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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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At least 1,009 records · Page 56
All sourcesNASA NTRSDOE OSTI
DOE OSTI2014

Evaluation on the Feasibility of Using Ultrasonic Testing of Reactor Pressure Vessel Welds for Assessing Flaw Density/Distribution per 10 CFR 50.61a, Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock

This technical letter report provides the status of an assessment undertaken by PNNL at the request of the NRC to verify the capability of periodic ASME-required volumetric examinations of reactor vessels to characterize the density and distribution of flaws of interest for applying §50.61a on a plant-by-plant basis. The PTS rule, described in the Code of Federal Regulations, Title 10, Section 50.61 (§50.61), "Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events," establishes screening criteria to ensure that the potential for a reactor vessel to fail due to a PTS event is deemed to be acceptably low. Recently, the NRC completed a research program that concluded that the risk of through-wall cracking due to a PTS event is much lower than previously estimated. The NRC subsequently developed and promulgated an alternate PTS rule, §50.61a, that can be implemented by PWR licensees. The §50.61a rule differs from §50.61 in that it requires licensees who choose to follow this alternate method to analyze the results from periodic volumetric examinations required by the ASME Code, Section XI, Rules for Inservice Inspection (ISI) of Nuclear Power Plants.

alternate PTS rule↗
DOE OSTI2015

Mechanical Properties of AM Stainless Steel Parts and Repair Welds

Goals: Advance certification of AM materials and compare microstructure and its evolution during processing and deformation between AM fabricated and conventional steels. Deliverables achieved: Measured texture data for 17 steel samples on HIPPO, including material planned to be shocked in pRAD in FY16; quantified texture and austenite/ferrite phase fractions; and provide input data for deformation modeling.

Materials Science(36)↗
DOE OSTI2015

Design of Experiment for Irradiation of Welded Candidate Fe-Cr-Al Alloys

The objective of the irradiation campaign described within is to provide critical data on the radiation response of candidate Fe-Cr-Al alloys designed to have enhanced weldability and radiation tolerance. This objective will be met by using a specialized irradiation capsule to be inserted into Oak Ridge National Laboratory’s High Flux Isotope Reactor (HFIR) followed by extensive post irradiation examination (PIE) including mechanical testing and microstructural characterization. Several different irradiation temperatures and doses will be investigated to establish temperature/dose relationships on specific radiation-induced and/or radiation-enhanced mechanisms within the candidate Fe-Cr-Al alloys. Data and analysis as the result of these efforts will enable informed decisions on the future use of Fe-CrAl alloys for a wide range of nuclear power generation applications including fission and fusion based reactor applications.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2015

Preliminary Results on FeCrAl Alloys in the As-received and Welded State Designed to Have Enhanced Weldability and Radiation Tolerance

The present report summarizes and discusses the recent results on developing a modern, nuclear grade FeCrAl alloy designed to have enhanced radiation tolerance and weldability. The alloys used for these investigations are modern FeCrAl alloys based on a Fe-13Cr-5Al-2Mo-0.2Si-0.05Y alloy (in wt.%, designated C35M). Development efforts have focused on assessing the influence of chemistry and microstructure on the fabricability and performance of these newly developed alloys. Specific focus was made to assess the weldability, thermal stability, and radiation tolerance.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

Status Report on Irradiation Capsules Containing Welded FeCrAl Specimens for Radiation Tolerance Evaluation

This status report provides the background and current status of a series of irradiation capsules, or “rabbits”, that were designed and built to test the contributions of microstructure, composition, damage dose, and irradiation temperature on the radiation tolerance of candidate FeCrAl alloys being developed to have enhanced weldability and radiation tolerance. These rabbits will also test the validity of using an ultra-miniature tensile specimen to assess the mechanical properties of irradiated FeCrAl base metal and weldments. All rabbits are to be irradiated in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) to damage doses up to ≥15 dpa at temperatures between 200-550°C.

36 MATERIALS SCIENCE↗