crack growth resistance in nuclear graphite - core

Graphite nodules and fatigue crack propagation

ABSTRACT Since 1948, ductile cast irons (DCIs) are able to combine the toughness of steels with the good castability of grey irons. They are widely used in a number of applications, for example wheels, gears, and crankshafts in cars and trucks. Their fatigue crack propagation resistance depends on loading conditions, chemical composition, matrix microstructure and graphite elements morphology

10.1016/j.carbon.2006.05.011

Graphite shows excellent thermal shock resistance due to its high thermal conductivity and low thermal expansion. For this reason it is a principal component in the manufacture of refractory products for use as electrodes in the aluminium smelting process, for steel-making arc furnaces and as a core material in nuclear reactors [3,4] .

Materials considerations for aerospace applications

Titanium–graphite is a combination of titanium foil (Ti-15V-3Cr-3Al-3Sn) and carbon-fiber epoxy, which improves the impact resistance and bearing strength of the laminate. Another fiber-reinforced polymer–metal composite is a combination of aluminum sheets and glass fiber/epoxy.

FM

Nuclear graphite is widely used as fuel blocks and reactor internals in high-temperature gas-cooled reactors (HTR) because of its high-temperature resistance and neutron moderation [1, 2]. As the structural material of HTR, the mechanical property and structural integrity of graphite structure have a great impact on HTR's safe operation.

Korukonda Murty

Crack lengths will be monitored by DC potential drop method that allows continuous monitoring of the crack growth. An online data acquisition system will be used along with specially developed software for continuous recording of data including time variations of load (using internally strain-gauged bolts), DC drop and crack-length as well as K.

Fatigue stress concentration and notch sensitivity in

C. Abnormal grain growth mechanism for crack initiation The exact origins of AGG and its role on the cyclic deformation and fracture in these materials are still unclear. Boyce et al. Reference Boyce and Padilla 5 showed that abnormally large grains in fatigued NC Ni–Fe were elongated in the directions of maximum stress and that they were oriented in such a way to suggest uniaxial deformation.

Crack propagation in graphene: Journal of Applied

2015/8/14The crack initiation and growth mechanisms in an 2D graphene lattice structure are studied based on molecular dynamics simulations. Crack growth in an initial edge crack model in the arm-chair and the zig-zag lattice configurations of

IN SITU CHARACTERISATION OF UNIRRADIATED GILSOCARBON GRAPHITE

The evolution of the deformation and fracture of a Gilsocarbon nuclear grade graphite has been investigated in situ at three length-scales (nano-, micro- and macro-scale): (i) Neutron diffraction was used to quantify the lattice spacing changes with externally applied bulk strain.

10.1016/j.carbon.2006.05.011

Graphite shows excellent thermal shock resistance due to its high thermal conductivity and low thermal expansion. For this reason it is a principal component in the manufacture of refractory products for use as electrodes in the aluminium smelting process, for steel-making arc furnaces and as a core material in nuclear reactors [3,4] .

Cracked Nuclear Reactor Shroud Warning Toll

2015/7/8Similarly, the graphite keyway root cracks found at the nuclear reactor near Glasgow Scotland, are a bell of warning: "Serious distortion of the graphite core due to cracking could prevent the insertion of control rods, which are essential for safety and are used to"

Fracture behavior of nuclear graphite NBG

The obtained curve of KIC against crack length showed three stages: an initial increase, a plateau and a final decrease, similar to a typical crack growth resistance curve. An analytical model based on the fracture process zone ahead of the crack tip was used to examine the size effect and to derive the length of fracture process zone cf and size-independent constant KIf.

(PDF) CRACK GROWTH IN NUCLEAR GRAPHITES USING R

Fracture is predicted found for a Japanese isotropic nuclear graphite, Figure to originate at the key-way root and travel to the bore, 3(a), a rise in R with crack initiation followed by a steady- Figure l(a). Currently, a critical stress criterion has been state value

Analysis of crack propagation in nuclear graphite using

2008/1/31S. Fazluddin, Crack Growth Resistance in Nuclear Graphite, PhD thesis, Department of Materials, The University of Leeds, July (2002). Google Scholar T.D. Burchell, T. Oku and M. Eto. A Comparison of Fracture Toughness Measurement Techniques as Applied

IN SITU CHARACTERISATION OF UNIRRADIATED GILSOCARBON GRAPHITE

The evolution of the deformation and fracture of a Gilsocarbon nuclear grade graphite has been investigated in situ at three length-scales (nano-, micro- and macro-scale): (i) Neutron diffraction was used to quantify the lattice spacing changes with externally applied bulk strain.

