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The 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.

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Annual progress rept. (Final) for CY 1979,

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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. Postirradiation test data are presented for plate, forging and weld deposit materials irradiated in six reactor experiments to fluences ranging from approx. 0.1 to approx. 10 to the 19th power nsq cm 1 MeV at 288 C. Comparisons are made between results for standard Charpy V-notch and fatigue precracked Charpy-V tests of preirradation and postirradiation metarial conditions. A companion document Annual Progress Report for CY 1979 Part II will present results for the 25.4 mm compact toughness J-R curve tests of the same materials and material conditions. A preliminary correlation of the Charpy-V and J-integral fracture toughness property changes with irradiation is observed.

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  • Containers and Packaging
  • Fission Reactor Materials

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