Journal ArticleDOI
Reliability of Core Exit Thermocouple for Accident Management Action during SBLOCA and Abnormal Transient Tests at ROSA/LSTF
Mitsuhiro Suzuki,Hideo Nakamura +1 more
TLDR
In this paper, experimental results on the general performances of core exit thermocouples (CETs) to detect core overheat for accident management (AM) action by using the Large Scale Test Facility (LSTF) of the ROSA Program of the Japan Atomic Energy Agency.Abstract:
Presented are experimental results on the general performances of core exit thermocouples (CETs) to detect core overheat for accident management (AM) action by using the Large-Scale Test Facility (LSTF) of the ROSA Program of the Japan Atomic Energy Agency. The LSTF is a full-height, full-pressure, and 1/48-volumetric-scaled model of a 4-loop pressurized water reactor (PWR). This study was motivated by a significant delay in the time and temperature rise of the CETs from core heat-up during a vessel top head small break loss-of-coolant accident (SBLOCA) test. A certain delay in time and temperature rise of the CETs was also observed in various SBLOCA and abnormal transient tests. Such CET performances are derived from thirteen LSTF tests as follows: (1) general CET performances are obtained in the form of equations including cases under limited influences of water fall-back from hot legs, (2) the major reason for the delay is the interaction of three-dimensional steam flows with low-temperature structures...read more
Citations
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Core Exit Temperature Effectiveness in Accident Management of Nuclear Power Reactor
I. Toth,R. Prior,O. Sandervag,K. Umminger,Hideo Nakamura,N. Muellner,M. Cherubini,A. Del Nevo,F. D'Auria,J. Dreier,J. R. Alonso,A. Amri +11 more
A Study on ROSA/LSTF SB-CL-09 test simulating PWR 10% cold leg break LOCA; Loop-seal clearing and 3D core heat-up phenomena
TL;DR: In this article, the authors present major results observed in LOCA test (SB-CL-09) conducted at the ROSA/LSTF test facility simulating 10% cold leg break in a 4-loop Westinghouse-type PWR.
Journal ArticleDOI
Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled-Up Model
TL;DR: In this paper, the authors are grateful to the Management Board of the OECD-NEA ROSA Project for their findings produced within this project, which is partially supported by the Grant-in-Aid for Scientific Research of the Spanish Ministerio de Educacion (Grant number: AP2009-2600), the Spanish Ministers of Ciencia e Innovacion under Projects ENE2011-22823 and ENE2012-34585, and the Generalitat Valenciana under Projects PROMETEOII/2014/008 and ACOMP/2013/237.
Journal ArticleDOI
A review of the assessment of severe accident management guidelines and actions through analytical simulations
TL;DR: The generic severe accident management guidelines (SAMG) were developed as a response to TMI-2 accident to improve the defense-in-depth (DiD) concept of light water reactors (LWRs) as discussed by the authors .
References
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ROSA-V large scale test facility (LSTF) system description for the third and fourth simulated fuel assemblies
TL;DR: The Large Scale Test Facility (LSTF) is a full-height and 1/48 volumetrically scaled test facility of the Japan Atomic Energy Research Institute (JAERI) for system integral experiments simulating the thermal-hydraulic responses at full-pressure conditions of a 1100 MWe-class pressurized water reactor (PWR) during small break loss-of-coolant accidents (SBLOCAs) and other transients as mentioned in this paper.
Detection of inadequate core cooling with core exit thermocouples: LOFT PWR experience
J.P. Adams,G.E. McCreery +1 more
TL;DR: In this article, results from four previously reported loss-of-coolant accident simulations in the Loss of Fluid Test Facility at the Idaho National Engineering Laboratory are analyzed to determine the response of the core exit thermocouples to core cladding heatup resulting from core uncovery.
Journal ArticleDOI
Post-implementation review of inadequate core cooling instrumentation
TL;DR: In this article, a review of reactor coolant inventory tracking systems (RCITS) is presented, and attention is given to operating experience, accuracy, and procedures for the detection of inadequate core cooling.
Instrument accuracy in reactor vessel inventory tracking systems
TL;DR: The NRC Regulatory Guide 1.97, which covers accident monitoring instrumentation, was revised (Rev. 3) to be consistent with the requirements of item II.2 of NUREG-0737.
Proceedings ArticleDOI
Performance of Core Exit Thermocouple for PWR Accident Management Action in Vessel Top Break LOCA Simulation Experiment at OECD/NEA ROSA Project
TL;DR: In this paper, the results of the Large Scale Test Facility (LSTF) conducted at the Japan Atomic Energy Agency (JAEA) with a focus on core exit thermocouple (CET) performance to detect core overheat during a vessel top break loss-of-coolant accident (LOCA) simulation experiment are presented.