Published May 2017 | Version v1
Report

Filtered Containment Venting System for Existing Nuclear Power Plants: Design Parameters and Associated Safety Criteria in Belgium

  • 1. Bel V, Brussels (Belgium)

Description

Following the post-Fukushima stress tests performed in Belgium, Filtered Containment Venting Systems (FCVS) are foreseen to be installed on Belgian Nuclear Power Plants (NPPs) as ultimate means to cope with slow pressurization of the containment that could occur during potential Severe Accidents (SA). After an introduction about the Belgian context, information about the regulatory framework is provided, as well as the main objectives of the FCVS. Then, the main part of the paper discusses the methodology supporting the definition of the FCVS main design parameters and associated safety criteria developed by Tractebel Engineering, on behalf of the licensee Electrabel – GDF Suez, and validated by the Belgian nuclear Safety Authorities. This methodology followed a series of subsequent steps starting with the definition of the safety referential applicable to the FCVS and leading to the identification of a reference sequence, namely the Complete Station Blackout (CSBO). Then, key parameters for the FCVS design were defined (e.g. pressure range, venting flow, stored decay heat, stored mass, Decontamination Factors (DF)) along with the associated safety criteria. Several of these key parameters were assessed through a well-defined set of supporting calculations. This set included both best estimate representative cases as well as conservative bounding cases performed with the state of the art SA codes MELCOR 1.8.6 and, subsequently, ASTEC V2.0 (CPA/IODE modules), in a chaining methodology. The aim of this approach was to take advantage of the iodine chemistry models features in the CPA/IODE modules of ASTEC to calculate the iodine speciation in the containment and in the FCVS, without having to run a full scope ASTEC calculation. Finally, an overview of the assessment by the Belgian TSO, Bel V, as well as the follow-up actions and next steps are reported, with the aim to provide information about the current status of the actions and implementation of the requirements related to the FCVS. (author)

Part of:
Severe Accident Mitigation through Improvements in Filtered Containment Vent Systems and Containment Cooling Strategies for Water Cooled Reactors. Proceedings of a Technical Meeting

Additional details

Publishing Information

ISBN
978-92-0-153817-8
Imprint Title
Severe Accident Mitigation through Improvements in Filtered Containment Vent Systems and Containment Cooling Strategies for Water Cooled Reactors. Proceedings of a Technical Meeting
Imprint Pagination
270 p.
Journal Page Range
p. 37-45
ISSN
1011-4289
Report number
IAEA-TECDOC--1812

Conference

Title
Technical Meeting on Severe Accident Mitigation through Improvements in Filtered Containment Venting for Water Cooled Reactors
Dates
31 Aug - 3 Sep 2015
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
48058093
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BELGIUM; CONTAINMENT; IODINE; NUCLEAR POWER PLANTS; RADIATION PROTECTION; SEVERE ACCIDENTS; VENTILATION SYSTEMS; VENTS
Descriptors DEC
ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; DEVELOPED COUNTRIES; ELEMENTS; EUROPE; HALOGENS; NONMETALS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS; WESTERN EUROPE

Optional Information

Notes
8 refs., 2 tabs.