Accurate simulation of transient system behavior of a nuclear power plant is the goal of systems code calculations, and evaluation of a code's calculation accuracy is accomplished by assessment and validation against appropriate system data. These system data may be either from a running system prototype or scaled model test facility, and are comprised of the relevant phenomena during both steady state and transient conditions. The identification and characterization of the relevant data, and the assessment and validation of thermal hydraulic systems codes, has been the objective of multiple international research programs. The validation and assessment of the TRACE systems code against the Multi-Application Small Light-Water Reactor (MASLWR) natural circulation, helical coil steam generator, nuclear steam supply system (NSSS) design is a novel effort, and is the topic of the present paper. Specifically, the current work relates to the assessment and validation process of the system thermal-hydraulic TRACE code against the natural circulation database developed in the OSU-MASLWR test facility. This facility was constructed at Oregon State University under a Department of Energy grant in order to examine the natural circulation phenomena of importance to the MASLWR reactor design, which includes an integrated helical coil steam generator. This paper illustrates a preliminary sensitivity analysis to evaluate the fidelity of various methods to model the OSU-MASLWR steam generator in TRACE. The results of these analyses show that oscillations observed in a previous study by Mascari (2008) are related to the particular steam generator nodalization used. The SNAP animation model capability is used to show a direct visualization of selected calculated data.

Sensitivity analysis of the MASLWR helical coil steam generator using TRACE

D'AURIA, FRANCESCO SAVERIO
2009-01-01

Abstract

Accurate simulation of transient system behavior of a nuclear power plant is the goal of systems code calculations, and evaluation of a code's calculation accuracy is accomplished by assessment and validation against appropriate system data. These system data may be either from a running system prototype or scaled model test facility, and are comprised of the relevant phenomena during both steady state and transient conditions. The identification and characterization of the relevant data, and the assessment and validation of thermal hydraulic systems codes, has been the objective of multiple international research programs. The validation and assessment of the TRACE systems code against the Multi-Application Small Light-Water Reactor (MASLWR) natural circulation, helical coil steam generator, nuclear steam supply system (NSSS) design is a novel effort, and is the topic of the present paper. Specifically, the current work relates to the assessment and validation process of the system thermal-hydraulic TRACE code against the natural circulation database developed in the OSU-MASLWR test facility. This facility was constructed at Oregon State University under a Department of Energy grant in order to examine the natural circulation phenomena of importance to the MASLWR reactor design, which includes an integrated helical coil steam generator. This paper illustrates a preliminary sensitivity analysis to evaluate the fidelity of various methods to model the OSU-MASLWR steam generator in TRACE. The results of these analyses show that oscillations observed in a previous study by Mascari (2008) are related to the particular steam generator nodalization used. The SNAP animation model capability is used to show a direct visualization of selected calculated data.
2009
9789616207300
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11568/129836
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