Results 151 to 160 of about 308 (200)
Some of the next articles are maybe not open access.
Integrity of Magnox reactor steel pressure vessels
Materials Science and Technology, 1993AbstractThe background to the safety assessment of the steel reactor pressure vessels for Magnox power stations is reviewed. The evolved philosophy adopted for the 1991 safety cases prepared for the continued operation of four Magnox power stations operated by Nuclear Electric plc is described together with different aspects of the multielement ...
P. E. J. Flewitt +2 more
openaire +1 more source
Validation of RTT0 for German Reactor Pressure Vessel Steels
Journal of Pressure Vessel Technology, 2008For the introduction of the new reference temperature RTT0 of the ASME Code Cases N-629 and N-631 into the German Standard KTA 3201.2, the applicability of RTT0 was validated by the reevaluation of the existing fracture toughness database of German reactor pressure vessel. (RPV) steels including unirradiated and irradiated base materials and weld metal
Dieter Siegele +2 more
openaire +1 more source
NEUTRON EMBRITTLEMENT OF REACTOR PRESSURE VESSEL STEELS
1963This report presents the status of observations on the embrittlement of steels which are commonly used for the primary pressure containment vessels of nuclear power plants. The demonstrated criterion of nil ductility transition (NDT) temperature provides the basis for meaningful analysis of neutron-induced embrittlement in reactor steels.
J. R. Hawthorne, L. E. Steele
openaire +1 more source
Evaluation of the reactor pressure vessel steels by positron annihilation
Journal of Nuclear Materials, 2013Abstract This paper presents a comparison of commercially used German and Russian reactor pressure vessel steels from the positron annihilation spectroscopy (PAS) point of view, having in mind knowledge obtained also from other techniques from the last decades.
V. Slugeň +8 more
openaire +1 more source
Intergranular Embrittlement of Nuclear Reactor Pressure Vessel Steels
Key Engineering Materials, 2013Service life of VVER-type nuclear reactor is limited by decrease in brittle fracture resistance of reactor pressure vessel produced of low-alloy low-carbon steel under effect of irradiation and/or elevated temperatures. In this work fracture surfaces were studied by Auger-electron spectroscopy in order to estimate the contribution of intergranular ...
Oleg O. Zabusov +5 more
openaire +1 more source
Radiation embrittlement of reactor pressure vessel steels
Nuclear Engineering and Design, 1966Abstract The problem of radiation embrittlement of reactor pressure vessel steels is considered within the framework of new NRL concepts of fracture analysis and in reference to the primary variables, steel composition, neutron exposure, and exposure temperature.
openaire +1 more source
Positron Lifetime Study of Reactor Pressure Vessel Steels
physica status solidi (a), 2000Positron lifetime (PL) study of several reactor pressure vessel (RPV) steels is presented. VVER-440 type Cr-Mo-V, VVER-1000 type Cr-Mo-Ni-V and A533-B RPV steels were included in the investigation. It was found that positrons annihilate from delocalized state or trapped at dislocations (lifetime 150 ps) in all specimens.
J. Čížek +3 more
openaire +1 more source
Strength problems of reactor steel pressure vessel of large dimensions
Nuclear Structural Engineering, 1965Abstract The production of an operationally reliable pressure vessel for the reactor is one of the difficult tasks encountered in many projects of large nuclear power stations. These steel vessels have large dimensions (diameters from 3 m to 8 m) and a comparatively high internal pressure so that the basic wall thickness is sometimes amounting to ...
openaire +1 more source
Microstructural study of WWER reactor pressure vessel steels
Nuclear Engineering and Design, 2013Abstract This paper presents results from our long-term studies of irradiated, commercially used WWER reactor pressure vessel steels. Results from Charpy-V tests and positron annihilation spectroscopy techniques are compared and discussed in details, having in mind actual state of art and other microstructural studies in this area. The optimal region
V. Slugeň, A. Kryukov
openaire +1 more source
Usnrc Research on Reactor Pressure Vessel Steel Embrittlement
1994Meutron radiation embrittlement of nuclear reactor vessels continues to be a major concern of the USNRC. Research is sponsored for improving understanding of radiation embrittlement effects to predict margins of safety and to improve regulations. Regulatory issues that are affected by neutron embrittlement are examined and related to NRC research ...
A Taboada, M Mayfield
openaire +1 more source