A5037552942- Nuclear Materials and Properties
- Nuclear and radioactivity studies
- Graphite, nuclear technology, radiation studies
- Nuclear reactor physics and engineering
- Fatigue and fracture mechanics
- Hydrogen embrittlement and corrosion behaviors in metals
- Non-Destructive Testing Techniques
- Fusion materials and technologies
- Risk and Safety Analysis
- Nuclear Engineering Thermal-Hydraulics
- MXene and MAX Phase Materials
- Material Properties and Failure Mechanisms
- Aluminum Alloys Composites Properties
- Nuclear Physics and Applications
- Welding Techniques and Residual Stresses
- Concrete Corrosion and Durability
- Radioactive element chemistry and processing
- Catalytic Processes in Materials Science
- Structural Integrity and Reliability Analysis
- Ultrasonics and Acoustic Wave Propagation
- Nuclear materials and radiation effects
- Heat transfer and supercritical fluids
- Thermodynamic and Structural Properties of Metals and Alloys
- Advanced ceramic materials synthesis
- Radiation Therapy and Dosimetry
Savannah River National Laboratory
2015-2024
Idaho National Laboratory
2017
Materials Science & Engineering
2012
University of South Carolina
2011
Fraunhofer Institute for Structural Durability and System Reliability
2007
Office of Scientific and Technical Information
1992
Westinghouse Electric (United States)
1991
A compendium of mechanical properties carbon and low alloy steels following hydrogen exposure has been assembled from literature sources. The property sets include yield strength, ultimate tensile uniform elongation, reduction in area, threshold stress intensity factor, fracture toughness, fatigue crack growth. These are sources under a variety test methods conditions. collection data is by no means complete, but the diversity dependency results on method sufficient to warrant design...
Mechanical testing of A285 carbon steel, a storage tank material, was performed to develop fracture properties based on the constraint theory mechanics. A series single edge-notched bend (SENB) specimen designs with various levels crack tip were used. The variation achieved by changing ratio initial length depth. test data show that J-R curves are specimen-design-dependent, which is known as effect. two-parameter methodology adopted construct constraint-modified curve, function parameter,...
Literature survey has been performed for a compendium of mechanical properties carbon and low alloy steels following hydrogen exposure. The property sets include yield strength, ultimate tensile uniform elongation, reduction area, threshold stress intensity factor, fracture toughness, fatigue crack growth. These are drawn from literature sources under variety test methods conditions. However, the collection data is by no means complete, but diversity dependency results in method sufficient...
A multipurpose canister (MPC) made of austenitic stainless steel is loaded with used nuclear fuel assemblies and part the transfer cask system to move from spent pool prepare for storage, storage on-site dry storage. This weld-sealed also expected be transportation package following The may subject service-induced degradation especially if exposed aggressive environments during possible very long-term period permanent repository yet identified readied. Stress corrosion cracking initiated on...
A recently revised American Society for Testing and Materials consensus standard guide drying of spent nuclear fuel (SNF) provides considerations guidance preparing SNF its safe storage in a sealed dry system. The discusses (1) needs drying, (2) techniques to dry, (3) demonstration adequate dryness. No specific approach is prescribed since the effective depend on specifics This paper these topics using examples both Zr-alloy-clad commercial aluminum-alloy-clad research reactor SNF.Residual...
Thermal models are constructed and analyses performed of aluminum-based spent nuclear fuel (Al-SNF) in interim dry storage geologic disposal configurations. Two developed, referred to as the model codisposal waste package (WP) model. Time-dependent source terms Al-SNF forms defense high-level (DHLW) canisters also developed for thermal performance analysis WP.The is a three-dimensional conduction-convection conjugate investigate natural convection cooling sealed canister with vertical...
An experiment was conducted to investigate the role of weld residual stress on corrosion cracking in welded carbon steel plates prototypic those used for nuclear waste storage tanks. Carbon specimen were butt-joined with Gas Metal Arc Welding technique. Initial cracks (seed cracks) machined across and heat affected zone. These then submerged a simulated high level radioactive chemistry environment. Stress occurred as-welded plate but not stress-relieved duplicate. A detailed finite element...
Abstract Stress corrosion cracking (SCC) had occurred in early-generation high-level nuclear waste tanks constructed by welding carbon steel. This paper describes an ultrasonic inspection system and its fundamental ability to detect quantify the length of SCC on thick welded steel plates. The finite element method (FEM) was applied simulate process estimate residual stress field. Growth cracks is driven crack intensities exceeding subcritical threshold intensity. subject plate experimentally...
Abstract Stress corrosion cracking may occur when chloride-bearing salts deposit and deliquesce on the external surface of stainless steel spent nuclear fuel storage canisters at weld regions with high residual stresses. Although it has not yet been observed, this phenomenon leads to a confinement concern for these due its potential radioactive materials breaching through containment system boundary provided by canister wall during extended storage. The tests crack growth rate have conducted...
Safe shipment and storage of nuclear reactor discharged fuel requires an understanding how the may perform under various conditions that can be encountered. One specific focus concern is performance during a drop accident. Tests at Savannah River National Laboratory (SRNL) are being performed to characterize properties clad relative mechanical accident condition such as container drop. Unirradiated ZIRLO tubing samples have been charged with range hydride levels simulate actual rod levels....
Abstract This paper compares engineering J estimates for Spent Fuel Canisters (SFCs) under combined mechanical and welding residual stress (WRS) with finite element (FE) results. Engineering are based on reference method provided in the R6 procedure considering interaction between primary secondary stresses using V-factor. It is found that should be considered fracture assessment reasonably conservative compared to FE analysis