A Sensitivity Study of a Steam Generator Tube Rupture for the SMART-P

SMART 연구로의 증기발생기 전열관 파열사고 민감도 분석

  • Published : 2005.06.01


The purpose of this study is for the sensitivity study f9r a Steam Generator Tube Rupture (SGTR) of the System-integrated Modular Advanced ReacTor for a Pilot (SMART-P) plant. The thermal hydraulic analysis of a SGIR for the Limiting Conditions for Operation (LCO) is performed using TASS/SMR code. The TASS/SMR code can calculate the core power, pressure, flow, temperature and other values of the primary and secondary system for the various initiating conditions. The major concern of this sensitivity study is not the minimum Critical Heat Flux Ratio(CHFR) but the maximum leakage amount from the primary to secondary sides at the steam generator. Therefore the break area causing the maximum accumulated break flow is researched for this reason. In the case of a SGIR for the SMART-p, the total integrated break flow is 11,740kg in the worst case scenario, the minimum CHFR is maintained at Over 1.3 and the hottest fuel rod temperature is below 606"I during the transient. It means that the integrity of the fuel rod is guaranteed. The reactor coolant system and the secondary system pressures are maintained below 18.7MPa, which is system design pressure.


SGTR;SMART-P;TASS/SMR;integrated break flow


  1. 10CFR50, 'Domestic Licensing of Production and Utilization Facilities', Title 10, Code of Federal Regulations, Part 50, Appendix A, 'General Design Criteria for Nuclear Power Plant', April, 1993
  2. 10CFR100, 'Reactor Site Criteria', Part 100, April, 1962
  3. 윤한영 외, 'TASS/SMR 열수력 모델 기술서', KAERI/TR-1835/2001
  4. Young-Jong Chung et al., 'A Conservative Analysis Methodology for a Steamline Break Accident of the SMART-P Plant', Nuclear Technology, will be published