Published 2009 | Version v1
Report

Qualification of P91 welds through Small Punch creep testing

  • 1. Institute for Energy, Joint Research Centre, European Commission, 1755 ZG Petten (Netherlands)

Description

Full text: As a result of its high temperature creep strength, the martensitic alloy P91 is a strong candidate for application as a pressure vessel and heat exchanger material of construction in Next Generation nuclear plant. This candidature is supported by lengthy and successful operation in other high temperature plant in particular in fossil fuel fired plant. The only potential area of concern which will have to be taken into account for the nuclear application concerns the behaviour of construction weldments. Any risk of Type IV cracking has to be avoided and hence a thorough knowledge concerning the integrity of the weld has to be demonstrated. This can be achieved on the macro scale through cross weld creep testing although the results of such tests are difficult to interpret and are not included in design codes. A novel approach is proposed which relies on the determination of the creep properties of the different zones of the weldment on a micro-scale based on the Small Punch Testing methodology. Although results from such tests are similarly debarred from design codes at present, the potential of the method should be evaluated through testing and analysis as it has a second prospective role in plant operation lifetime assessment once the plant is in operation. The test methodology has recently been incorporated into a CEN Code of Practice in order to improve the acceptability of the results. In this paper, results are presented from the Small Punch creep tests carried out exactly following the Code of Practice for the various constituent zones of the weldment and the potential weaknesses are identified within the heat affected zone. (author)

Part of:
Book of abstracts of the joint EC-IAEA topical meeting on development of new structural materials for advanced fission and fusion reactor systems

Additional details

Publishing Information

Imprint Title
Book of abstracts of the joint EC-IAEA topical meeting on development of new structural materials for advanced fission and fusion reactor systems
Imprint Pagination
57 p.
Journal Page Range
p. 34
Report number
INIS-XA--09N1744

Conference

Title
Joint EC-IAEA topical meeting on development of new structural materials for advanced fission and fusion reactor systems
Dates
5-9 Oct 2009
Place
Barcelona (Spain)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
40109416
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALLOYS; CREEP; DESIGN; HEAT AFFECTED ZONE; HEAT EXCHANGERS; NUCLEAR POWER PLANTS; PRESSURE VESSELS; TESTING; WELDED JOINTS
Descriptors DEC
CONTAINERS; JOINTS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS; ZONES

Optional Information

Secondary number(s)
F1-TR--37435