irradiation tests of several steels

(PDF) Charpy impact tests on martensitic/ferritic steels

Charpy impact tests were performed on martensitic/ferritic (MF) steels T91, F82H, Optifer-V and Optimax-A/-C irradiated in SINQ Target-3 up to 7.5 dpa and 500 appm He

(PDF) Charpy impact tests on martensitic/ferritic steels

Charpy impact tests were performed on martensitic/ferritic (MF) steels T91, F82H, Optifer-V and Optimax-A/-C irradiated in SINQ Target-3 up to 7.5 dpa and 500 appm He (PDF) In Situ Micropillar Compression Tests of 304 In Situ Micropillar Compression Tests of 304 Stainless Steels After Ion Irradiation and Helium Implantation several of the solution annealed and pre-implanted specimens were aged at 800°C for

(PDF) In-situ Observation of Irradiation Induced Defects

The study of irradiation-induced defects in the Zr alloys is important to understand the effect of irradiation damage to the materials. (PDF) LABORATORY EXPERIMENTS TENSILE TESTINGThe radiation damage effects produced by 800 MeV proton irradiation on the tensile properties of the two iron base alloys, Fe-2.25Cr-1Mo and Fe-12Cr-1Mo (HT-9) were determined.

Advances in the Hopkinson bar testing of irradiated/non

May 13, 2014 · In particular, complete results of the effect of irradiation on the dynamic mechanical properties of AISI304L steel, tested at 20, 400 and 550°C are presented. These high strain rate tests have been performed with a modified Hopkinson bar (MHB), installed inside a hot cell. Atom probe tomography applied to the analysis of irradiated steel welds was shown directly for therst time using atom probeeld ion microscopy (APFIM), an older version of the APT technique.19 Since, APT has been used to quantify irradiation-induced solute clus-ters in various steels retrieved from nuclear reactors. Overall, it was determined that the presence of Cu is

Chapter Radiation Effects in Metals:Hardening

Swelling and irradiation creep are considered in the following chapter. Radiation hardening usually means the increase in the yield stress and the ultimate tensile stres as a function of fast-neutron fluence and temperature. The yield strength and ultimate strength are measured in tests in which Corrosion Test of 304 Stainless Steel in Hydrazine and The corrosion tests of 304 stainless steels in 2 mmol dm 3 methanol solution and 2 mmol dm 3 hydrazine solution at 320 °C were carried out under -ray irradiation, and the corrosion environment was evaluated. Electrochemical corrosion potential (ECP) of the stainless steels was measured during the immersion tests.

Dislocation Loop - an overview ScienceDirect Topics

Irradiation dose effects on measured tensile yield strength for several 300 series stainless steels, irradiated and tested at a temperature of about 300°C (from ref. Effect of irradiation on steels used in pressure vessels In exploratory studies using in-reactor tests on A.302B steel, Hawthorne and Steele1 have shown no significant effects of irradiation with strain amplitudes of 4 - 8 x 1 0 " 3 and neutron doses up to 101 9 n/sq. cm ( > 1 MeV).

Effects of neutron irradiation on the creep-rupture

The effects of irradiation in the Dounreay Fast Reactor and the Dounreay Materials Testing Reactor on the creep-rupture properties of Type 316 stainless-steel tubing have been investigated. DFR irradiation produced a loss of rupture ductility but, in general, no change in creep strength in 650 deg C biaxial tests of solution-treated material. Effects of neutron-irradiation-induced intergranular Sep 01, 2008 · The neutron irradiation affects the DBTT (T 41J) defined at an absorbed energy of 41 J in the CVN impact tests , , differently depending on the composition of the steel with regard to levels of P, Cu and Ni . The PH steel, and the PL and B steels show the strongest and weakest effects of irradiation on the DBTT, respectively, and the other

Effects of neutron-irradiation-induced intergranular

Sep 01, 2008 · The neutron irradiation affects the DBTT (T 41J) defined at an absorbed energy of 41 J in the CVN impact tests , , differently depending on the composition of the steel with regard to levels of P, Cu and Ni . The PH steel, and the PL and B steels show the strongest and weakest effects of irradiation on the DBTT, respectively, and the other steels show intermediate behavior. Embrittlement of steels - TEC EurolabEmbrittlement of steels, Strain-age embrittlement. Most susceptible to the phenomenon of strain-age embrittlement are low-carbon rimmed or capped steels that are severely cold worked during forming processes. Subsequent moderate heating during manufacture (as in galvanizing, enameling, or paint baking) or aging at ambient temperature during service may cause embrittlement., 20201126

