... for steels irradiated in both types of reactors. However, hardening of steel irradiated in the fast reactor is higher than hardening in the thermal reactor under the same irradiation conditions (280–300 °C, 7–9 dpa). austenitic stainless steels neutron irradiation VVER reactors swelling...

... The relationship between the addition of minor element and the swelling behavior was investigated using six heats of Fe-15Cr-20Ni austenitic model alloys and a PNC 1520 steel irradiated at 480, 570, 620 and 700°C in the Joyo to doses of 20–56 dpa. Phosphorus and boron suppressed the appearance...

... in the BN-350. The elastic moduli of both steels are reduced and the electrical resistance is increased as the neutron dose and resultant swelling increase. Dependencies of these changes in physical properties on neutron irradiation dose, temperature, and swelling level are plotted and it is shown...

... Void swelling in structural materials used for nuclear reactors is characterized by an incubation period whose duration largely determines the utility of the material for core components. Significant evolution of the dislocation and void microstructures that control radiation-induced swelling...

... Recent studies associated with light water reactors (LWR) in both the USA and Russia have raised the question of void swelling in austenitic components of core internals. One question of particular interest is the range of temperatures over which voids can develop, especially the lowest...

... The experimental data comprising more than 1800 data points on swelling of fuel pin cladding specimens of cold worked austenitic steel 16Cr-15Ni-2Mo-1Mn irradiated in the BN-600 reactor are described by the equation S = R s ∙(D-D 0 )∙(1-exp(-p(D-D 0 ))) . Where S = swelling; D = damage dose...

... at the stress and temperature dependence of creep at low swelling for selected 316 stainless steels and HT9 steels irradiated at temperatures from 400–670°C. Analysis of the creep data has revealed that a transition from a lower creep rate with a stress exponent of one to a higher creep rate with an unknown...

... creep and swelling of EP-450 and EP-852 at temperatures between 305–335°C and doses ranging from 61–89 dpa are presented. Where comparisons are possible, it appears that these steels exhibit behavior that is very consistent with that of Western steels. Swelling is relatively low at high neutron exposure...

... The measured irradiation creep strain ε in structural materials is usually fitted with the equation: E/σ B 0 dpa+DS, where σ is the applied stress, S the void swelling, and B 0 and D are the material parameters. The stress dependence of swelling is sometimes described using the equation...

... Swelling behavior and microstructural evolution of 12% cold-worked 316 SS hexagonal ducts following irradiation in the outer rows of EBR-II is described. Immersion density measurements and transmission electron microscopy (TEM) examination were performed on a total of seven irradiation...

... The difference in swelling behavior of P, Ti-modified 316 stainless steel (PNC316) between sample irradiation using material irradiation vehicle (e.g. FFTF/MOTA) and fuel assembly irradiation in FBR was investigated. From the evaluation of the dose dependence in the swelling of PNC316...

... Swelling and microstructure of silicon carbide (SiC) are studied by means of MeV-range ion irradiation. The material used is chemical vapor deposited high purity polycrystalline cubic (3C)-SiC. The swelling behavior is characterized by precision interferometric profilometry following ion...

...-Permeation Cup Method ,” are widely used to evaluate the chemical resistance of protective clothing materials. However, these techniques are not well adapted to solvents of low volatility. In this study, the chemical resistance of protective materials to solvents was investigated with volumetric and swelling...

... The irradiation-induced creep and swelling of annealed 16Cr-15Ni-3Mo-Nb stainless steels with different contents of carbon and boron in BOR-60 at 420°C have been investigated to exposures of 100 dpa. Swelling depends on carbon content and boron. The creep rate directly depends on stress...

... In comparing results of irradiation creep experiments conducted by researchers in France and those by researchers at Pacific Northwest National Laboratory in the United States, quite different values for the creep-swelling coupling coefficient were reported. The differing coefficients...

... The relationship between swelling and irradiation creep was investigated using eight sets of pressurized tubes, representing two heats of 20% cold-worked 316 stainless steel irradiated at either 550°C, 575°C, 600°C, and 670°C in the FFTF-MOTA to doses of 79–84 dpa. After reaching these exposures...

... Irradiation creep and void swelling are important damage processes for stainless steels when subjected to neutron irradiation at elevated temperatures. To date, most published data of this type have been derived from steels prepared by various Western nations and Japan. This paper describes...

... Irradiation of thin metallic foils in a High Voltage Electron Microscope (HVEM) has been widely used for investigating void swelling. One of the observations in HVEM experiments is the formation of void denuded zones in foils prepared from metals and alloys preconditioned by neutron irradiation...

... A pressurized tube experiment was carried out in the British Prototype Fast Reactor (PFR) at Dounreay, U.K. in order to determine swelling and stress-induced swelling of four heats of the commercial German austenitic steel DIN 1.4970, with different contents of the minor alloying elements Si, Ti...

... Evidence has been provided to support the “temperature-shift” concept of swelling. The swelling of annealed X18H10T stainless steel in the BOR-60 fast reactor at PWR-relevant dpa rates was found to be higher than predicted by a swelling equation developed from data obtained at dpa rates almost...