The NRL-EPRI research program (RP886-2), evaluation and prediction of neutron embrittlement in reactor pressure vessel materials. Part I. dynamic C sub V, PPC sub V investigations. Annual progress report (final) for CY 1979. [PWR; BWR]
Technical Report
·
OSTI ID:6052891
Nuclear reactor pressure vessel materials are subject to progressive reductions in fracture resistance in service due to neutron irradiation. Current technology is inadequate to quantitatively predict radiation embrittlement for all vessel materials and their metallurgical variations for the neutron fluences of interest. In addition a relationship between apparent notch ductility and fracture toughness in the irradiated condition is needed to evolve more quantitative projections of structural integrity. The NRL-EPRI RP886-2 Program was formulated to advance both areas for the benefit of reactor vessel design and operation. Its primary objective is the development of a high-quality data base for evaluation of current radiation-embrittlement projection methods and the development of improved methods. This report documents program highlights and research results for CY 1979 along with plans for the completion of program investigations.
- Research Organization:
- Naval Research Lab., Washington, DC (USA)
- OSTI ID:
- 6052891
- Report Number(s):
- AD-A-094067
- Country of Publication:
- United States
- Language:
- English
Similar Records
NRL-EPRI research program (RP886-2), evaluation and prediction of neutron embrittlement in reactor pressure vessel materials. Annual progress report for CY 1978
The NRL-EPRI research program (rp886-2) evaluation and prediction of neutron embrittlement in reactor pressure vessel materials. Annual progress report for CY 1977
NRL-EPRI research program (RP886-2): evaluation and prediction of neutron embrittlement in reactor pressure-vessel materials. Part I. Dynamic C/sub v/, PCC/sub v/ investigations. Annual progress report for CY 1979
Technical Report
·
Thu Aug 30 00:00:00 EDT 1979
·
OSTI ID:5504673
The NRL-EPRI research program (rp886-2) evaluation and prediction of neutron embrittlement in reactor pressure vessel materials. Annual progress report for CY 1977
Technical Report
·
Tue Feb 28 23:00:00 EST 1978
·
OSTI ID:6764207
NRL-EPRI research program (RP886-2): evaluation and prediction of neutron embrittlement in reactor pressure-vessel materials. Part I. Dynamic C/sub v/, PCC/sub v/ investigations. Annual progress report for CY 1979
Technical Report
·
Tue Dec 30 23:00:00 EST 1980
·
OSTI ID:5685170
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
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210200 -- Power Reactors
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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
BWR TYPE REACTORS
CHARPY TEST
CONTAINERS
DESTRUCTIVE TESTING
EMBRITTLEMENT
FATIGUE
FRACTURE PROPERTIES
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
PERFORMANCE
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
STEELS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
BWR TYPE REACTORS
CHARPY TEST
CONTAINERS
DESTRUCTIVE TESTING
EMBRITTLEMENT
FATIGUE
FRACTURE PROPERTIES
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
PERFORMANCE
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
STEELS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS