Results 141 to 150 of about 308 (200)

Enhanced Molybdenum Recovery Achieved by a Complex of Porous Material-Immobilized Surface-Engineered Yeast in Development of a Sustainable Biosorption Technology. [PDF]

Microorganisms
Jittayasotorn T, Kojima K, Stephanie A, Nakamura K, Bacosa HP, Kubota K, Kamitakahara M, Inoue C, Chien MF.   +8 more
europepmc   +1 more source

An Investigation on the Potential of Utilizing Aluminum Alloys in the Production and Storage of Hydrogen Gas. [PDF]

Materials (Basel)
Reda R, Ashraf A, Magdy I, Ragab M, Eldabaa N, Abo Elmagd M, Abdelhafiz M, El-Banna O, Fouad A, Aly HA, Tlija M, Soliman AT, Elsayed A, Elshaghoul YGY.   +13 more
europepmc   +1 more source

Nanoindentation Test of Ion-Irradiated Materials: Issues, Modeling and Challenges. [PDF]

Materials (Basel)
Ma H, Fan P, Qian Q, Zhang Q, Li K, Zhu S, Yuan D.   +6 more
europepmc   +1 more source

Some of the next articles are maybe not open access.

Related searches:

Interactions of Defects with Dislocations in Reactor Pressure Vessel Steels

1993
The radiation embrittlement of reactor pressure vessel steels may be partially explained by the creation of irradiation-induced defects that interact with the moving dislocations during plastic deformation. This research studies the nature of the interaction mechanisms and the microstructural properties and the mobility of the dislocations.
R Schaller
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