Effects of Radiation on Materials: 18th International Symposium, Issue 1325R. K. Nanstad |
Contents
THE ROLE OF THERMAL NEUTRONS AND BORON | 3 |
THE IMPACT OF MOBILE POINT DEFECT CLUSTERS IN A KINETIC MODEL OF PRESSURE VESSEL EMBRITTLEMENT | 14 |
AN ANALYSIS OF RADIATION EFFECTS IN MODEL A533B PRESSURE VESSEL STEELS CONTAINING COPPER PHOSPHORUS AND NICK... | 30 |
AN ASSESSMENT OF POTENTIAL GAMMA RAY ENHANCEMENT OF EMBRITTLEMENT IN ABWR PRESSURE VESSEL WALLS | 52 |
DYNAMIC FINITE ELEMENT MODELING OF THE UPPER SHELF ENERGY OF PRECRACKED CHARPY SPECIMENS OF NEUTRON IRRAD... | 75 |
IMPLICATIONS TO LOW FLUX IRRADIATION EMBRITTLEMENT | 88 |
SMALL ANGLE NEUTRON SCATTERING STUDY OF LINDE 80 RPV WELDS | 102 |
EVALUATION OF VARIABILITY IN MATERIAL PROPERTIES AND CHEMICAL COMPOSITION FOR MIDLAND REACTOR WELD WF70 | 123 |
DETECTION OF IRRADIATION EMBRITTLEMENT OF LOWALLOY STEEL FOR NUCLEAR REACTOR PRESSURE VESSELS USING A PRO... | 601 |
THE EFFECT OF ORDERING ON RADIATIONINDUCED SEGREGATION IN AUSTENITIC IRON AND NICKELBASE ALLOYS | 619 |
THE MODELLING OF COMBINED RADIATIONINDUCED AND THERMAL NONEQUILIBRIUM SEGREGATION OF CHROMIUM IN NEUTR... | 634 |
RADIATIONINDUCED INSTABILITY OF MnS PRECIPITATES AND ITS POSSIBLE CONSEQUENCES ON IRRADIATIONINDUCED STRESS ... | 647 |
TENSILE PROPERTIES OF A TITANIUM MODIFIED AUSTENITIC STAINLESS STEEL AND THE WELD JOINTS AFTER NEUTRON IRRADI... | 659 |
TEMPERATURE DEPENDENCE OF THE DEFORMATION BEHAVIOR OF TYPE 316 STAINLESS STEEL AFTER LOW TEMPERATURE NEU... | 671 |
MICROSTRUCTURES IN NEUTRON IRRADIATED FeCrNiPTi MODEL AUSTENITIC ALLOYS DOPED WITH 10B | 689 |
BEHAVIOR OF FeCrNixPyTi ALLOYS UNDER ELECTRON He ION DUAL BEAM IRRADIATION | 701 |
FRACTURE TOUGHNESS TESTING OF LINDE 1092 REACTOR VESSEL WELDS IN THE TRANSITION RANGE USING CHARPYSIZED SPE... | 157 |
COMPARISON OF IRRADIATIONINDUCED SHIFTS OF Kjc AND CHARPY IMPACT TOUGHNESS FOR REACTOR PRESSURE VESSEL STEE... | 167 |
MINIATURIZED CHARPY TEST FOR REACTOR PRESSURE VESSEL EMBRITTLEMENT CHARACTERIZATION2 | 191 |
USE OF FORCES FROM INSTRUMENTED CHARPY VNOTCH TESTING TO DETERMINE CRACKARREST TOUGHNESS | 204 |
THE DUCTILEBRITTLE TRANSITION BEHAVIOUR OF SUBMERGEDARC WELDMENTS FOLLOWING HIGH TEMPERATURE EXPOSURE | 223 |
IRRADIATION OF VESSEL MATERIALS USING KORPUS FACILITY OF RBT6 REACTOR | 233 |
AUGER SPECTROSCOPY OF MAGNOX PRESSURE VESSEL STEELS | 247 |
PHOSPHORUS FREE ENERGY CHANGE ASSOCIATED WITH SEGREGATION TO GRAIN BOUNDARIES IN SUBMERGEDARC WELDS | 260 |
IRRADIATION EMBRITTLEMENT OF REACTOR PRESSURE VESSEL STEELS DUE TO MECHANISMS OTHER THAN RADIATION HARDE... | 271 |
TEMPER EMBRITTLEMENT IRRADIATION INDUCED PHOSPHORUS SEGREGATION AND IMPLICATIONS FOR POSTIRRADIATION ANN... | 296 |
THE EFFECT OF HEAT TREATMENT ON PHOSPHORUS SEGREGATION IN A SUBMERGEDARC WELD METAL | 317 |
