Decay Heat - Predictions

  1. K. Oyamatsu, H. Takeuchi, M. Sagisaka and J. Katakura, "New Method for Calculating Aggregate Fission Product Decay Heat with Full Use of Macroscopic-Measurement Data", Journal of Nuclear Science and Technology, Vol. 38, No. 7, pp. 477-489. (July 2001).
  2. T. Yoshida, T. Tachibana, "Theoretical Treament of the Asymptotic Behaviour of Fission Product Decay Heat toward Very Short Cooling-Time", Journal of Nuclear Science and Technology, Vol. 37, No. 6, pp. 491-497. (June 2000).
  3. J. Karlsson, "DECAY HEAT REMOVAL BY NATURAL CONVECTION AND THERMAL RADIATION FROM THE REACTOR VESSEL" (ADS), Presented at ADTTA'99, Prague. Word- document available at the ADS homepage, under the "what's new" section. (June 1999).
  4. T. Yoshida, T. Tachibana, F. Storrer, K. Oyamatsu, J. Katakura, "Possible Origin of the Gamma-Ray Discrepancy in the Summation Calculations of Fission Product Decay Heat", Journal of Nuclear Science and Technology, Vol. 36, No. 2, pp. 135-142. (February 1999).
  5. NRC regulatory guide 3.54. "Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation", Revision 1, (January 1999).
  6. O.W. Hermann, P.R. Daniel, J.C. Ryman; "ORIGEN-S Decay Data Library and Half-Life Uncertainties"; ORNL/TM-13624; Oak Ridge Nat. Lab. (September 1998).
  7. K. Oyamatsu et al.; "Uncertainties in fission product decay heat calculations", Proc. Symposium on Nucl. Data, Tokai, Japan, JAERI-Conf 97-004, (1997)
  8. K. Oyamatsu et al.; "Comparison of Yield and Decay Data among JNDC-2, ENDF/B-VI and JEF2.2", Proc. Symposium on Nucl. Data, Tokai, Japan, JAERI-Conf 97-004, (1997)
  9. K. Oyamatsu et al.; "Two methods for evaluation and benchmark test of fission product summation calculations", Proc. Int. Conf. on Nucl. Dat. for Sci. And Tech., Trieste, Italy, (1997)
  10. K. Oyamatsu et al.; "Uncertainties in summation calculations of aggregate decay heat and delayed neutron emission with ENDF/B-VI", Proc. Int. Conf. on Nucl. Dat. for Sci. And Tech., Trieste, Italy, (1997)
  11. J.L. Kloosterman; "New European Cross-Section Data Libraries for ORIGEN-S Based on JEF2.2 and EAF3", Technical Report ECN-R-95-008, ECN, Petten, The Netherlands. (March 1995)
  12. O.W. Hermann, C.V. Parks, J.P. Renier; "Technical Support for a Proposed Decay Heat Guide Using SAS2H/ORIGEN-S Data", ORNL-6698, NUREG/CR-5625, Oak Ridge Natl. Lab., (September 1994).
  13. Proceedings of a Specialists' Meeting on Fission Product Nuclear Data Tokai, Japan 25th-27th May 1992. Organised by JAERI, JNDC and OECD NEA. (1992).
  14. J.K. Dickens, T.R. England, R.E. Schenter; "Current status and proposed improvements to the ANSI/ANS-5.1 American National Standard for decay heat power in Light Water Reactors", Nuclear Safety, 32, 209. (1992)
  15. J.K. Dickens,"Analysis of Beta-Ray Important to Decay Heat Predictions" Nuclear Science and Engineering, 109, 92-102. (1992)
  16. O.W. Hermann, C.V. Parks, J.P. Renier, "A Proposed Regulatory Guide Basis for Spent Fuel Decay Heat", Proc. of the Second Annual International Conference on High-Level Radioactive Waste Management, Las Vegas, NV, Vol. 2, pp. 1662-1669, (April 12-16, 1992)
  17. NEACRP/NEANDC Task Force Meeting on Decay Heat Predictions; NEA Data Bank, 21st and 22nd September 1989. (The 2nd meeting of the Task Force.) NEANDC-A-260. (1989).
  18. B. Duchemin, C. Nordborg, "DECAY HEAT CALCULATION; An International Nuclear Code Comparison". NEACRP-319-U, also NEANDC-275-U. (1989).
  19. C.Nordborg and B. Duchemin, "International Comparison Study of Codes used in Decay Heat Calculations". NEANDC-U-246, NEACRP-L-303 (incorporated as annex 1 in NEANDC-275/U). (1988).
  20. Summary Record of the First Meeting of the NEANDC/NEACRP Task Force on Decay Heat Predictions, London, U.K. 21st November 1988. NEA/NEANDC(1988)252/A. (1988)
  21. Proceedings of a Specialists' Meeting on Data for Decay Heat Predictions. Studsvik, Sweden, 7-10 September 1987, NEACRP-U-302, NEANDC-U-245, (1987).
  22. T. Yoshida, J. Katakura, "Calculation of the Delayed Gamma-Ray Energy Spectra from Aggregate Fission Product Nuclides", Nuclear Science and Engineering, 93, 193-203. (1986).
  23. First announcment of the NEACRP/NEANDC Specialists' Meeting on Experimental Data for Decay-Heat Predictions. NEA/NEANDC(1986)229/A. (1986)
  24. O.W. Hermann, C.V. Parks, J.C. Ryman, "Spent Fuel Decay Heat Calculations Using ORIGEN-S", Proc. of Third International Spent Fuel Storage Technology Symposium/Workshop, p. W-97 of CONF-860417, Vol 2, held in Seattle, WA. (April 8-10, 1986)
  25. J.C. Ryman, O.W. Hermann, C.C. Webster, C.V. Parks; "Fuel Inventory and Afterheat Power Studies of Uranium-Fueled Pressurized Water Reactor Fuel Assemblies Using the SAS2 and ORIGEN-S modules of Scale with an ENDF/B-V Updated Cross Section Library", NUREG/CR-2397, ORNL/CSD-90, Union Carbide Corp., Nuclear Division, (September 1982).
  26. J.C. Ryman, O.W. Hermann, C.C. Webster, V.V. Parks, "A Simplified Method for Predicting Afterheat Power From Urainum-Fueled PWR Fuel Assemblies", Proc. of the International Meeting on Thermal Nuclear Reactor Safety, Chicago, IL, (August 29-September 2, 1982)
  27. T. Yoshida, R. Nakasima, "Decay Heat Calculations Based on Theoretical Estimation of Average Beta- and Gamma-Energies Released from Short-Lived Fission Products", Journal of Nuclear Science and Technology, Vol. 18, No. 6, pp. 393-407, Also in NEACRP-L-253. (June 1981).
  28. F. Schmittroth, R.E. Schenter, "Application of Least-Squares Method to Decay Heat Evaluation", Nuclear Science and Engineering, 69, 389-397. (1979)
  29. T. Yoshida, "Estimation of Nuclear Decay Heat for Short-Lived Fission Products", Nuclear Science and Engineering, 63, 376-390. (1977).
  30. F. Schmittroth, "Uncertainty Analysis of Fission Product Decay Heat Summation Method", Nuclear Science and Engineering, 59, 117-139. (1976).
  31. R.E. Schenter, F. Schmittroth, "Radioaactive Decay Heat Analyses", Nuclear Cross Sections and Technology, Volume 1, Proceedings of a Conference, Washington, D.C., (March 3-7, 1975)

This page was created 2000-05-20 and updated 2006-01-25.