-3966, Sandia National Laboratories (2003).
  • K. VERFONDERN and H. NABIELEK, “Fission Product Release from HTGR Fuel Under Core Heatup Accident Conditions,” Proc. 4th Int. Topl. Mtg. High Temperature Reactor Technology (HTR-2008), Washington, D.C., September 28–October 1, 2008.
  • K. VERFONDERN and Y. W. LEE, “Advances in HTGR Fuel Technology—A New IAEA Coordinated Research Program,” Proc. Int. Congress Advances in Nuclear Power Plants (ICAPP05), Seoul, Korea, May 15–19, 2005.
  • S. GROOT, V. BASINI, P. GUILLERMIER, K. BAKKER, K. SAWA, Y. W. LEE, J.-M. ESCLEINE, M. PEREZ, S. UETA, and B. G. KIM, “RAPHAEL-FT&Generation IV PYCASSO-I Irradiation,” Proc. 4th Int. Topl. Mtg. High Temperature Reactor Technology (HTR-2008), Washington, D.C., September 28–October 1, 2008.
  • Y. W. LEE, J. Y. PARK, Y. K. KIM, K. C. JEONG, W. K. KIM, B. G. KIM, Y. M. KIM, and M. S. CHO, “Development of HTGR-Coated Particle Fuel Technology in Korea,” Nucl. Eng. Des., 238, 2842 (2008).
  • M. STAN, “Multi-Scale Models and Simulations of Nuclear Fuels,” Nucl. Eng. Technol., 41, 1, 39 (2009).

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