SANS STUDY OF HIGHCOPPER RPV WELDS IN IRRADIATED AND ANNEALED CONDITIONS | 333 |
INVESTIGATION OF THE DEVELOPMENT OF IRRADIATION INDUCED PRECIPITATES IN VVER440TYPE REACTOR PRESSURE VESSE... | 346 |
HARDNESS AND MICROSTRUCTURAL RESPONSE TO THERMAL ANNEALING OF IRRADIATED ASTM A533B CLASS 1 PLATE STEEL | 363 |
EFFECTS OF DAMAGE RATE ON IRRADIATION HARDENING AND POSTIRRADIATION ANNEALING CHARACTERISTICS OF CARBON S... | 379 |
EXPERIMENTAL TESTS OF IRRADIATIONANNEALREIRRADIATION EFFECTS ON MECHANICAL PROPERTIES OF RPV PLATE AND WE... | 388 |
COMPARISON OF DIFFERENT EXPERIMENTAL AND ANALYTICAL MEASURES OF THE THERMAL ANNEALING RESPONSE OF NEUTR... | 403 |
THE ANNEALING RECOVERY OF THE PALISADES NUCLEAR POWER PLANT SURVEILLANCE MATERIAL USING WELD RECONSTITU... | 421 |
DESIGN OF AN ANNEALING SUPPLEMENTAL SURVEILLANCE PROGRAM FOR THE PALISADES REACTOR PRESSURE VESSEL | 441 |
COMPARISON OF BR3 SURVEILLANCE AND VESSEL PLATES TO THE SURROGATE PLATES REPRESENTATIVE OF THE YANKEE ROW... | 452 |
ROLE AND EXPERIENCE WITH THERMAL MONITORS IN REACTOR VESSEL SURVEILLANCE CAPSULES | 485 |
A CONSIDERATION OF SCATTER IN RADIATION DAMAGE TREND CURVES FOR REACTOR PRESSURE VESSEL STEEL PLATE MATERI... | 500 |
REFINEMENTS TO PRESSURE VESSEL STEEL EMBRITTLEMENT CORRELATIONS | 508 |
DEVELOPMENT OF EMBRITTLEMENT PREDICTION MODELS FOR US POWER REACTORS AND THE IMPACT OF THE HEATAFFECTED ... | 525 |
EMPIRICAL CORRELATION OF OBSERVED THREE STAGES OF FAST NEUTRON IRRADIATION HARDENING AND EMBRITTLEMENT IN... | 541 |
EVALUATION OF IRRADIATED PRESSURE VESSEL STEEL BY MECHANICAL TESTS AND POSITRON ANNIHILATION LINESHAPE ANA... | 559 |
DETECTION OF RADIATION DAMAGE IN LOW ALLOY STEEL USING A SQUID SENSOR | 568 |
NONDESTRUCTIVE EVALUATION OF NEUTRON IRRADIATION EMBRITTLEMENT FOR REACTOR VESSEL STEEL BY MAGNETOMECH... | 576 |
CHANGES IN ELECTROMAGNETIC PROPERTIES OF A LOWALLOY STEEL CAUSED BY NEUTRON IRRADIATION | 589 |
COMPARISON OF IRRADIATION CREEP AND SWELLING OF AN AUSTENITIC ALLOY IRRADIATED IN FFTF AND PFR | 713 |
IRRADIATION CREEP AT TEMPERATURES OF 400C AND BELOW FOR APPLICATION TO NEARTERM FUSION DEVICES | 725 |
IRRADIATION CREEP IN NICKEL CONTAINING AND IN MANGANESE CONTAINING STAINLESS STEEL ALLOYS | 742 |
VARIABILITY OF IRRADIATION CREEP AND SWELLING OF HT9 IRRADIATED TO HIGH NEUTRON FLUENCE AT 400600C | 765 |
EVALUATION OF LOWTEMPERATURE SWELLING IN AUSTENITIC STAINLESS STEELS | 783 |
A REEVALUATION OF HELIUMDPA AND HYDROGENDPA RATIOS FOR FAST REACTOR AND THERMAL REACTOR DATA USED IN FIS... | 794 |
THE EFFECTS OF PHASE STABILITY ON VOID SWELLING IN PTi MODIFIED 316 STAINLESS STEELS DURING NEUTRON IRRADIATION | 808 |
THE DEPENDENCE OF SWELLING ON PHOSPHORUS CONTENT IN STAINLESS STEELS CONTAINING HIGH SILICON LEVELS | 822 |
NEUTRON IRRADIATION CREEP AT 100C ON 316L AMCR AND WELDED 316L STAINLESS STEEL ALLOYS | 830 |
