Light water reactor pressure vessel surveillance dosimetry improvement program. Volume 1. Notch ductility and fracture toughness degradation of A 302-B and A 533-B reference plates from PSF simulated surveillance and through-wall irradiation capsules

Technical Report · Sun Apr 01 00:00:00 EST 1984

OSTI ID:6924157

Hawthorne, J R; Menke, B H; Hiser, A L

Mechanical properties data have been developed for two of the materials: the ASTM A302-B correlation monitor reference plate and the A533-B plate No. 03 from the NRC's Heavy Section Steel Technology Program. These results are presented together with an overview of specimen irradiation and testing procedures. Data comparisons are used to describe the observed toughness gradient produced by irradiation where fluences were typical of vessel end-of-life conditions. In addition, assessments are made of the relative irradiation effect at surveillance capsule vs. through-wall locations and the correspondence of Charpy-V vs. fracture toughness test methods in their independent descriptions of radiation-induced embrittlement. Irradiation in the simulated surveillance capsule location was found to reproduce reasonably well the irradiation effect to vessel inner surface and quarter wall thickness positions. As expected, the adjustment of the ASME lower bound (i.e., dynamic) K/sub IR/ toughness curve by the radiation induced elevation of the Charpy-V 41 J and the compact specimen 100 MPa ..sqrt..m temperatures was conservative when compared against the static toughness data. However, the temperature elevation of the C/sub v/ curve (41 J level) with irradiation frequently did not provide a conservative estimate of the temperature elevation defined by fracture toughness tests (100 MPa ..sqrt..m level). On the other hand, correction of the fracture toughness data for lack of test specimen constraint (..beta../sub Ic/-correction) results in transition temperature elevations less than the C/sub v/ 41 J elevations, in most cases. Overall, the toughness gradient observed between in-wall locations after irradiation was small for both materials; the difference between transition temperatures for wall surface vs. mid thickness locations was 31/sup 0/C or less, independent of the test method used. Candidate areas for future research investigation are discussed.

• Research Organization: Materials Engineering Associates, Inc., Lanham, MD (USA)
• OSTI ID: 6924157
• Report Number(s): NUREG/CR-3295-Vol.1; MEA-2017-Vol.1; ON: DE84901099
• Resource Relation: Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
22 GENERAL STUDIES OF NUCLEAR REACTORS
STEEL-ASTM-A302
PHYSICAL RADIATION EFFECTS
STEEL-ASTM-A533-B
CHARPY TEST
DEPTH
DUCTILITY
FRACTURE PROPERTIES
MECHANICAL PROPERTIES
NEUTRON DOSIMETRY
ORR REACTOR
PLATES
PRESSURE VESSELS
TENSILE PROPERTIES
THICKNESS
WATER COOLED REACTORS
ALLOYS
CARBON STEELS
CONTAINERS
DESTRUCTIVE TESTING
DIMENSIONS
DOSIMETRY
ENRICHED URANIUM REACTORS
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MECHANICAL TESTS
RADIATION EFFECTS
REACTORS
STEELS
TANK TYPE REACTORS
TESTING
WATER MODERATED REACTORS
360106* - Metals & Alloys- Radiation Effects
220200 - Nuclear Reactor Technology- Components & Accessories