.... Depending on the amount of hydrogen, as well as the temperature and deformation rate, different embrittlement mechanisms can be active in the material. As long-term dry storage of spent nuclear fuel becomes increasingly prevalent, the study of hydrogen's effects on cladding materials becomes crucially...

... A review of long-term thermal aging data from reactor pressure vessel steels shows that the main aging mechanism is embrittlement from phosphorus segregation to grain boundaries. Some softening can be seen in lightly tempered steels or hardening in high-copper steels. An investigation of data...

... beyond. Traditionally, the effect has been coupled to the nonhardening effects caused by phosphorus and sulphur diffusion to available phase or grain boundaries, or both, resulting in a marked embrittlement of these low-alloy steels. This phosphorus segregation is proposed to be the main embrittlement...

... to this document. zirconium texture anisotropy hydrogen embrittlement solubility diffusion coefficients thermal-diffusion KROLL PAPERS ZIRCONIUM IN THE NUCLEAR INDUSTRY: 17TH INTERNATIONAL SYMPOSIUM 3 STP 1543, 2015 / available online at www.astm.org / doi: 10.1520/STP154320120216 J. J. Kearns1...

... The aim of this publication is to contribute to the recent research and development efforts on mitigation of the reactor pressure vessel (RPV) embrittlement for operational lifetime extension. This research was done in the framework of the PRIMAVERA international project and it was focused...

... of 1 and 0.7 mm respectively. Inconel X-750 embrittlement irradiation AUSTENITIC STEELS, Ni, Zr, AND Al-Mg ALLOYS, AND POLYETHYLENE Effects of Radiation on Nuclear Materials: 25th Volume STP 1547, 2012 Available online at www.astm.org DOI:10.1520/STP104242 C. D. Judge,1 M. Griffiths,1 L...

... in irradiated cladding materials with susceptible microstructures and under various deformation rates. cladding high burnup Zircaloy-4 hydrides hydride rim reorientation radial hydride oxide finite element modeling ring compression embrittlement ductility Journal of ASTM International, Vol...

... A study on phosphorus (P) segregation at grain boundaries and intergranular embrittlement of reactor pressure vessel steels due to thermal aging and neutron irradiation has been performed for A533B steel plates and weld metals doped with different bulk levels of P. The initial P concentration...

... embrittlement type 316 stainless steels tensile properties low-strain-rate lower dose rate irradiation EBR-II reflector duct fast reactor core materials Journal of ASTM International, March 2005, Vol. 2, No. 3 Paper ID JAI12346 Available online at www.astm.org Tsunemitsu Yoshitake,1 Ichiro Yamagata,1...

... power reactor to three different dose levels, maximally 0.14 dpa, at an irradiation temperature of 255°C. The volume content of the micostructural features measured is correlated with the irradiation hardening and embrittlement. In every case clear radiation-related hardening, embrittlement...

... techniques. The corrosion level of irradiated specimens reached up to 130 μm of oxide layer thickness. The influence of in-pile oxide layer spallation has also been addressed. High strain-rate material properties of irradiated Zircaloy-4 and the consequences of hydride embrittlement can be derived from...

... for representative times of LOCA transient (1800 s). (3) Oxygen has the most important effect in embrittlement of as-received Zr alloys at 1100 and 1200°C. (4) Hydriding has no effect on the oxidation kinetics at 1200°C, but after quenching the hydrided materials become brittle at a lower weight gain than...

..., the stress relief time has an effect on yield stress. The stress relief time may have an effect on the irradiation embrittlement of the welds, but the trend is not conclusive. Since there is an effect of stress relief time on the initial transition temperature, it is felt that it is important to test...

... The current neutron irradiation embrittlement trend equation used in the U.S. is contained in Nuclear Regulatory Commission (NRC) Regulatory Guide 1.99, Revision 2. The database used to establish this correlation was compiled in the late 1980s. Since that time there has been about a five fold...

.... This unified definition would provide common margins for the two approaches and assure a consistent level of confidence in the analysis. The statistical basis of the Master Curve makes it possible to establish a more rational basis for the margins applied in both approaches. embrittlement embrittlement...

... The effect of neutron flux level is a longstanding concern for determining the applicability of test reactor data or high lead-factor surveillance data to the prediction of embrittlement in commercial reactor pressure vessels (RPV). However, as operating reactors reach higher fluences...

... tensile and impact Charpy data for this material. F82H master curve T o Charpy tensile embrittlement Mikhail A. Sokolov, ~Ronald L. Klueh, ~G. Robert Odette,2 Kiyoyuki Shiba, 3 and Hiroyasu Tanigawa3 Fracture Toughness Characterization of Irradiated F82H in the Transition Region Reference...

... Both the intergranular and intragranular segregation of phosphorus may significantly contribute to irradiation embrittlement of reactor pressure vessel steels. The modeling of phosphorus radiation-induced segregation at cylindrical (dislocations), spherical (precipitates and voids) and flat...

... in testing at room temperature, but did not fail in-pile. Significant improvement in ductility was observed in clad that had been exposed to the less severe transients, where a small α-phase grain structure was retained. Zircaloy cladding dry-out microstructure mechanical properties embrittlement...

..., dose and Fe and P diffusion parameters available for iron alloys. It is shown that the GB phosphorus concentration calculated as a function of temperature reveals one or two maxima depending on dose and the choice of material parameters. iron alloys irradiation embrittlement grain boundaries...