Application of two alternative shutdown severe accident management guideline (SSAMG) entry conditions for CPR1000
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Z. Huang
, H. Miao , H. Hsieh , N. Li and D. Gu
Abstract
Recently, with the development and application of full-scope level 2 probabilistic safety assessment (PSA) method around the world, severe accident phenomena during shutdown and low power conditions have aroused extensive attention in nuclear industry. And the shutdown severe accident management guideline (SSAMG) is claimed to be developed, and the verification of the traditional and alternative entry conditions is the first consideration in this procedure. Thus in this paper, the feasibility of the hot leg pipe temperature and the modified jakob number are analyzed based on a SBO sequence firstly. Subsequently, verification work is conducted under a SBO sequence with pressurizer manhole open and a SBO sequence along with SBLOCA. The results proved the excellent effectiveness of the two parameters to be used as alternative SSAMG entry conditions. Also, a relational figure is constructed based on the results of diverse sequences with various primary system pressure to provide visualized guidance for operators. What's more, the value of modified jakob number which indicates the SSAMG entry is thought to be in the range of 0.5–1.
Kurzfassung
Einhergehend mit der Entwicklung und Anwendung der Full-Scope Level 2 Probabilistic Safety Assessment (PSA)-Methode werden weltweit Phänomene während schwerer Unfälle beim Abschalten und bei niedrigen Leistungszuständen untersucht. Gleichzeitig soll eine Richtlinie für das Management schwerer Störfälle während des Abschaltens entwickelt werden. Dabei steht die Überprüfung der traditionellen und alternativen Startbedingungen im Vordergrund. So werden in diesem Beitrag als alternative Eingangsbedingungen zunächst die Hotleg-Temperatur und die modifizierte Jakobzahl am Beispiel eines SBO-Störfall untersucht. Anschließend werden Verifikationsarbeiten zu einem SBO-Szenario mit geöffnetem Druckhaltermannloch sowie zu einem SBO-Szenario in Kombination mit einem SBLOCA durchgeführt. Die Ergebnisse zeigen die ausgezeichnete Wirksamkeit der beiden Parameter, die als alternative SSAMG-Eintrittsbedingungen verwendet werden sollen. Außerdem wird eine Beziehung basierend auf den Ergebnissen verschiedener Sequenzen mit unterschiedlichem primärem Systemdruck konstruiert, um eine visualisierte Führung für den Bediener zu ermöglichen.
References
1 IAEA: Severe accident management programmes for nuclear power plants. IAEA Safety Standards Series. (2009) NS-G-2.15Search in Google Scholar
2 Hermsmeyer, S.; Iglesias, R.: Herranz, L. E.; et al.: Review of current severe accident management (SAM) approaches for nuclear power plants in europe. 2014Search in Google Scholar
3 Vöröss, L.: Lessons learned from the INES-3 event at Paks NPP on April 10, 2003. Hungarian Atomic Energy Authority, 2003.Search in Google Scholar
4 Solovjanov, O.; Dessars, N.; Lutz, R.; et al.: Implementation of severe accident management guidelines to shutdown and low-power modes for VVER and PWR plants. Westinghouse Electric Belgium SA, 2010Search in Google Scholar
5 Yun, J.; Kim, T.; Kim, J.: Verification of SAMG entry condition for APR1400. Annals of Nuclear Energy75 (2015) 404–41210.1016/j.anucene.2014.08.057Search in Google Scholar
6 Choi, W.; Lee, Y.; Kim, S. J.; Kim, H.-Y.: Effectiveness of modified Jakob number as a SAMG entry condition of OPR1000. Proceedings of the KNS 2015 spring meeting, (pp. 1 CD-ROM), 2015Search in Google Scholar
7 Kumar, M.; Löffler, H., Morandi, S.; et al.: Complement of existing ASAMPSA2 guidance for shutdown states of reactors, spent fuel pool and recent R&D results. 2016Search in Google Scholar
8 EPRI: MAAP4 modular accident analysis program for LWR power plants user's Manual. 2005Search in Google Scholar
9 Zuber, N.: The dynamics of vapor bubbles in nonuniform temperature fields. International Journal of Heat and Mass Transfer2 (1961) 83–9810.1016/0017-9310(61)90016-3Search in Google Scholar
© 2019, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- New research reactor protection system
- Ultimate response guideline strategy evaluation for Maanshan power plant
- Application of two alternative shutdown severe accident management guideline (SSAMG) entry conditions for CPR1000
- Simulation and analysis of the Loss of Flow Accident (LOFA) scenarios for an open pool type research reactor by using the RELAP5/MOD3.2 code
- Numerical study on cut-off diameter of aerosol particle for filtered containment venting system in nuclear power plant
- Reanalysis of environmental qualification radiation parameters for Kuosheng nuclear power plant
- Effect of reactor operator intervention during unprotected LOFA in a typical MTR
Articles in the same Issue
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- New research reactor protection system
- Ultimate response guideline strategy evaluation for Maanshan power plant
- Application of two alternative shutdown severe accident management guideline (SSAMG) entry conditions for CPR1000
- Simulation and analysis of the Loss of Flow Accident (LOFA) scenarios for an open pool type research reactor by using the RELAP5/MOD3.2 code
- Numerical study on cut-off diameter of aerosol particle for filtered containment venting system in nuclear power plant
- Reanalysis of environmental qualification radiation parameters for Kuosheng nuclear power plant
- Effect of reactor operator intervention during unprotected LOFA in a typical MTR