Ferritic/Martensitic Steel - an overview ScienceDirect

Investigations of several Cr Mo steels have demonstrated that the degree of embrittlement is considerable and is a matter for serious concern. Irradiation of 12Cr1MoVW steel in a fast-flux test facility (FFTF) to 10 and 17 dpa at 365 °C confirmed the saturation effect under fast reactor irradiation. High Flux Test Module IFMIF/EVEDAThe irradiation of small specimens is planned at several blanket-relevant irradiation temperatures and shall accumulate structural damage of up to 150 NRT dpa. The HFTM will allow the irradiation and the temperature control of the specimens by an active cooling system of He gas. The HFTM is mainly dedicated to the research on RAFM steels

High Flux Test Module IFMIF/EVEDA

The irradiation of small specimens is planned at several blanket-relevant irradiation temperatures and shall accumulate structural damage of up to 150 NRT dpa. The HFTM will allow the irradiation and the temperature control of the specimens by an active cooling system of He gas. The HFTM is mainly dedicated to the research on RAFM steels IRRADIATION TESTS OF SEVERAL STEELS FOR REACTOR irradiation test of several steels for reactor pressure vessels. Technical Report Masayoshi, H NEUTRON IRRADIATION TEST ON REACTOR PRESSURE VESSEL STEEL (A302B STEEL

IRRADIATION-ASSISTED STRESS CORROSION

Irradiation-assisted stress corrosion cracking (IASCC) of several types of BWR field components fabricated from solution-annealed austenitic stainless steels (SSs) , including a core internal weld, were investigated by means of slow-strain-rate test (SSRT), scanning In Situ Micropillar Compression Tests of 304 Stainless Mar 26, 2020 · A study was conducted to better understand the roles of irradiation defects and cavities on the mechanical properties of 304 stainless steel. Micropillars were fabricated using focused ion beam techniques, and pillars were heat treated at 300°C to serve as a control, irradiated in situ to 5 dpa with 1 MeV krypton ions at 300°C, or pre-implanted with a specific amount of helium and then

Industry Practice for the Neutron Irradiation

Jul 09, 2010 · Neutron irradiation embrittlement of reactor pressure vessel steels (RPVs) is one of the important material aging issues. In Japan, almost 40 years have past since the first plant started its commercial operation, and several plants are expected to become beyond 40 years old in Influence of Impurities and Alloying Elements on IASCC in Slow strain rate tests (SSRTs) and HNO 3 /Cr 6+ corrosion tests of several types stainless steels irradiated to 5.3×10 24 n/m 2 at about 573K, were conducted to evaluate the correlation between irradiation assisted stress corrosion cracking (IASCC) and radiation induced grain boundary segregation.. All the stainless steels tested failed intergranularly after neutron irradiation.

International Fusion Materials Irradiation Facility

The Test Facility will provide high, medium and low flux regions ranging from 20 dpa/full power year (fpy) to 1 dpa /fpy with increasingly available irradiating volumes of 0.5 l, 6 l and 8 l that will house different metallic and non-metallic materials potentially subjected to the different irradiation Irradiation Effects on Ferritic / Martensitic Steels A.Almazouzi and E.Lucom present results obtained from the irradiation campaign that has been performed in the BR2 reactor within the SPIRE project to assess the mechanical behavior of several standard 9-12%Cr steels. The irradiations have been performed up to 4.5 dpa at 200°C.

