Results 151 to 160 of about 1,137 (200)

Irradiation-induced embrittlement of a 2.25Cr1Mo steel

Journal of Nuclear Materials, 2000
Irradiation-induced embrittlement of a 2.25CrlMo is investigated by means of small punch testing and scanning electron microscopy (SEM). The ductile-brittle transition temperature (DBTT) determined by the small punch test is much lower than that determined by the standard Charpy test.
Song, S. H., Faulkner, R. G., Flewitt, P. E. J., Smith, R. F., Marmy, P., Victoria, M.   +5 more
openaire   +1 more source

Mitigation of Irradiation Embrittlement by Annealing

1996
The main results of a complex investigation carried out in Russia of post irradiation annealing and reembrittlement of WWER-440 reactor pressure vessel materials are presented. The dependence of the Charpy transition temperature recovery on annealing temperature and fluence was established. Charpy specimens were reirradiated after annealing at 340, 380,
AD Amayev, AM Kryukov, VI Levit, PA Platonov, MA Sokolov   +4 more
openaire   +1 more source

Irradiation-induced embrittlement of magnox cans

Radiation Effects, 1972
Abstract The creep ductility of Magnox AL80 (Mg/0.8 wt per cent A1/0.005 wt per cent Be) fuel element cans is known to decrease with increasing irradiation. A possible cause of this embrittlement is void nucleation at inert gas bubbles formed on grain boundaries.
G. B. Gibbs, J. E. Harris
openaire   +1 more source

The effect of chemical composition on irradiation embrittlement

Nuclear Engineering and Design, 1990
The Japanese Pressurized Thermal Shock (PTS) integrity study is now being conducted by the Japan Power Engineering and Inspection Corporation (JAPEIC) under contract with the Ministry of International Trade and Industry (MITI). This paper introduces the study plan and the interim results on irradiation embrittlement of reactor pressure vessel steels.
S. Ishino, T. Kawakami, T. Hidaka, M. Satoh   +3 more
openaire   +1 more source

The embrittlement of molybdenum by neutron irradiation

Philosophical Magazine, 1960
To determine if the same type of irradiation embrittlement which Hull and Mogford observed in EN/sub 2/ steel occurred in other body-centered cubic metals, their method was applied to molybdenum. Twenty molybdenum tensile, specimens, each having a different grain size, were prepared.
openaire   +1 more source

Irradiation embrittlement of ferritic stainless steels

Metal Science, 1984
AbstractThe characteristics of the irradiation embrittlement of some ferritic stainless steels were examined by tensile tests. Steels selected in this investigation were classified into three groups: X phase, precipitation hardened Fe-13Cr steels; tempered martensitic Fe-12Cr steels; and low alloy steels.
K. Suganuma, H. Kayano
openaire   +1 more source

Irradiation embrittlement mitigation

1993
Mitigation methods for reducing the irradiation damage on pressure vessel materials are reviewed: load leakage loading schemes are commonly used in PWRs to mitigate reactor pressure vessel embrittlement; dummy assemblies have been applied in WWER 440-type and in some old western power plants, when exceptional fast embrittlement has been encountered ...
Pelli, Reijo, Planman, Tapio, Valo, Matti, Törrönen, Kari   +4 more
openaire   +3 more sources

Assessment of irradiation embrittlement of the Eurofer97 steel after 590MeV proton irradiation

Journal of Nuclear Materials, 2009
The irradiation hardening of the Eurofer97 steel following 590 MeV proton irradiations was determined at three different irradiation temperatures, 50 °C, 250 °C and 350 °C, and various doses up to about 1.3 displacement per atom. The dose and temperature dependence of the irradiation hardening was characterized by a linear relationship between the ...
Spätig, P., Stoenescu, R., Mueller, P., Odette, G. R., Gragg, D.   +4 more
openaire   +1 more source

Embrittlement of irradiated ferritic/martensitic steels in the absence of irradiation hardening

Journal of Nuclear Materials, 2008
Irradiation damage caused by neutron irradiation below 425–450 C of 9–12% Cr ferritic/martensitic steels produces microstructural defects that cause an increase in yield stress. This irradiation hardening causes embrittlement observed in a Charpy impact test as an increase in the ductile–brittle transition temperature.
R.L. Klueh, K. Shiba, M.A. Sokolov
openaire   +1 more source

Irradiation embrittlement of neutron-irradiated low activation ferritic steels

Journal of Nuclear Materials, 1988
Abstract Effects of neutron irradiation and additions of small amounts of alloying elements on the ductile-brittle transition temperature (DBTT) of three different groups of ferritic steels were investigated by means of the Charpy impact test in order to gain an insight into the development of low-activation ferritic steels suitable for the nuclear ...
H. Kayano, A. Kimura, M. Narui, Y. Sasaki, Y. Suzuki, S. Ohta   +5 more
openaire   +1 more source