Overview of separate effect and integral system tests on the passive containment cooling system of SMART100
1
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
SMART100 has a containment pressure and radioactivity suppression system (CPRSS) for passive containment cooling system (PCCS). This prevents overheating and over-pressurization of a containment through direct contact condensation in an in-containment refueling water storage tank (IRWST) and wall condensation in a CPRSS heat exchanger (CHX) in an emergency cool-down tank (ECT). The Korea Atomic Energy Research Institute (KAERI) constructed scaled-down test facilities, SISTA1 and SISTA2, for the thermal-hydraulic validation of the SMART100 CPRSS. Three separate effect tests were performed using SISTA1 to confirm the heat removal characteristics of SMART100 CPRSS. When the low mass flux steam with or without non-condensable gas is released into an IRWST, the conditions for mitigation of the chugging phenomenon were identified, and the physical variables were quantified by the 3D reconstruction method. The local behavior of the noncondensable gas was measured after condensation inside heat exchanger using a traverse system. Stratification of non-condensable gas occurred in large tank of the natural circulation loop. SISTA2 was used to simulate a small break loss-of-coolant accident (SBLCOA) transient. Since the test apparatus was a metal tank, compensations of initial heat transfer to the material and effect of heat loss during long-term operation were important for simulating cooling performance of SMART100 CPRSS. The pressure of SMART100 CPRSS was maintained below the design limit for 3 days even under sufficiently conservative conditions of an SBLOCA transient.
Abstract
SMART100 has a containment pressure and radioactivity suppression system (CPRSS) for passive containment cooling system (PCCS). This prevents overheating and over-pressurization of a containment through direct contact condensation in an in-containment refueling water storage tank (IRWST) and wall condensation in a CPRSS heat exchanger (CHX) in an emergency cool-down tank (ECT). The Korea Atomic Energy Research Institute (KAERI) constructed scaled-down test facilities, SISTA1 and SISTA2, for the thermal-hydraulic validation of the SMART100 CPRSS. Three separate effect tests were performed using SISTA1 to confirm the heat removal characteristics of SMART100 CPRSS. When the low mass flux steam with or without non-condensable gas is released into an IRWST, the conditions for mitigation of the chugging phenomenon were identified, and the physical variables were quantified by the 3D reconstruction method. The local behavior of the noncondensable gas was measured after condensation inside heat exchanger using a traverse system. Stratification of non-condensable gas occurred in large tank of the natural circulation loop. SISTA2 was used to simulate a small break loss-of-coolant accident (SBLCOA) transient. Since the test apparatus was a metal tank, compensations of initial heat transfer to the material and effect of heat loss during long-term operation were important for simulating cooling performance of SMART100 CPRSS. The pressure of SMART100 CPRSS was maintained below the design limit for 3 days even under sufficiently conservative conditions of an SBLOCA transient.
참고문헌 (15)
- J. H. Yang, "Investigation of condensation with noncondensable gas in natural circulation loop for passive safety system", Nucl. Eng. Technol, 55, pp.1125~1139 (2023)
- Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants, "International Atomic Energy Agency", IAEA, ~, pp.IAEA-TECDOC-1624 (2006)
- J. H. Yang, "Experimental study on SBLOCA using fullheight CPRSS validation test facility", Transactions of the Korean Nuclear Society Autumn Mmeeting (2021)
- Similarity Analysis and Scaling Criteria for LWRs under Single-Phase and Two-phase Natural Circulation, "M. Ishii", ~, pp.NUREG (1983), CR-3267
- J.H. Yang, "3D bubble reconstruction method for direct contact condensation phenomena on Elbow Tip", The 9th China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-9) (2019)
- J.H. Yang, "Condensation experiments with noncondensable gas in closed loop using local measurement method", The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (2022)
- J. H. Yang, "Stratification of long-term cooling system using condensation heat exchanger", Trans. Korean Soc. Mech. Eng. B, 46(3), pp.127~132 (2022)
- T. -H. Ahn, "Quantification of the volume and interfacial area of 3D bubble for the direct contact condensation in IRWST", Transactions of the Korean Nuclear Society Autumn meeting (2019)
- C. K. Chan, "A regime map for direct contact condensation", Int J. Multiph. Flow, 8(1), pp.11~20 (1982)
- B. Qingchuan Yang, "Experimental investigation on the condensation regime and pressure oscillation characteristics of vertical upward steam jet condensation with low mass flux", Exp. Therm. Fluid Sci, 111, pp.109983~ (2020)
- Weichao Li, "Effect of non-condensable gas on pressure oscillation of submerged steam jet condensation in condensation oscillation regime", Int. J. Heat Mass Tran, 124, pp.141~149 (2018)
- C. Yang Xiaoping, "Experimental study on the direct contact condensation of the steam–air mixture in subcooled water flow in a rectangular channel", Int. J. Heat Mass Tran, 88, pp.424~432 (2015)
- Srinivasa Ramanujan, "Modular Equations and Approximations to π", Quart. J. Pure App. Math, 45, pp.350~372 (1914)
- D. H. Youn, "The direct contact condensation of steam in a pool at low mass flux", J. Nucl. Sci. Technol, 40(10), pp.881~885 (2003)
- MARS Code Manual Volume I: Code Structure, System Models, and Solution Methods, "Korea Atomic Energy Research Institute", KAERI, ~, pp.KAERI (2007), TR-2812[DOI]