Zobrazeno 1 - 10
of 37
pro vyhledávání: '"M. P. Puls"'
Autor:
M. P. Puls
Publikováno v:
Journal of Nuclear Materials. 399:248-258
This work comments on Kim’s rebuttal of this authors’ critical review that is cited in the title of this paper. The author shows that Kim’s rebuttal of the author’s review is based on essentially the same physical misconceptions concerning th
Autor:
M. P. Puls
Publikováno v:
Journal of Nuclear Materials. 393:350-367
A review is given of the thermodynamic basis of a model developed by Dutton and Puls for the rate of subcritical crack propagation by delayed hydride cracking in zirconium alloys. This review was prompted, in part, by the publications of a series of
Autor:
M. P. Puls
Publikováno v:
Nuclear Engineering and Design. 171:137-148
In modern CANDU ™ nuclear generating stations, pressure tubes of cold-worked Zr2.5Nb material are used in the reactor core to contain the fuel bundles and the heavy water (D 2 O) coolant. The pressure tubes operate at an internal pressure of abo
Autor:
M. P. Puls, San-Qiang Shi
Publikováno v:
Hydrogen Effects in Materials
Recent theoretical advances in understanding the phenomena of delayed hydride cracking (DHC) in structural materials such as zirconium alloys used in nuclear reactors are reviewed. The criteria for the Initiation of DHC are established in terms of th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6d58a36b9336fc2180177e13a6cf5e30
https://doi.org/10.1002/9781118803363.ch53
https://doi.org/10.1002/9781118803363.ch53
Publikováno v:
Journal of Nuclear Materials. 228:227-237
The terminal solid solubility (TSS) of hydrogen or deuterium is an important parameter in Zr alloys that are used in the nuclear industry. If this solubility is exceeded, it can make the alloys susceptible to delayed hydride cracking. Accurate expres
Publikováno v:
Journal of Nuclear Materials. 218:189-201
An experimental study was carried out to determine the hydrogen concentration limit as a function of temperature at which delayed hydride cracking (DHC) commences in Zr-2.5 Nb pressure tube material. For a given hydrogen content of the specimen, two
Autor:
San-Qiang Shi, M. P. Puls
Publikováno v:
ResearcherID
The maximum normal tensile stress at a shallow notch is used elsewhere to define a threshold level for the initiation of delayed hydride cracking at blunt notches in the pressure tubes of CANDUTM nuclear reactors. A simple method, based on a modified
Publikováno v:
Metallurgical and Materials Transactions A. 25:135-145
A study of the deformation behavior of irradiated highly textured Zr-2.5Nb pressure tube material in the temperature range of 30 °C to 300 °C was undertaken to understand better the mechanism for the deterioration of the fracture toughness with neu
Crack initiation at long radial hydrides in Zr-2.5nb pressure tube material at elevated temperatures
Autor:
R. Choubey, M. P. Puls
Publikováno v:
Metallurgical and Materials Transactions A. 25:993-1004
Crack initiation at hydrides in smooth tensile specimens of Zr-2.5Nb pressure tube material was investigated at elevated temperatures up to 300 °C using an acoustic emission (AE) technique. The test specimens contained long, radial hydride platelets
Publikováno v:
ResearcherID
This work investigates the experimental conditions necessary for initiation of delayed hydride cracking in Zr-2.5Nb alloys. The experiments were performed on 240 notched cantiliver beam specimens loaded in pure bending to a wide range of stresses. Th