EFFECT OF RADIATIONINDUCED SEGREGATION ON PRECIPITATE STABILITY AND SWELLING IN IRRADIATED ALLOYS | 850 |
MICROSTRUCTURAL AND MICROCHEMICAL CHARACTERISATION OF FERRITIC EXSERVICE MAGNOX CONTROL ROD SHEATH MAT... | 869 |
BEHAVIOR OF AN OXIDE DISPERSION STRENGTHENED FERRITIC STEEL IRRADIATED IN PHENIX | 882 |
THE CONSEQUENCES OF HELIUM PRODUCTION AND NICKEL ADDITIONS ON MICROSTRUCTURAL DEVELOPMENT IN ISOTOPICALL... | 899 |
TENSILE AND CHARPY IMPACT PROPERTIES OF IRRADIATED REDUCEDACTIVATION FERRITIC STEELS | 911 |
IMPACT BEHAVIOR OF LOW ACTIVATION STEELS AT 30 DPA | 931 |
ELECTRON MICROSCOPY OF PRECIPITATION AND AGE HARDENING IN Fe06Cu MODEL ALLOY | 945 |
THE EFFECT OF NEUTRON IRRADIATION AND TRANSMUTATION ON BOND INTEGRITY | 973 |
VOID SWELLING OF COPPER AND COPPER ALLOYS INDUCED BY HEAVY ION IRRADIATION | 991 |
RADIATIONENHANCED DIFFUSION OF 63NI IN NICKEL AND IN COPPER | 999 |
THE EFFECTS OF IRRADIATION ON THE MECHANICAL PROPERTIES OF 6061T651 ALUMINUM BASE METAL AND WELDMENTS | 1027 |
IRRADIATION INDUCED GROWTH AND MICROSTRUCTURE EVOLUTION OF Zr12Sn1Nb04Fe UNDER NEUTRON IRRADIATION TO HIG... | 1045 |
THE NEUTRON IRRADIATION EFFECT ON THE MECHANICAL PROPERTIES AND STRUCTURE OF BERYLLIUM | 1062 |
INSITU RADIOLUMINESCENCE FROM SAPPHIRES UNDER FISSION REACTOR IRRADIATION | 1077 |
THE EFFECTS OF CONSTRAINT LOADING RATE AND IRRADIATION ON THE TOUGHNESSTEMPERATURE BEHAVIOR OF A V4Cr4Ti A... | 1088 |
EFFECTS OF HELIUM ON VOID SWELLING BEHAVIOR OF VANADIUM ALLOYS USING DUAL ION BEAM IRRADIATION | 1109 |
EFFECTS OF LOW TEMPERATURE IRRADIATION ON THE MECHANICAL PROPERTIES OF V4Cr4Ti | 1119 |
AUTHOR INDEX | 1135 |
| 1139 | |
Common terms and phrases
A. S. Kumar ABWR alloys AMCR American Society annealing ASTM International ASTM STP atoms austenitic base metal calculated capsules Charpy impact Charpy impact tests Charpy specimens chromium clusters composition correlation curve damage DBTT decrease diffusion dislocation Effects of Radiation electron embrittlement experimental F. A. Garner fast neutron ferritic Figure flux fracture toughness ft-lb grain boundary hardening helium HFIR increase interstitial irradiation creep irradiation temperature Journal of Nuclear Magnox matrix measured mechanism microstructure n/cm² n/m² neutron fluence neutron irradiation nickel Nuclear Materials number density Oak Ridge observed phosphorus plate point defects predicted Pressure Vessel Steels R. K. Nanstad Radiation on Materials radiation-induced Reactor Pressure Vessel reactor vessel recovery samples scattering segregation Society for Testing stainless steel surveillance swelling Table tensile Testing and Materials thermal ageing thermal neutron unirradiated upper shelf energy vacancy values void weld metal yield strength yield stress