Materials Literature

文献浏览

按标题、摘要、年份、主题和来源检索公开元数据。结果保留作者、摘要、分类与原始来源链接。

清除
第 247773 / 303984 页 · 当前展示 4,955,441–4,955,460 / 6,079,668 条匹配结果 · 摘要仅作预览

Drop Analysis of Structures and Development of Impact Energy Absorber

S. S. Babu、Inderdeep Grewal、Ravi P. Jategaonkar 等 4 位作者2012-07-15OpenAlex

Historic radioactive waste generated, due to various research and development activities at Chalk River Laboratories (CRL), as part of fuel development process are stored in containers in Tile holes. The fuel in the historic containers needs to be removed to new containers that provide improved storage conditions. A n…

Graphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Surface plasmon resonance of Cu nanowires in polycarbonate template

A. Azariana、Ferydon Babaei2012-07-15arXiv (Cornell University)

The Cu nanowires were electrodeposited in polycarbonate track-etched (PCT) membrane. SEM, TEM and XPS techniques were used to characterize the morphology, structure and size of nanowires as well as chemical Composition. The absorption spectrum of copper nanowires embedded in PCT was measured and calculated for differe…

Plasmonic and Surface Plasmon ResearchNanofabrication and Lithography TechniquesAnodic Oxide Films and Nanostructures

Dynamic Finite Element Analysis of Drum-Type Shipping Packages for Radioactive Materials

Zenghu Han、Vikram N. Shah、Yung Y. Liu2012-07-15OpenAlex

The US Department of Energy (DOE) often uses Type AF and Type B drum-type packages for shipment of radioactive materials (RAM), both of which shall be designed and certified to meet the regulatory requirements specified in 10 CFR 71, to ensure safety, public health and protection of environment. In particular for the…

High-Velocity Impact and Material BehaviorGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Failure Analysis of an In-Service Natural Gas Pipeline

Huaixiang Cao、Xingqi Qiu、Xiaojing Yao 等 4 位作者2012-07-15OpenAlex

A natural gas pipeline which had been serviced nearly 10 years burst and led to fire. Analysis on samples taken from the pipeline had been made, the mechanism of crack initiation and propagation was discussed, and the cause of burst and fire of the pipeline was put forward. The analysis results showed that, the pipeli…

Corrosion Behavior and InhibitionHydrogen embrittlement and corrosion behaviors in metalsStructural Integrity and Reliability Analysis

Thermal Upgrading of 9977 Radioactive Material (RAM) Type B Package

Narendra K. Gupta、G. Abramczyk2012-07-15OpenAlex

The 9977 package is a radioactive material package that was originally certified to ship Heat Sources and RTG contents up to 19 watts and it is now being reviewed to significantly expand its contents in support of additional DOE missions. Thermal upgrading will be accomplished by employing stacked 3013 containers, a 3…

Nuclear Materials and PropertiesGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Material Characterization and Modeling Within Safety Analysis of Packages for Transport of Radioactive Material

Martin Neumann、Viktor Ballheimer、Jens Sterthaus 等 6 位作者2012-07-15OpenAlex

In mechanical design safety assessment of packages for the transport of radioactive material the International Atomic Energy Agency (IAEA) regulations [1, 2] require the use of one of four methods of demonstration of compliance with regulations: tests with prototypes, reference to previous satisfactory demonstrations,…

High-Velocity Impact and Material BehaviorGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Cracking of Heavy Wall Steam Separators During Fabrication: An Investigation

K. Dilip Kumar、Luis Ganhao2012-07-15OpenAlex

On a recent project, four high pressure steam separator vessels were received from overseas after fabrication. There was suspicion on the quality of fabrication when non destructive examination (NDE) reports were reviewed. There were major concerns with the quality of radiographic films as they did not meet the ASMe S…

Hydrogen embrittlement and corrosion behaviors in metalsWelding Techniques and Residual StressesNon-Destructive Testing Techniques

Thermal-Creep Induced Stress Relaxation Near a Notch in Zr-2.5Nb

Shuai Wan、Mark R. Daymond、R.A. Holt2012-07-15OpenAlex

In CANDU nuclear reactors, flaws on the surface of Zr-2.5Nb pressure tubes naturally cause stress concentration, and subsequently potentially lead to crack initiation through delayed hydride cracking. However, the concentrated stresses tend to relax due to creep, which is suggested to reduce the occurrences of cracks.…

Fusion materials and technologiesNuclear reactor physics and engineeringNuclear Materials and Properties

Graded Approach to Small Modular Reactor Implementation

William G. Culp、Brendaly Cintron-De Leon2012-07-15OpenAlex

The regulatory process covers health and safety issues in the context of large power reactors; this paper addresses how requirements on designers and owners might be scaled for small modular reactors (SMR) in proportion to the risks for the type of technology. Light water SMRs are designed to incorporate many of the f…

Nuclear reactor physics and engineeringGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Role of Transport and Kinetics in Growth of Renal Stones

Mohammad Kassemi2012-07-1542nd International Conference on Environmental Systems

Renal stone disease is not only a concern on earth but could conceivably pose as a serious risk to the astronauts health and safety in Space. In this paper, a combined transport-kinetics model for growth of calcium oxalate crystals is presented. The model is used to parametrically investigate the growth of renal calcu…

Radioactive element chemistry and processingCalcium Carbonate Crystallization and InhibitionCrystallization and Solubility Studies

