Published February 1962 | Version v1
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Irradiation effects in strain aged pressure vessel steel

Creators

Description

Tensile specimens, Charpy-V notch and subsize impact specimens of an aluminium killed carbon manganese steel, have been irradiated at 160 - 190 deg C in the reactor G1. The total neutron dose received was 2.4 x 1018 n/cm2 (> 1 MeV). Specimens were prepared from normalized plate and from strain aged material from the same plate. It was found that the changes in brittle ductile transition temperature due to neutron irradiation and those due to strain ageing must be considered additive

Availability note (English)

Available from INIS in electronic form

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Additional details

Publishing Information

Imprint Pagination
12 p.
Report number
AE--65

INIS

Country of Publication
Sweden
Country of Input or Organization
Sweden
INIS RN
38092876
Subject category
S36: MATERIALS SCIENCE;
Descriptors DEI
AGESTA REACTOR; AGING; BRITTLE-DUCTILE TRANSITIONS; CHARPY TEST; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS
Descriptors DEC
CONTAINERS; DESTRUCTIVE TESTING; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IMPACT TESTS; MATERIALS TESTING; MECHANICAL TESTS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PROCESS HEAT REACTORS; RADIATION EFFECTS; REACTORS; TESTING; THERMAL REACTORS

Optional Information

Notes
4 refs., 4 figs.