OSU MASLWR integral test facility, owned and operated at Oregon State University, represents a SMR cooled and moderated by light water. The main features of the experimental facility are based on the preliminary design of the Multi-Application Small Light Water Reactor carried out at Idaho National Labs. This reactor relies on natural circulation and on passive and inherently safe engineering safety features. It is featured by a helical-coil steam generator. The primary system and the containment are inherently coupled, in some anticipated operation occurrences and postulated accident conditions. Reliable simulations of such system requires the demonstration that a thermal-hydraulic system code, such as RELAP5 in this paper, can predict or, at least, bound some phenomena, which are outside its standard area of application. Challenging phenomena for the code simulation are: heat exchange for helical-coil SG and two phase instabilities in parallel tubes (SG secondary side); mixing and thermal stratification in a pool system; the condensation on the free surface in presence of noncodensable gas; chocked flow, the coupling primary system and containment. This paper presents also the performance of RELAP5 code in simulating the heat transfer in tube bundle with crossflow and the validation performed using two experiments performed in OSU MASLWR integral test facility. They are: 1) a natural circulation experiment aimed at characterizing the system performances at different power levels, and 2) a total loss of feedwater flow postulated accident scenario. The activity has been performed in the framework of an International Collaborative Standard Problem under the auspices of the IAEA.

Modeling the Heat Transfer of Helical Coil Tubes Steam Generator in SMR by RELAP5 Code and Validation

FORGIONE, NICOLA
2013-01-01

Abstract

OSU MASLWR integral test facility, owned and operated at Oregon State University, represents a SMR cooled and moderated by light water. The main features of the experimental facility are based on the preliminary design of the Multi-Application Small Light Water Reactor carried out at Idaho National Labs. This reactor relies on natural circulation and on passive and inherently safe engineering safety features. It is featured by a helical-coil steam generator. The primary system and the containment are inherently coupled, in some anticipated operation occurrences and postulated accident conditions. Reliable simulations of such system requires the demonstration that a thermal-hydraulic system code, such as RELAP5 in this paper, can predict or, at least, bound some phenomena, which are outside its standard area of application. Challenging phenomena for the code simulation are: heat exchange for helical-coil SG and two phase instabilities in parallel tubes (SG secondary side); mixing and thermal stratification in a pool system; the condensation on the free surface in presence of noncodensable gas; chocked flow, the coupling primary system and containment. This paper presents also the performance of RELAP5 code in simulating the heat transfer in tube bundle with crossflow and the validation performed using two experiments performed in OSU MASLWR integral test facility. They are: 1) a natural circulation experiment aimed at characterizing the system performances at different power levels, and 2) a total loss of feedwater flow postulated accident scenario. The activity has been performed in the framework of an International Collaborative Standard Problem under the auspices of the IAEA.
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11568/426267
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