• Received : 2014.09.11
  • Accepted : 2014.12.09
  • Published : 2014.12.30


The object of this paper is to evaluate the fission product inventories and radiological doses in a non-LOCA event, based on the U.S. NRC's regulatory methodologies recommended by the TID-14844 and the RG 1.195. For choosing a non-LOCA event, one fuel assembly was assumed to be melted by a channel blockage accident. The Hanul nuclear power reactor unit 6 and the CE $16{\times}16$ fuel assembly were selected as the computational models. The burnup cross section library for depletion calculations was produced using the TRITON module in the SCALE6.1 computer code system. Based on the recently licensed values for fuel enrichment and burnup, the source term calculation was performed using the ORIGEN-ARP module. The fission product inventories released into the environment were obtained with the assumptions of the TID-14844 and the RG 1.195. With two kinds of source terms, the radiological doses of public in normal environment reflecting realistic circumstances were evaluated by applying the average condition of meteorology, inhalation rate, and shielding factor. The statistical analysis was first carried out using consecutive three year-meteorological data measured at the Hanul site. The annual-averaged atmospheric dispersion factors were evaluated at the shortest representative distance of 1,000 m, where the residents are actually able to live from the reactor core, according to the methodology recommended by the RG 1.111. The Korean characteristic-inhalation rate and shielding factor of a building were considered for a series of dose calculations.


  1. DiNunno JJ, Baker RE, Anderson FD, et al. Calculation of distance factors for power and test reactor sites, U.S. AEC, Technical Information Document-14844. 1962.
  2. U.S. Nuclear Regulatory Commission. Methods and assumptions for evaluating radiological consequences of design basis accidents at light water nuclear power reactors. U. S. NRC, Regulatory Guide 1.195. 2003.
  3. Burns EM. Next generation nuclear plant - Emergency planning zone definition at 400 meters. Westinghouse Electric Company, NGNP-LIC-GENRPT-L-00020. 2009.
  4. U.S. Nuclear Regulatory Commission. Alternative radiological source terms for evaluating design basis accidents at nuclear power reactors. U. S. NRC, Regulatory Guide 1.183. 2000.
  5. Croff AG. A user's manual for the ORIGEN2 computer code. ORNL, ORNL/TM-7175. 1980.
  6. Bowman SM, Leal LC. SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. U.S. NRC, NUREG/CR-0200. 2000.
  7. Kim HJ, Jung DW, Lee KH. The nuclear design report for Ulchin nuclear power plant unit 6 cycle 5. KNFC, KNF-U6C5-10007. 2010.
  8. SCALE Version 6.1, ORNL/TM-2005/39, Avalilabe from RSICC at ORNL as CCC-785. 2011.
  9. International Commission on Radiological Protection. 1990 Recommendations of the international commission on radiological protection. ICRP Publication 60. Oxford; Pergamon Press. 1991.
  10. Sagendorf JF, Goll JT, Sandusky WF. XOQDOQ:Computer program for the methorological evaluation of routine effluent releases at nuclear power stations. U.S. NRC, NUREG/CR-2919. 1982.
  11. U.S. Nuclear Regulatory Commission. Methods for estimating atmospheric transport and dispersion of gaseous effluents in routine releases from light-water-cooled reactors. U.S. NRC, Regulatory Guide 1.111. 1977.
  12. Korea Atomic Energy Research Institute. Evaluation of environmental assessment and model development in Kori site. KAERI, KAERI/NSC-397/89. 1989.
  13. Jeong HS, Kim EH, Jeong HJ, et al. Monte carlo radiation shielding evaluation for representative domestic houses. KAERI, KAERI/TR-5417/2013. 2013.