Experimental Study for Two Phase Flow Instability in the PCHE Type Steam Generator in SMR
Creators
- 1. Korea Advanced Institute of Science and Technology, Department of Quantum and Nuclear Engineering, Guseong-dong, Yuseong-gu, 373-1, Daejeon 305-701 (Korea, Republic of)
Description
Conventional U-tube type heat exchangers have some limitations when applied to Small Modular Reactor (SMRs). In particular, the size of steam generators is important in the SMR, as it greatly affects the size, and thus the cost, of the reactor vessel.. Therefore, the circuit heat exchanger (PCHE) is suggested as an alternative. PCHE, a compact type heat exchanger manufactured by HEATRIC, has several advantages such as the reduced size, wide operation range until 900? and 900 bar and high power density due to the large heat transfer area over volume ratio. Recently, it is newly suggested as an application of a steam generator. MIT and KAIST have already conceptually suggested PCHE as a steam generator. Under boiling condition, flow instability is one of the critical issues-resulting in unstable mass flow rate, sudden temperature change and system control failure. According to the flow mechanism, there are various types of instabilities in the heat exchanger and each flow tendency is different. Typical examples are Ledinegg instability of the static instability and pressure-drop oscillation and density-wave oscillation of the dynamic instability. The characteristic of Ledinegg instability is that the flow under unstable condition changes into the stable flow. The characteristic of dynamic instability is that the flow fluctuates continuously. Pressure-drop oscillation has the period of tens of seconds and the system pressure also highly oscillates with the period of flow instability. In comparison, the density-wave oscillation has the period of few seconds and the system pressure is relatively stable. Previous studies on flow instability are focused on the single channel flow and helical tube type heat exchanger. There has been very limited experimental research on flow instability using PCHE. In KAIST, the test facility was constructed to study the thermal hydraulics in PCHE. The objectives of our test facility are: (1) to identify the occurrence of instability under two phase and super-heated steam flow in PCHE, and (2) to examine whether it can operate normally using throttling effect. (authors)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 115
- Journal Page Range
- p. 1719-1720
- ISSN
- 0003-018X
Conference
- Title
- 2016 ANS Winter Meeting and Nuclear Technology Expo
- Dates
- 6-10 Nov 2016
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52083312
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOILING; DENSITY; FLOW RATE; HEAT EXCHANGERS; HEAT TRANSFER; INSTABILITY; OSCILLATIONS; POWER DENSITY; PRESSURE DROP; REACTOR OPERATION; REACTOR VESSELS; SMALL MODULAR REACTORS; STEAM GENERATORS; TEST FACILITIES; THERMAL HYDRAULICS; TWO-PHASE FLOW
- Descriptors DEC
- BOILERS; CONTAINERS; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MECHANICS; OPERATION; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; REACTOR LIFE CYCLE; REACTORS; VAPOR GENERATORS
Optional Information
- Notes
- 5 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)