Structural integrity of water reactor pressure boundary components: Annual report for 1986
Description
This program is being conducted for the NRC to provide analytical and experimental methods and data that are necessary to ensure the structural safety and reliability of pressure boundary components in commercial, light water reactor power systems. Emphasis is placed on characterization of material properties performance in a nuclear environment for the application to plant-life extension and mitigation of the consequences of postulated accident scenarios. Current work is organized into three major tasks; (1) fracture mechanics investigations, (2) environmentally-assisted crack growth in high temperature, primary reactor water, and (3) radiation sensitivity and postirradiation properties recovery. Research progress in these three tasks for 1986 is summarized in this report
Availability note (English)
NTIS, PC A11/MF A01 - US Govt. Printing Office. as TI87900921.
Files
Additional details
Publishing Information
- Imprint Pagination
- 235 p.
- Report number
- NUREG/CR--3228-Vol.5
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19018812
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; FRACTURE MECHANICS; MECHANICAL PROPERTIES; MECHANICAL STRUCTURES; PERFORMANCE; PHYSICAL RADIATION EFFECTS; PROGRESS REPORT; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; RELIABILITY; RESEARCH PROGRAMS; SAFETY; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICS; POWER REACTORS; RADIATION EFFECTS; REACTORS; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- MEA--2207-Vol.5.