Analysis of Irradiation Data for A302B and A533B

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Analysis of Irradiation Data for A302B and A533B#0183;Web viewWorkshop for Applied Nuclear Data Analysis.22-24 January 2019.Washington,DC.Damage Correlation Exposure vs.Material Damage in addition need to consider data from irradiation experiments using various charged particles .Correlation Parameters Change in yield stress in neutron irradiated A302B and A212B RPV steels.Understanding Pressure Vessel Steels An Atom Probe NEUTRON IRRADIATION Most of the early atom probe studies fo-cussed on Western pressure vessel steels.These steels have included an A302B plate and several A533B type steels and welds.Some typical compositions of these steels are given in Table 1.In addition to these steels,a ferriticbainitic 16MND5-type steel from the French surveillance Understanding Pressure Vessel Steels An Atom Probe NEUTRON IRRADIATION Most of the early atom probe studies fo-cussed on Western pressure vessel steels.These steels have included an A302B plate and several A533B type steels and welds.Some typical compositions of these steels are given in Table 1.In addition to these steels,a ferriticbainitic 16MND5-type steel from the French surveillance

Trend Curve Exposure Parameter Data Development and

Progress in these trend curve-data correlation analysis activities at HEDL is described.The exposure parameters of primary interest are those associated with the production of displaced atoms and helium in different PV steels,particularly,A302B,A533B,and A508.Temper Embrittlement of Pressure Vessel SteelsA302B 10 11 12 ATS D 13 14 A S A302B 15 16 A S A302B 17 18 A S A533A 19 20 A S A302C 2 22 A S A302C 23 24 A S A533B 25 26 A S A533B Introduction The development of economies in costs of material,fabrication,trans Analysis of Irradiation Data for A302B and A533B#173; portation and operation has promoted the use of alloy plate steels in in Analysis of Irradiation Data for A302B and A533B#173; creasingly close proximity to max Analysis of Irradiation Data for A302B and A533B#173; imum capability.Some results are removed in response to a notice of local law requirement.For more information,please see here.Previous123456NextCHARACTERIZATION OF IRRADIATED A533B PRESSUREThe effects of neutron irradiation on the microstructure of an A302B pressure vessel steel surveillance sample have been investigated by Miller et a1.[~.~1 The atom probe detected,for the first time,small copper-rich and phosphorus-rich regions,and the precipitation of small rod-shaped and spherical

Some results are removed in response to a notice of local law requirement.For more information,please see here.12345Next(PDF) CHARACTERIZATION OF IRRADIATED A533B

These precipitates have been observed in A302B plate [11] and A533B plate of these materials during neutron irradiation is presented. by APT analysis show that the number density of Cu Some results are removed in response to a notice of local law requirement.For more information,please see here.Reaction kinetic analysis of reactor surveillance data In reactor pressure vessel surveillance data,it was found that the concentration of matrix defects was very low even after nearly 40 years of operation,though a large number of precipitates existed.In this paper,defect structures obtained from surveillance data of A533B (high Cu concentration) were simulated using reaction kinetic analysis with 11 rate equations.

Reaction kinetic analysis of reactor surveillance data

In reactor pressure vessel surveillance data,it was found that the concentration of matrix defects was very low even after nearly 40 years of operation,though a large number of precipitates existed.In this paper,defect structures obtained from surveillance data of A533B (high Cu concentration) were simulated using reaction kinetic analysis with 11 rate equations.Ramberg-Osgood Strain-Hardening Characterization of an The strain-hardening exponent increases only slightly with temperature over this range,while the coefficient decreases with increasing temperature.Tensile specimens irradiated to 0.002,0.029,and 0.046 dpa exhibited significant increases in the strain-hardening exponent with increasing neutron irradiation level.OF IRRADIATION EFFECTS ON REACTOR YESStL STEELSN changes,it is applied to determine the status of steel samples used to study the basic mechanism of irradiation embrittle-V exposed to neutron irradiation.ment.Although these methods can provide valuable infor-Two commercial steels,A302B plate and A533B weld,and mation on radiation damage and an effective means to pre-

