ANALYSIS OF DVI LINE BREAK IN ATLAS TEST FACILITY USING RELAP5 CODE
Main Article Content
Abstract
The ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) is an integral effect test for simulating APR1400 reactor in a wide range of accident conditions. Most of the safety injection features of the APR1400 are incorporated into the safety injection system of the ATLAS. It is a half-height and 1/288-volume scaled test facility with respect to the APR1400 included a primary system, a secondary system, a safety injection system, a break simulating system, a containment simulating system, and auxiliary systems. The DVI line break test of the APR1400 was done on ATLAS with the same pressure and temperature conditions and was chosen as the first domestic standard problem of Korean Nuclear Industry. The calculations presented in the paper have been carried out with the RELAP5 code. The calculation was run for the steady state already supplied in DSP-1 and then, the transient calculations for DVI break were performed for the time period of 2000 seconds. The main calculation results are in good agreement with experiment data and results reported by KAERI, KINS and KNF.
Article Details
Keywords
APR1400, Direct Vessel Injection, Downcomer, Safety Injection pump, Integral Effect Test, Peak Cladding Temperature
References
[2] Ki-Yong Choi, Hyun-Sik Park at al., “Experimental Simulation of A Direct Vessel Injection Line Break of The APR1400 with The ATLAS”, Nucl. Eng. and Tech., Vol.41. No.5 June 2009.
[3] K. D. Kim, “ALTAS DSP-1 Lecture (100% DVI Line Break)”, ALTAS DSP-1 Lecture for VAEI, KAERI, July 9, 2010.
[4] Yeon-Sik Kim , Ki-Yong Choi et al. “Commissioning of the ATLAS thermal-hydraulic integral test facility”, Annals of Nuclear Energy 35 (2008) 1791–1799.
[4] “ATLAS Domestic Standard Problem (DSP) Specifications” , KAERI , July 2009.
[5] Won-Pil Baek, Yeon-sik Kim and Ki-Yong Choi. “ LBLOCA and DVI Line Break Tests with tha ATLAS Integral Facility” Nuclear Engineering and Technology, Vol.41. No.6 August 2009.
[6] 2. The Relap5 Development Team, “RELAP5/MOD3.3 Code Manual”, NUREG/CR-5535, Rev1, vols. 1-8, Idaho National Engineering Laboratory, January 2002.