... and for the as-produced materials of commercial heat treatment. zirconium alloys Zircaloy-2 nuclear fuel cladding microstructure heat treatment solubility matrix composition irradiation radiation damage atom probe tomography ZIRCONIUM IN THE NUCLEAR INDUSTRY: 20TH INTERNATIONAL SYMPOSIUM 149 STP 1645...

... A review is presented of work performed in our group over the years in the areas of radiation damage, corrosion, hydrogen pickup, hydriding, and the mechanical behavior of zirconium alloy nuclear fuel cladding with the goal of developing a greater mechanistic understanding of cladding...

... of the bubble size distribution. Possible reasons for this observation are discussed. helium bubbles radiation damage transmission electron microscopy Effects of Radiation on Nuclear Materials: 25th Volume STP 1547, 2012 Available online at www.astm.org DOI:10.1520/STP103972 E. Gaganidze,1 C...

... of the radiation damage that forms in Zr alloys will be illustrated and discussed in terms of the dose, dose rate, and impurity factors that are applicable. The original paper was published by ASTM International in the Journal of ASTM International , December 2007. zirconium irradiation fast neutron flux...

... of the radiation damage that forms in Zr alloys will be illustrated and discussed in terms of the dose, dose rate, and impurity factors that are applicable. zirconium irradiation fast neutron flux dpa radiation damage point defects vacancy interstitial dislocation loops cavities climb M. Grif...

...). The microstructure and mechanical properties change significantly in the transition from the unirradiated state up to fluxes of about 1×10 17 n·m −2 ·s −1 . zirconium irradiation thermal creep deformation strain fast neutron flux radiation damage point defects vacancy interstitial dislocation loops...

... that act as barriers to slip. Experimental evidence from Zircaloy-2 samples irradiated at 70°C suggests that the increase in critical resolved yield stress due to irradiation is lower for basal compared with prism planes. zirconium irradiation radiation damage dislocations anisotropy tensile...

... embrittlement information fusion radiation damage J. A. Wang,1,2 N. S. V. Rao,1 and S. Konduri1 Journal of ASTM International, Vol. 4, No. 7 Paper ID JAI100681 Available online at www.astm.org Information Fusion Embrittlement Models for U.S. Power Reactor Pressure Vessel Steels ABSTRACT: A new approach...

.... The present paper intends to highlight the most important achievements and results of this research activity. multiscale modelling radiation damage FeCr alloys Journal of ASTM International, Vol. 4, No. 6 Paper ID JAI100692 Available online at www.astm.org L. Malerba,1 D. A. Terentyev,1 G. Bonny,1...

..., irradiation induced vacancy clusters and loops, precipitates and precipitate-matrix interfaces, etc., are utilized to monitor the influx of point defects, particularly those of interstitials nature. Some of the reanalysis of the former results will be presented. radiation damage cascade ion...

... sample, and the other was untested. The influence of the defect microstructure on the deformation and fracture behavior is evaluated and results are discussed in light of current theories of deformation behavior in irradiated metals. austenitic stainless steels radiation damage microstructure...

... simulation displacement cascade radiation damage stacking fault tetrahedron dislocation loop high dose irradiation Journal of ASTM International, September 2005, Vol. 2, No. 8 Paper ID JAI12419 Available online at www.astm.org Roman E. Voskoboinikov, Ph.D.,1 Yuri N. Osetsky, Ph.D.,2 and David J...

... of only one type can glide in one dimension only. We have also performed separate MD simulations of some SIA and vacancy clusters to study their thermal stability and possible transformations. Computer simulation displacement cascade radiation damage point defect cluster dislocation loop...

... the length, and this is a result of cooling of the tube during the extrusion process. During service in a nuclear reactor, the microstructure evolves further, and this additional change in microstructure is primarily dependent on the rate of radiation damage (determined by the fast neutron flux...

... are consistent with a modest effect of flux on embrittlement for fluxes near those typical of commercial RPVs. neutron flux embrittlement ferritic steels modeling point defects pressure vessels radiation damage Journal of ASTM International, April 2004, Vol. 1, No. 4 Paper ID JAil 1355 Available...

... activation ferritic/martensitic steels are reviewed in order to identify the key elements to hardening mechanisms. ferritic/martensitic steels hardening radiation damage microstructure Nadine Baluc, 1Robin Schaublin,1 Philippe Spatig, ~and Max Victoria1 Hardening Mechanisms in Ferritic...

... absorption. Irradiation dose rate and temperature also affect the duration of incubation. These features are in general agreement with experiments for high purity metals. voids swelling stainless steels dislocations radiation damage Michael P. Surh, ~J. B. Sturgeon,1and W. G. Wolfer1 Incubation...

..., and in-reactor deformation. Zr-2.5Nb pressure tubes zirconium alloys nuclear reactor materials mechanical properties yield stress ultimate tensile strength total elongation delayed-hydride-cracking neutron irradiation radiation damage microstructure correlation X-ray diffraction line...

... platform constructed from molybdenum foil rings. radiation damage tensile test jig sub-size TEM pieces plastic deformation maps strain localization Kenneth Farrell, ~Thak Sang Byun,1J. Wade Jones, 1Loy T. Gibson,z Robert. G. Sitterson,l Naoyuki Hashimoto,l JeffL. Bailey,l and M. Janie GardnerI...

... The JENDL PKA/KERMA File is prepared from the evaluated nuclear data file, for radiation damage calculations used to support programs such as the International Fusion Material Irradiation Facility (IFMIF). The file contains primary knock-on atom (PKA) spectra, KERMA factors and displacement-per...