Reanalysis of environmental qualification radiation parameters for Kuosheng nuclear power plant
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Y.-P. Lin
Abstract
Kuosheng BWR-6 plant, owned by Taiwan Power Company, is currently operating at core thermal power of 2 971 MWt. The purpose of this study is to develop a method used to calculate the radiation dose at the reactor auxiliary building and at various rooms accommodating safety-related equipment during the design basis Loss of Coolant Accident (LOCA). The method integrates various aspects, including core inventory calculation using ORIGEN2 code, radioactive material transport and removal calculation using RADTRAD code, activity release calculation based on Technical Specification leakage limit and RADTRAD output, atmospheric dispersion calculation using ARCON96 code, and dose calculation using gamma energy and spectrum based finite cloud model. The assumptions used are based on the Regulatory Guide 1.89 revision 1. The calculation shows that the original Environmental Qualification(EQ) radiation parameters defined in the FASR, for the safety-related electrical and instrumental control equipment in the reactor auxiliary building, can be relaxed significantly and the radiation environment during accident could be reclassified, from “harsh environment” to “mild environment”.
Kurzfassung
Die BWR-6-Anlage Kuosheng, die sich im Besitz der Taiwan Power Company befindet, wird derzeit mit einer thermischen Kernleistung von 2 971 MWt betrieben. Ziel dieser Studie ist es, ein Verfahren zur Berechnung der Strahlendosis am Reaktorhilfsgebäude und an verschiedenen Räumen mit sicherheitsrelevanten Einrichtungen während des Auslegungsereignisses Kühlmittelverlustunfall (LOCA) zu entwickeln. Das Verfahren integriert verschiedene Aspekte, darunter die Berechnung des Kernbestands mit ORIGEN2-Code, die Berechnung des Transports und der Entfernung radioaktiver Stoffe mit dem RADTRAD-Code, die Berechnung der Aktivitätsfreisetzung mit Hilfe der Leckgrenze der Technischen Spezifikation und der RADTRAD-Ausgabe, die Berechnung der atmosphärischen Ausbreitung mit dem ARCON96-Code und die Dosisberechnung mit dem Gamma-Energie- und spektrenbasierten Finite-Cloud-Modell. Die verwendeten Annahmen basieren auf dem Regulatory Guide 1.89 Revision 1. Die Berechnung zeigt, dass die im FASR definierten ursprünglichen Strahlungsparameter der Umweltqualifikation (EQ) für die sicherheitsrelevanten elektrischen und instrumentellen Steuergeräte im Reaktorhilfsgebäude deutlich entspannt werden können und die Strahlungsumgebung während des Unfalls von “rauer Umgebung“ in “milder Umgebung“ umklassifiziert werden kann.
References
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© 2019, Carl Hanser Verlag, München
Artikel in diesem Heft
- 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
Artikel in diesem Heft
- 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