NED0-10115 .July

estimate of the radiation sensitivity of A302B/A5338 - Class I steel.The lower curve reflects the upper limit for GE 650 Analysis of Irradiation Data for A302B and A533B#176;F BWR operating experience.Note that the GE data include radiation effects on A3028/A533B -Class 1.weld and weld HAZ material as well base metal.Tabulated results of how the minimum pressure testMulticriteria materials selection for extreme operating Nov 11,2017 Analysis of Irradiation Data for A302B and A533B#0183;A methodology for evaluating different combinations of materials specifications for extreme environment applications is presented.This new approach addresses the materials selection problem using a multicriteria stringency level methodology that defines several thresholds obtained by analyzing different prediction models of irradiation embrittlement and hot cracking.Magnetic evaluation of irradiation hardening in A533B We report results of measurements of magnetic minor hysteresis loops for neutron-irradiated A533B nuclear reactor pressure vessel steels varying alloy composition and irradiation condition.A minor-loop coefficient,which is obtained from a scaling power law between minor-loop parameters exhibits a steep decrease just after irradiation,followed by a maximum in the intermediate fluence regime

Magnetic evaluation of irradiation hardening in A533B

We report results of measurements of magnetic minor hysteresis loops for neutron-irradiated A533B nuclear reactor pressure vessel steels varying alloy composition and irradiation condition.A minor-loop coefficient,which is obtained from a scaling power law between minor-loop parameters exhibits a steep decrease just after irradiation,followed by a maximum in the intermediate fluence regime Magnetic evaluation of irradiation hardening in A533B We report results of measurements of magnetic minor hysteresis loops for neutron-irradiated A533B nuclear reactor pressure vessel steels varying alloy composition and irradiation condition.A minor-loop coefficient,which is obtained from a scaling power law between minor-loop parameters exhibits a steep decrease just after irradiation,followed by a maximum in the intermediate fluence regime Information Fusion Technique for Evaluating Radiation Wang,J.A.,March 2000,Analysis of the Irradiated Data for A302B and A533B Correlation Monitor Materials, pp.5980 in Effect of Radiation on Materials 19th International Symposium ASTM STP 1366,ASTM,Philadelphia.

Factors controlling the irradiation embrittlement response

The first analysis of this type developed,and the most frequently quoted,is that due to Varsik and Byrne (ref.29),derived from data compilations for plates and weld metals of A533B and A302B.Compositional dependence is taken into account in terms of a chemistry relation (CR) formulated in terms of atomic % of copper and major alloying Evaluation of Irradiation Embrittlement of A508 Gr 4N and This trend also occurs for low copper A533B and A302B plate material.The irradiation temperature dependence of embrittlement in A508 Gr 4N is nearly the same as other low copper low-alloy steels tested over a wide range of temperatures.Evaluation of Irradiation Embrittlement of A508 Gr - COREIn contrast,the raw irradiation test data show that ASTM A508 Grade 4N containing up to 3.7% nickel,0.1% Cu and 0.01% P does not show enhanced irradiation embrittlement.A simple statistical fit to irradiation dose and irradiation temperature was developed to

Effect of radiation embrittlement to reactor pressure

Irradiation hardening Irradiation embrittlement High Ni A533B Ni~0.6% A508Bcl3 Ni~0.7% VVER-1000 weld seams up to Ni ~ 1.9% High Ni 11 Extended analysis of VVER-1000 surveillance data,Kryukov,Debarberis et al.,International Journal of Pressure Vessels and Piping,Vol.79,2002 EFFECT OF MATERIALS HETEROGENEITIES ONExamples of the effect of the irradiation on the intrinsic microstructure 18 RPV-steel analysis C Si Mn Cr Mo Ni P Cu V S 3JRQ57 (A533B Cl.1.) melt block 3JRQ57 0.18 0.15 0.24 0.24 1.42 1.20 0.12 0.13 0.51 0.47 0.84 0.81 0.017 0.016 0.14 0.13 0.002 0.004 0.004 0.004 SOTERIA Training School - September 2018 - Polytechnic University of ValenciaCited by 4Publish Year 1996Author J.A.WangAnalysis of Irradiation Data for A302B and A533B STP1366 Analysis of Irradiation Data for A302B and A533B Correlation Monitor Materials.Author Information Wang,JA Research Scientist,Oak Ridge National Laboratory,Oak Ridge,TN

Cited by 4Publish Year 1996Author J.A.WangAnalysis of Irradiation Data for A302B and A533B

