Compilation of reports from research supported by the Materials Engineering Branch, Division of Engineering: 1991--1993. Volume 2
- comp.
Since 1965, the Materials Engineering Branch, Division of Engineering, of the Nuclear Regulatory Commission`s Office of Nuclear Regulatory Research, and its predecessors dating back to the Atomic Energy Commission (AEC), has sponsored research programs concerning the integrity of the primary system pressure boundary of light water reactors. The components of concern in these research programs have included the reactor pressure vessel (RPV), steam generators, and the piping. These research programs have covered a broad range of topics, including fracture mechanics analysis and experimental work for RPV and piping applications, inspection method development and qualification, and evaluation of irradiation effects to RPV steels. This report provides as complete a listing as practical of formal technical reports submitted to the NRC by the investigators working on these research programs. This listing includes topical, final and progress reports, and is segmented by topic area. In many cases a report will cover several topics (such as in the case of progress reports of multi-faceted programs), but is listed under only one topic. Therefore, in searching for reports on a specific topic, other related topic areas should be checked also. The separate volumes of this report cover the following periods: Volume 1: 1965--1990 and Volume 2: 1991--1993.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Materials Engineering Branch
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 10173837
- Report Number(s):
- NUREG-1426-Vol.2; ON: TI94016727; TRN: 94:015634
- Resource Relation:
- Other Information: PBD: Jun 1994
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
US NRC
DATA COMPILATION
REACTOR MATERIALS
WATER COOLED REACTORS
RESEARCH PROGRAMS
ANNEALING
CARBON STEELS
DOSIMETRY
CRACK PROPAGATION
FATIGUE
FRACTURE PROPERTIES
REACTOR COMPONENTS
ACOUSTIC EMISSION TESTING
IN-SERVICE INSPECTION
PIPES
PRESSURE VESSELS
EMBRITTLEMENT
RADIATION EFFECTS
STAINLESS STEELS
AGING
THERMAL STRESSES
360100
210100
210200
METALS AND ALLOYS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED