Published 2015 | Version v1
Miscellaneous Restricted

An effective surveillance strategy for reactor pressure vessel assessment in the long term operation perspective

  • 1. SCK-CEN, Boeretang 200, 2400 Mol (Belgium)
  • 2. Tractebel Engineering, Avenue Ariane 7, 1200 Brussels (Belgium)

Description

The reactor pressure vessel (RPV) irradiation embrittlement is monitored by means of surveillance capsules containing the RPV belt-line materials, inserted inside the reactor pressure vessel (RPV) before the start of operation. These capsules are placed at location where they receive a higher neutron flux than the vessel wall, by a factor of the order of 2 to 3. They are regularly retrieved and tested to evaluate the RPV irradiation embrittlement according to specific regulatory procedures and standards, in order to guarantee the safe operation of the RPV throughout its lifetime. These procedures are often relying on empirical but conservative concepts. In parallel, material research reactor (MTR) irradiations are often used to support the surveillance data and to develop a better understanding of irradiation effects, not only qualitatively but also quantitatively. Taking advantage of the increased understanding of irradiation effects, analytical tools were developed to improve the evaluation embrittlement and quality assurance of the RPV embrittlement assessment. In this framework, an alternative but complementary surveillance program assessment was developed in Belgium, the so-called enhanced surveillance, in order to benefit from the latest developments in the area of materials science and irradiation effects. The neutron flux and fracture properties of the surveillance materials can be reliably characterized and correlated to each other using physically-based rather than empirical concepts. The enhanced surveillance approach is complementary to the mandatory regulatory procedure and allows quantifying the conservatism of the regulatory approach. The enhanced surveillance approach that uses the reconstitution technology to fabricate additional small size specimens, appropriate modeling tools and microstructural examination when required, makes it possible to rationalize all available information in a physically-based way

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Additional details

Publishing Information

Imprint Pagination
53 p.
Report number
INIS-FR--15-0296

Conference

Title
Conference on Contribution of Materials Investigations and Operating Experience to LWRs' Safety, Performance and Reliability
Acronym
Fontevraud 8
Dates
15-18 Sep 2014
Place
Avignon (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
46081608
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
EMBRITTLEMENT; FRACTURE PROPERTIES; MECHANICAL TESTS; MONITORING; OPTIMIZATION; PRESSURE VESSELS; SIMULATION; WATER COOLED REACTORS
Descriptors DEC
CONTAINERS; MATERIALS TESTING; MECHANICAL PROPERTIES; REACTORS; TESTING

Optional Information

Notes
33 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/