[KSCI] Korea Science Citation Index Service

http://dx.doi.org/10.5516/NET.2010.42.4.394

KEY IMPACT PARAMETERS FOR APPLICATION OF ALTERNATIVE SOURCE TERM TO KORI UNIT 1

Lee, Seung-Chan (KOREA HYDRO & NUCLEAR POWER Co., Nuclear Engineering & Technology Institute)

Publication Information

Nuclear Engineering and Technology / v.42, no.4, 2010 , pp. 394-413 More about this Journal

Abstract

The object of this paper is to identify the key elements that impact a radiation dose at EAB (Exclusion Area Boundary). This study is based on the AST (Alternative Source Terms) as defined in Regulatory Guide 1.183. The LOCA (Loss of Coolant Accident) and the LRA (Locked Rotor Accident) are selected as limiting cases. A sensitivity analysis of accidental behavior with respect to various parameters during LOCA and LRA at Kori Unit 1 is also undertaken for the following objectives: to determine the limiting parameters, to find the impact trend of the radiation dose, and to find the safety margin between AST and TID (Technical Information Document) methodologies. This work confirms that key parameters are particulate removal rate, decontamination factor, iodine chemical form, gap fraction, partitioning factor, and the impact of isotopes group. Comparing TID with AST, the radiation dose of TID is about 80% greater than that of AST under a LOCA, and about 60% greater than that of AST for the case of a LRA; thus the safety margin is remarkably increased when the AST is used. In this work, the sensitivity analysis results are presented in terms of a sensitivity index called the "NDD (Normalized Dose Difference)", which compares the impact of parameters with that of a reference case. These values are derived by using a combination of the leak rate (primary to secondary), iodine chemical form, gap fraction, partitioning factor, spray removal rate, source term, and other variables.

Keywords

TID-14844; AST; NUREG-1465; Kori Unit1; LRA; LOCA;

Citations & Related Records

Times Cited By Web Of Science : 0 (Related Records In Web of Science)
Times Cited By SCOPUS : 0

Reference

1	American Nuclear Society, “American National Standard Radioactive Source Term for Normal Operation of Light Water Reactors”, ANS/ANSI-18.1-1999, (1999).
2	U.S. Federal Guidance Report No. 11 & No. 12.(1988-1993).
3	USNRC, “Assumptions Used for Evaluating the Potential Radiological Consequences,” Regulatory Guide 1.4, Revision 2, (June 1974).
4	USNRC, “Results of the Revised (NUREG-1465) Source Term Rebaselining for Operating Reactors,” SECY-98-154, (June 30, 1998).
5	USNRC, “A Simplified Model of Aerosol Removal by Containment Sprays,” NUREG/CR-5966,( March 1993).
6	USNRC, “A Simplified Model of Aerosol Removal by Natural Processes in Reactor Containments,” NUREG/CR-6189, (March 1993).
7	USNRC, “Assumptions Used for Evaluating the Potential Radiological Consequences,” Regulatory Guide 1.25, (March 1972).
8	William H., Teukolsky, Saul A., Vetterling, William T., Flannery, Brain P., Numerical Receipes in C, Cambridge University Press (1992).
9	U.S. Atomic Energy Commission (now USNRC), Technical Information Document-14844, “Calculation of Distance Factors for Power and Test Reactor Sites”, NRC’s Public Electronic Reading Room, Accession number 8202010067, (1962).
10	US. NRC, “Alternative Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors”, Regulatory Guide 1.183, (July 2000).
11	USNRC, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,” NUREG-0800, (September 1981).
12	Final Safety Analysis Report at Kori Unit 1 (revision in 2007).
13	Calculation DRE02-0036, “Re-analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms”, Dresden Unit 2&3,(August 13, 2005).
14	Porcheron, E., Lemaitre, P., Nuboer, V., Vendel, J., “Experimental investigation in the TOSOQAN facility of heat and mass transfers in a spray for containment application”, Nuclear Engineering and Design, vol. 237, pp.1862 - 1871 (2007). DOI
15	Rimberg, D., Peng, Y., “Aerosol collection by Falling Droplet”, Air Pollution Control and Design Hand book, (New York, 1977).
16	USNRC, “RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation”, NUREG/CR-6604(April, 1998), Supplements 1(June 1999) and 2(October, 2002).