Irradiation Effects on Mechanical Properties of High

Several high-manganese austenitic steels and ferritic steels were studied by means of mechanical tests in order to develop materials for reduction of radioactivity of the first wall material after irradiation Irradiation Issues and Material Selection for Canadian Influence of Irradiation on the Creep/Fatigue Behavior of Several Austenitic Stainless Steels and Incoloy 800 at 700 C , ASTM International, West Conshohocken, PA, Standard No. STP 529

Irradiation performance of cladding and structural steels

As the standard cladding and duct material for the Fast Flux Test Facility driver fuel, 20% cold-worked 316 stainless steel has provided good service up to a fast fluence of 16 à 10²² n Irradiation, Annealing, and Reirradiation Effects on @article{osti_11010, title = {Irradiation, Annealing, and Reirradiation Effects on American and Russian Reactor Pressure Vessel Steels}, author = {Chernobaeva, A A and Korolev, Y N and Nanstad, R K and Nikolaev, Y A and Sokolov, M A}, abstractNote = {One of the options to mitigate the effects of irradiation on reactor pressure vessels (RPVs) is to thermally anneal them to restore the toughness

Irradiation-Assisted Stress Corrosion Cracking - an

3.6.3 Irradiation assisted stress corrosion cracking. Irradiation assisted stress corrosion cracking (IASCC) was observed in the early 1960s. It mainly affected stainless steel fuel element cladding, instrument tubes, control rod followers and other core devices or internals. The most important experience appeared in the early 1990s, mainly in the BWR recirculation loops and core shrouds, the Irradiation-assisted stress corrosion cracking of Irradiation-assisted stress corrosion cracking (IASCC) of several types of BWR field components fabricated from solution-annealed austenitic stainless steels (SSs), including a core internal weld, were investigated by means of slow-strain-rate test (SSRT), scanning electron microscopy (SEM), Auger electron spectroscopy (AES), and field-emission-gun advanced analytical electron microscopy (FEG

Micromechanical testing of unirradiated and helium ion

Oct 07, 2020 · It is possible that the discrepancy between irradiation hardening measured in this work on 0.6 dpa He 2+ room temperature irradiated HIP SA508 grade 3 steel (hardening of 727.7 ± 72.5 MPa) with previous works [60,61] reporting on 0.6 dpa neutron irradiated RPV steels (hardening of 500 MPa), may be induced by the use of microtensile testing Microstructural evolution of type 304 and 316 stainless @article{osti_1236587, title = {Microstructural evolution of type 304 and 316 stainless steels under neutron irradiation at LWR relevant conditions}, author = {Tan, Lizhen and Stoller, Roger E. and Field, Kevin G. and Yang, Ying and Morgan, Dane and Wirth, Brian D. and Gussev, Maxim N. and Busby, Jeremy T. and Nam, H.}, abstractNote = {Extension of light water reactors' useful life will expose

NUREG/CR-6897 'Assessment of Void Swelling in

NUREG-series reports will address irradiation embrittlement in cast and wrought stainless steels (SSs), as well as the development and application of models for predicting the effects of irradiation. Void swelling results from the agglomeration of microscopically small voids (or vacancies) produced during neutron irradiation. STP457 Irradiation Effects in Structural Alloys for Irradiation Tests of Several Steels for Reactor Pressure Vessels. Initial Assessments of Notch Ductility Behavior of A533 Pressure Vessel Steel with Neutron Irradiation. Notch Ductility, Tensile and Neutron Spectrum Analyses of PM-2A Reactor Pressure Vessel. Irradiation Effects in Pressure Vessel Materials for Steam-Cooled Fast Reactors

Slow Strain Rate Tensile Tests of Irradiated Austenitic

Irradiation-assisted stress corrosion cracking is of concern for the safe and economic operation of light water reactors. In this study, cracking susceptibility of austenitic stainless steels was investigated by using slow strain rate tensile (SSRT) tests in a simulated pressurized water reactor (PWR) environment. Steel - Application BritannicaSteel - Steel - Application:The many applications of steel demonstrate best the great versatility of this material. Most often, steel consumers needs are met by carbon steels. Good examples are sheets for deep-drawn automobile bodies and appliances made of low-carbon steels, medium-carbon structural steels and plates employed in all kinds of construction, high-carbon railroad rails, and

Irradiation Tests of Several Steels for Reactor Pressure

The first trial irradiation tests of pressure vessel steels scheduled by the Steel Irradiation Joint Committee of Japan (SIJC) were begun in 1963 and completed in 1967. ASTM Specification A302 Grade B, modified A302B with nickel, HY-80, and several other domestic-made low-alloy high strength steels were selected.

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