AMALIA, assessment of nuclear power plants core

AMALIA, assessment of nuclear power plants core internals (EMMA) The AMALIA laboratory is used in order to study the effect of environment on the mechanical performance and characterisation including life assessment and qualification of structural materials for present and next generation of nuclear

Nuclear Thermal Propulsion Reactor Materials

2019/10/9Nuclear thermal propulsion (NTP) systems have been studied in both the USA and the former Soviet Union since the 1950s for use in space science and exploration missions. NTP uses nuclear fission to heat hydrogen to very high temperatures in a short amount of time so that the hydrogen can provide thrust as it accelerates through an engine nozzle. Benefits of NTP systems compared to

Technical Basis Part 2 for Code Case N

Technical Basis Part 2 for Code Case N-889: Reference Stress Corrosion Crack Growth Rate Curves for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments Eason, E. D., Pathania, R., Jenssen, A., and Weakland, D. P. (September 15

Nuclear Graphite Research Needs in the 21st Century

in Oxidation Resistance of the Nuclear Graphite By Reaction-Coated SiC Coating, J. Nucl. Mater. 224, 103 (1995). [5] D. R. De Halas, Radiation Effects in Graphite, in Nuclear Graphite, ed. by R. E. Nightengale 7: Theory of Radiation Effects

Quantitative in situ study of short crack propagation in

Quantitative in situ study of short crack propagation in polygranular graphite by digital image correlation Quantitative in situ study of short crack propagation in polygranular graphite by digital image MOSTAFAVI, M.; MARROW, T.J. 2012-08-01 00:00:00 NOMENCLATURE a Half a distance between inner and outer supports da Crack length increase f (σ) Frequency of occurrence of σ h Specimen

Management of Ageing in Graphite Reactor Cores

Nuclear power currently contributes nearly a quarter of the electricity needs of the UK. Much of this is from nuclear reactor plants developed some fifty years ago. Consequently, in the next few decades, many of these reactors and components are coming to the end

Crack growth resistance in nuclear graphite

R-curve behaviour is often used for evaluating crack growth resistance in quasibrittle materials but few studies have focused on polycrystalline graphite. In this study, R-curve behaviour in three commercial grade nuclear graphites, ofud varying structure and properties, is compared using an optical method, a theoretical compliance method, and, a potential drop (PD) technique to measure crack

IN SITU CHARACTERISATION OF UNIRRADIATED GILSOCARBON GRAPHITE

The evolution of the deformation and fracture of a Gilsocarbon nuclear grade graphite has been investigated in situ at three length-scales (nano-, micro- and macro-scale): (i) Neutron diffraction was used to quantify the lattice spacing changes with externally applied bulk strain.

Effect of Tensile Strength on the Microstructure of

Owing to the inhomogeneous distribution of FLiNaK salt impregnated into graphite which is observed by scanning electron microscopy and an element probe micro-analyzer, a map scan of in situ real-time tensile synchrotron-based two-dimensional X-ray diffraction (2D-XRD) at several fixed external forces was implemented to reveal the local microstructure evolution of graphite and FLiNaK salt

Reactor pressure vessel

Graphite-moderated reactor - Includes the Chernobyl reactor (), which has a highly unusual reactor configuration compared to the vast majority of nuclear power plants in Russia and around the world. Gas cooled thermal reactor - Includes the Advanced Gas-cooled Reactor, the gas cooled fast breeder reactor, and the high temperature gas cooled reactor .

Advanced Gas

The Advanced Gas-cooled Reactor (AGR) is a type of nuclear reactor designed and operated in the United Kingdom. These are the second generation of British gas-cooled reactors, using graphite as the neutron moderator and carbon dioxide as coolant. They have been the backbone of the UK's nuclear power generation fleet since the 1980s. The AGR

Brittle Failure of Graphite Weakened by V

It relates brittle fracture of graphite to the crack nucleation and the subcritical crack growth from pre-existing pores under the influence of the stress field related to the pores or defects. Lomakin et al. [ 17 ] instead, through an energy release rate criterion, analyzed the fracture initiation in cracked graphite specimens under mode I loading.

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