Results 171 to 180 of about 3,105,065 (231)

Accelerating Green Hydrogen Generation Strategies for High-Efficiency Auxiliary Hydrogen Production Under High Current Density. [PDF]

ChemSusChem
Qiu H, Wen S, Fu Q, Yan L, Zhao X.
europepmc   +1 more source

Mechanical properties and residual stresses in multi pass AISI 304 to AISI 1018 steel welds by SMAW and GTAW. [PDF]

Sci Rep
Shridhar, Janapareddy PK, Kumar GBV, Sahu SK, El-Rayyes A, Giri J, Singh B.   +6 more
europepmc   +1 more source

Dataset of tensile properties for sub-sized specimens of nuclear structural materials. [PDF]

Sci Data
Li L, Merickel JW, Tang Y, Song R, Rittenhouse JE, Vakanski A, Xu F.   +6 more
europepmc   +1 more source

Developments, challenges and prospects in thermal-hydraulic research on accident tolerant fuel. [PDF]

Heliyon
Li Y, You E, Wang T, Xing D, Xu J, Zhang H.   +5 more
europepmc   +1 more source

Heitt Mjölnir: a heated miniature triaxial apparatus for 4D synchrotron microtomography. [PDF]

J Synchrotron Radiat
Freitas D, Butler IB, Elphick SC, Gilgannon J, Rizzo RE, Plümper O, Wheeler J, Schlepütz CM, Marone F, Fusseis F.   +9 more
europepmc   +1 more source

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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
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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Irradiated for 4 cycles inside the reactor, the irradiation surveillance capsule (ISC) was withdrawn and transported to Nuclear Power Institute of China (NPIC) for dismantling in the hot cell.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
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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
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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