Properties of Bimetallic Core-Shell Nanoclusters

Y. H. Park、Iyad Hijazi2012-07-15OpenAlex

Gold (Au) and copper (Cu) materials and their combination exhibit the most of the main wanted properties in nanostructures. Nobel metals such as Au and Cu have important magnetic, electronic, optical, catalytic and thermal properties. Compared to monometallic clusters, bimetallic nanoclusters have more degrees of free…

Nanocluster Synthesis and Applicationsnanoparticles nucleation surface interactions

Further Predictions of Fracture Experiments of a Pre-Cracked Pressurised Thermal Shock Disk (PTS-D) Specimen Under Warm Prestressing Loading Cycles

H. Teng、J. K. Sharples、Peter Budden2012-07-15OpenAlex

Finite element analyses have been performed to investigate the effects of warm prestressing (WPS) of a pre-cracked PTS-D (Pressurized Thermal Shock Disk) specimen. Three basic types of WPS loading cycles were used in the analyses: LUCF (Load-Unload-Cool-Fracture) cycle; LCF (Load-Cool-Fracture) cycle; and LCTF (Load-C…

Fatigue and fracture mechanicsHigh-Velocity Impact and Material BehaviorFire effects on concrete materials

Hot Isostatically Pressed (HIPed) Large Bore Valves for a Pressurised Water Reactor (PWR) Application

John Sulley、Michael Bohan2012-07-15OpenAlex

This paper presents an overview of the work undertaken by Rolls-Royce to introduce Hot Isostatically Pressed (HIP) large bore valve, 304 stainless steel, pressure boundaries into Pressurised Water Reactor (PWR) plant. It presents the work from a design justification/manufacturing quality assurance perspective, rather…

Nuclear Materials and PropertiesEngineering and Material Science ResearchNuclear and radioactivity studies

Prediction of Lower Bound Fracture Toughness in the Transition Temperature Region by T33-Stress

Kai Lu、Toshiyuki Meshii2012-07-15OpenAlex

It is well known that the fracture toughness Jc in the ductile-to-brittle transition temperature region depends highly on the specimen thickness (hereafter, TST). The TST effect on Jc, which Wallin [1] described as Jc (∝ KJc2) ∝ B(-1/2) (Jc was calculated from the equations outlined in ASTM E1820 [2], KJc was derived…

Microstructure and mechanical propertiesMicrostructure and Mechanical Properties of SteelsHydrogen embrittlement and corrosion behaviors in metals

Degradation of Moderator Graphite in Gas Cooled Reactors

R. Moskovic2012-07-15OpenAlex

Magnox reactors employ pile grade A (PGA) graphite as moderator. Reactor cores are typically constructed of twelve to thirteen layers of interlocking graphite bricks. Their temperature varies from 250°C at the bottom to 360°C at the top of the core. It serves a dual role as both the moderator and encasing the fuel in…

Nuclear reactor physics and engineeringGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Application of a Large-Scale Database System for the Analysis and Design of the US EPR™ Standard Nuclear Power Plant

Se-Kwon Jung、Joseph Harrold、Nawar Alchaar2012-07-15OpenAlex

Due to the increased size and complexity of large-scale commercial and industrial structures, it is increasingly challenging to manage key engineering data including analysis and design results of these structures. This paper presents a novel approach of using large-scale database systems as a means to gather, organiz…

Probabilistic and Robust Engineering DesignConcrete Corrosion and DurabilityGraphite, nuclear technology, radiation studies

Prediction of Residual Stress Distribution for RPV CRDM Penetration Nozzles

Hong-Yeol Bae、Yun‐Jae Kim、Ju-Hee Kim 等 5 位作者2012-07-15OpenAlex

In nuclear power plants, RPV (Reactor Pressure Vessel) upper head CRDM (Control Rod Drive Mechanism) penetration tubes has been fabricated J-groove weld geometry. Recently, the incidences of cracking in Alloy 600 CRDM tubes and their associated welds have increased significantly. The cracking mechanism has been attrib…

Fatigue and fracture mechanicsHydrogen embrittlement and corrosion behaviors in metalsNon-Destructive Testing Techniques

Application of the System Based Code Concept to the ASME Code for Liquid Metal Reactors

Tai Asayama、Shigeru Takaya、Masaki Morishita2012-07-15Volume 1: Codes and Standards

The System Based Code (SBC) which was initially proposed by Asada forms the basis of the development of a set of codes and standards in Japan that fully take advantage of the potential of liquid metal reactors (LMRs). The concept of SBC is also being elaborated within the American Society of Mechanical Engineers (ASME…

Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear and radioactivity studies

Blast Analysis, Design and Research: A Canadian Perspective

Waleed Mekky、Wael El‐Dakhakhni2012-07-15OpenAlex

In order to protect structures against accidental or deliberate blast loads, special expertise and knowledge are necessary to ensure adequate performance of the structural systems. Although the structure may require an extensive repair following a blast event, the main goal of the protective design is to avoid structu…

Structural Response to Dynamic LoadsEngineering and Material Science ResearchTransportation Safety and Impact Analysis

Compaction Ring Analysis of Concrete Penetration

Justin T. Loveless、Jennifer M. Conway、Mark E. Barkey 等 4 位作者2012-07-15OpenAlex

The purpose of this paper is to report the results of laboratory scale penetration tests on aged fine particle concrete targets. Hardened 4340 steel (RC-50) projectiles were fabricated with ogive noses and flat ends for the purpose of the tests. The projectiles were 0.164 inches in diameter with varying lengths. The p…

High-Velocity Impact and Material BehaviorElectromagnetic Launch and Propulsion TechnologyEngineering and Material Science Research