Published 1979 | Version v1
Report Open

Radiation damage and annealing of Cr-Mo-V steel

Creators

Description

Radiation embrittlement was studied of steel 15KH2MFA used for the WWER-440 type reactor pressure vessels. The results show that it has higher resistance to radiation embrittlement than, eg., steel ASTM A533-B used for similar purposes. In the steel studied, radiation embrittlement at normal irradiation temperature (up to 350 degC) and a neutron flux of up to 4x1024 m-2 is reversible. The degree of regeneration, however, depends on the chemical composition of the steel. The results confirm that steel 15KH2MFA is suitable for the manufacture of reactor pressure vessels. (J.B.)

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
15 p.
Report number
ZJE--239

INIS

Country of Publication
Serbia and Montenegro
Country of Input or Organization
Serbia and Montenegro
INIS RN
12607130
Subject category
S36: MATERIALS SCIENCE;
Descriptors DEI
ANNEALING; CHROMIUM-MOLYBDENUM STEELS; COMPARATIVE EVALUATIONS; EMBRITTLEMENT; HIGH TEMPERATURE; NEUTRON FLUENCE; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; STEEL-ASTM-A533-B; VANADIUM ADDITIONS; WWER TYPE REACTORS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CARBON STEELS; CHROMIUM ALLOYS; CHROMIUM STEELS; CONTAINERS; ENRICHED URANIUM REACTORS; HEAT TREATMENTS; IRON ALLOYS; IRON BASE ALLOYS; MOLYBDENUM ALLOYS; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS