Results 151 to 160 of about 2,735 (205)

The fatigue behavior of irradiated Reactor Pressure Vessel steel

Engineering Failure Analysis, 2017
Abstract Fatigue specimens of A508-3 steel were irradiated in the swimming-pool test reactor in China Institute of Atomic Energy, the fluence was 3 × 10 19  n/cm 2 at 300 °C, then low-cycle fatigue tests were carried out at ambient temperature, with the fatigue strain range is 0.32–1.8%. The results indicate that, irradiated A508-3 specimens exhibit
W. Zhong, Z. Tong, G. Ning, C. Zhang, H. Lin, W. Yang   +5 more
exaly   +2 more sources

Stainless steel reactor pressure vessels

Nuclear Engineering and Design, 1970
Abstract The properties of stainless steels preferred for nuclear reactor pressure vessel construction, the austenitic-chromium-nickel types, are reviewed along with other bases for this nuclear application. The engineering criteria which establish the limits for design and operation, the various aspects of vessel fabrication and the implications of ...
P.J. Karnoski, W.J. Fretague, Uldis Potapovs, L.E. Steele   +3 more
openaire   +1 more source

Assessment of Steels for Nuclear Reactor Pressure Vessels

Journal of Engineering for Power, 1964
Some of the materials problems associated with the use of mild steels in large gas-cooled reactor pressure vessels are discussed. Tests to failure of 5-ft-dia 0.36 percent carbon-steel vessels with through-thickness longitudinal slots, supported by tests on 7-ft-wide centrally slotted flat plates, have indicated that rapid failure at working-stress ...
A. Cowan, R. W. Nichols
openaire   +1 more source

Irradiation-Embrittlement of Reactor Pressure Vessel Steel

18th International Conference on Nuclear Engineering: Volume 5, 2010
Irradiated for 4 cycles inside the reactor, the irradiation surveillance capsule (ISC) was withdrawn and transported to Nuclear Power Institute of China (NPIC) for dismantling in the hot cell. This paper presented tensile tests and Charpy-V impact tests on non-irradiated and irradiated specimens. Tensile tests were performed at room temperature and 300
Guoyun Li, Yukun Wu, Guofu Jiang, Juan Huang, Haisheng Zhang   +4 more
openaire   +1 more source

Micromechanical modelling of reactor pressure vessel steel

Materials & Design (1980-2015), 2012
Abstract Safe operation of nuclear power plants is one of the major concerns and relies primarily on the integrity of the reactor pressure vessel. Neutron exposure induces temperature dependent embrittlement and can lead to loss of fracture toughness of reactor pressure vessel steel.
R. Chhibber, H. Singh, N. Arora, B.K. Dutta   +3 more
openaire   +1 more source

Microstructural evolution in reactor pressure vessel steels

Journal of Nuclear Materials, 1993
Abstract The irradiation-induced changes occurring at the nanometer level in the microstructure of the reactor pressure vessel have been shown to be responsible for a degradation in mechanical properties that occur in large structures with dimensions in the tens of metres. These changes can place severe restrictions on the reactor both at the startup
W.J. Phythian, C.A. English
openaire   +1 more source

Carbon analysis in reactor pressure vessel steels

Proceedings, annual meeting, Electron Microscopy Society of America, 1983
The effect of neutron irradiation on the notch ductility transition temperature (NDTT) of A533B steel is known to be affected by the activity of the carbon atom which would be affected by its nearest neighboring substitutional atom, that is, silicon, manganese, etc.
O.C. de Hodgins, B.L. Shriver, K.R. Lawless   +2 more
openaire   +1 more source

Integrity of Magnox reactor steel pressure vessels

Materials Science and Technology, 1993
AbstractThe 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, G. H. Williams, M. B. Wright   +2 more
openaire   +1 more source

Validation of RTT0 for German Reactor Pressure Vessel Steels

Journal of Pressure Vessel Technology, 2008
For 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, Elisabeth Keim, Gerhard Nagel   +2 more
openaire   +1 more source

NEUTRON EMBRITTLEMENT OF REACTOR PRESSURE VESSEL STEELS

1963
This 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