Published May 1999 | Version v1
Report Metadata-only

The effects of neutron irradiation on fracture toughness of austenitic stainless steels

Creators

Description

Austenitic stainless steels are used extensively as structural alloys in reactor pressure vessel internal components because of their superior fracture toughness properties. However, exposure to high levels of neutron irradiation for extended periods leads to significant reduction in the fracture resistance of these steels. This paper presents results of fracture toughness J-R curve tests on four heats of Type 304 stainless steel that were irradiated in a helium environment in the Halden heavy water boiling reactor. The tests were performed on 1 /4-T compact tension specimens in air at 288 C; crack extensions were determined by both DC potential and elastic unloading compliance techniques (author) (ml)

Part of:
Enlarged Halden programme group meeting on high burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects and man-machine systems research. Volume I

Additional details

Publishing Information

Imprint Title
High burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects and man-machine systems research
Imprint Pagination
vp.
Journal Page Range
p. 18
Report number
HPR--351-V1

Conference

Title
Enlarged HPG meeting on high burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects and man-machine systems research
Dates
24-29 May 1999
Place
Loen (Norway)

INIS

Country of Publication
Norway
Country of Input or Organization
Norway
INIS RN
38108746
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
BWR TYPE REACTORS; CRACK PROPAGATION; CRACKS; DYNAMIC LOADS; EXPERIMENTAL DATA; HBWR REACTOR; IRRADIATION; MATERIALS TESTING; NEUTRON FLUENCE; NUCLEAR POWER PLANTS; PHYSICAL RADIATION EFFECTS; PWR TYPE REACTORS; REACTOR COMPONENTS; SIMULATION; STAINLESS STEEL-304; STRESS ANALYSIS; STRESS INTENSITY FACTORS; TEMPERATURE RANGE 0400-1000 K; WATER CHEMISTRY
Descriptors DEC
ALLOYS; AUSTENITIC STEELS; BHWR TYPE REACTORS; CARBON ADDITIONS; CHEMISTRY; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; DATA; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; NICKEL ALLOYS; NUCLEAR FACILITIES; NUMERICAL DATA; POWER PLANTS; POWER REACTORS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; TANK TYPE REACTORS; TEMPERATURE RANGE; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
24 refs., 5 figs., 7 tabs