Results 131 to 140 of about 1,645 (179)
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Radiation and Temper Embrittlement Processes in Advanced Reactor Weld Metals

Journal of Engineering for Industry, 1972
Experimental weld filler metals having high resistance to radiation embrittlement at ≃550 F (288 C) have been developed for quenched and tempered A543 and A542 steel. The filler metals are from a special 2-1/4 Cr-1 Mo-0.40Si-0.10C composition series formulated to study the effects of variable copper, nickel, and manganese contents on weld performance ...
J. R. Hawthorne, E. Fortner
exaly   +2 more sources

Radiation induced embrittlement of PTFE

Polymer, 2003
Abstract The radiochemical degradation of polytetrafluoroethylene (PTFE) samples has been studied in air at dose rate 100 Gy/h for doses up to 5000 Gy, at ambient temperature. The polymer degradation has been monitored by DSC, tensile testing and Essential Work of Fracture (EWF) testing.
B. Fayolle, L. Audouin, J. Verdu
openaire   +1 more source

Contribution of γ radiation to radiation embrittlement of vessel steel

Atomic Energy, 2009
Data on the contribution of reactor γ rays to the embrittlement of nuclear reactor vessel steel are presented and discussed. It is shown qualitatively that the increase of the shift of the critical brittleness temperature in the region of the outer layers of propulsion-reactor vessels and, conversely, the decrease of this shift at the same locations in
V. A. Nikolaenko   +3 more
openaire   +1 more source

BURNUP AND RADIATION EMBRITTLEMENT OF THE U-MO NEUTRON SOURCE TARGET

Problems of Atomic Science and Technology, 2022
The burnup of uranium target plates of the NSC KIPT neutron source was studied. An analysis of experimental work on the effect of neutron irradiation on the strength and plastic properties of uranium and U-Mo alloys under conditions close to the operation of the target has been carried out.
Borts, B.V.   +6 more
openaire   +2 more sources

Radiation embrittlement of low-alloy steels

International Journal of Pressure Vessels and Piping, 2002
Abstract Results of phosphorus, copper and nickel effect on radiation induced yield stress increase and ductile-to-brittle transition temperature (DBTT) shift are presented. The synergetic interaction between phosphorus and nickel is observed. The results of Russian VVER-440 and VVER-1000 surveillance programs and results of research programs on ...
Yu.A Nikolaev   +2 more
openaire   +1 more source

Composition effects in the radiation embrittlement of low-alloy steel

Atomic Energy, 1998
Alexander Kryukov   +2 more
exaly   +2 more sources

Radiation-induced strengthening and embrittlement in aluminum

Metallurgical Transactions, 1973
Commercially pure aluminum (1100 grade) in the annealed condition was irradiated to fast fluences in the range 1 to 3 × 1026 neutron/m2 (E > 0.1 MeV) and to similar thermal fluences at temperatures of 318 to 328 K, and was then tensile tested at temperatures between 298 and 643 K.
K. Farrell, R. T. King
openaire   +1 more source

The effect of nitrogen on the radiation embrittlement of iron

Solid State Communications, 1966
Abstract Two vacuum-melted pure iron alloys, the former containing a maximum of free nitrogen and the latter enough titanium to block the remaining nitrogen and carbon in nitride and carbide form, were carefully prepared in an induction furnace. From these materials, sub-size Charpy-notched specimens were machined and then irradiated to an integrated
R.L. Colombo, F.S. Rossi, J. Sebille
openaire   +1 more source

Radiation Embrittlement Surveillance and Trend Evaluation in Hungary

2023
The scatter of the existing trend curves is too large for the WWER-440 reactors operated in Hungary because the end-of-life fluence of these units are out of the validity range of the existing trend curves with the exception of the Russian trend curves.
Ferenc Gillemot   +4 more
openaire   +1 more source

Radiation Embrittlement of VVÉR-1000 Vessel Materials

Atomic Energy, 2001
Radiation embrittlement of VVER-1000 vessel materials has been studied much less than for VVER-440 reactors. In the present paper the results of an investigation of the first batches of control samples of VVER-1000 vessel materials are discussed. The chemical composition of the materials is characterized by a low content of harmful impurities (copper ...
A. V. Nikolaeva   +2 more
openaire   +1 more source

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