In general,the embrittlement behavior of both the A302B and A533B-1 plate materials is similar.There is evidence for a flux effect in the CMM data irradiated in test reactors; thus its implication for power reactor surveillance programs deserves special attention.Cited by 4Publish Year 1996Author J.A.Wang(PDF) CHARACTERIZATION OF IRRADIATED A533BThese precipitates have been observed in A302B plate [11] and A533B plate of these materials during neutron irradiation is presented. by APT analysis show that the number density of Cu CHARACTERIZATION OF IRRADIATED A533B PRESSUREThe effects of neutron irradiation on the microstructure of an A302B pressure vessel steel surveillance sample have been investigated by Miller et a1.[~.~1 The atom probe detected,for the first time,small copper-rich and phosphorus-rich regions,and the precipitation of small rod-shaped and spherical

CHARACTERIZATION OF IRRADIATED A533B PRESSURE

The effects of neutron irradiation on the microstructure of an A302B pressure vessel steel surveillance sample have been investigated by Miller et a1.[~.~1 The atom probe detected,for the first time,small copper-rich and phosphorus-rich regions,and the precipitation of small rod-shaped and sphericalAnalysis of the irradiation data for A302B and A533B The results of Charpy V-notch impact tests for A302B and A533B-1 Correlation Monitor Materials (CMM) listed in the surveillance power reactor data base (PR-EDB) and material test reactor data base (TR-EDB) are analyzed.The shift of the transition temperature at 30 ft-lb (T{sub 30}) is considered as the primary measure of radiation embrittlement in this report.Analysis of the irradiation data for A302B and A533B In general the embrittlement behavior of both the A302B and A533B-1 plate materials is similar.There is evidence for a fluence-rate effect in the CMM data irradiated in test reactors; thus its implication on power reactor surveillance programs deserves special attention

Analysis of the irradiation data for A302B and A533B

In general the embrittlement behavior of both the A302B and A533B-1 plate materials is similar.There is evidence for a fluence-rate effect in the CMM data irradiated in test reactors; thus its implication on power reactor surveillance programs deserves special attentionAnalysis of the irradiation data for A302B and A533B In general the embrittlement behavior of both the A302B and A533B-1 plate materials is similar.There is evidence for a fluence-rate effect in the CMM data irradiated in test reactors; thus its implication on power reactor surveillance programs deserves special attentionAnalysis of the irradiation data for A302B and A533B @article{osti_233376,title = {Analysis of the irradiation data for A302B and A533B correlation monitor materials},author = {Wang,J A},abstractNote = {The results of Charpy V-notch impact tests for A302B and A533B-1 Correlation Monitor Materials (CMM) listed in the surveillance power reactor data base (PR-EDB) and material test reactor data

A COMPREHENSIVE STUDY OF RELATIONSHIP BETWEEN

The results were explained by a model analysis assuming Avrami-type growth A302B 0.14 0.20 1.20 0.24 0.60 0.015 0.21 0.28 data for LD alloy before irradiation is shown.For each minor loop measured in various alloy-irradiation condi-tions,parameters were obtained according to the defini- A COMPREHENSIVE STUDY OF RELATIONSHIP BETWEENThe results were explained by a model analysis assuming Avrami-type growth A302B 0.14 0.20 1.20 0.24 0.60 0.015 0.21 0.28 data for LD alloy before irradiation is shown.For each minor loop measured in various alloy-irradiation condi-tions,parameters were obtained according to the defini- 2067-3 Joint ICTP/IAEA Workshop on IrradiationA533B class 1 subarc weld A533B class 1 weld A533B weld HAZ A533B class 1 HSST-01 HSST-02 HSST-03 A508 class 2 A508 class 2 A508 class 2 1:1 RT Tois not correlated with RT NDT RT Toappropriately bounds available data (thats why 35oF) 0 50 100 150 200-250 -150 -50 50 150 Temperature [oF] K Jc [ksi*in 0.5] 0F 20F 40F 60F 80F [Sokolov,1996

2067-3 Joint ICTP/IAEA Workshop on Irradiation

A533B class 1 subarc weld A533B class 1 weld A533B weld HAZ A533B class 1 HSST-01 HSST-02 HSST-03 A508 class 2 A508 class 2 A508 class 2 1:1 RT Tois not correlated with RT NDT RT Toappropriately bounds available data (thats why 35oF) 0 50 100 150 200-250 -150 -50 50 150 Temperature [oF] K Jc [ksi*in 0.5] 0F 20F 40F 60F 80F [Sokolov,1996 (PDF) The Effect of Neutron Flux on Radiation-Induced The results of Charpy V-notch impact tests for A302B and A533B-1 Correlation Monitor Materials (CMM) listed in the surveillance power reactor database (PR-EDB) and material test reactor database

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