Zobrazeno 1 - 10
of 14
pro vyhledávání: '"H. K. Khandelwal"'
Publikováno v:
Journal of Nuclear Materials. 467:373-382
Zr-2.5Nb alloy pressure tubes used in pressurized heavy water reactors (PHWR) are susceptible to failure by Delayed Hydride Cracking (DHC), which is a form of localized hydride-embrittlement phenomenon manifested in the presence of a hydrostatic stre
Publikováno v:
Journal of Nuclear Materials. 466:208-219
In order to attain improved in-reactor performance few prototypes pressure tubes of Zr-2.5Nb alloy were manufactured by employing forging to break the cast structure and to obtain more homogeneous microstructure. Both double forging and single forgin
Autor:
D. Bhachawat, R. Shekhar, R.N. Singh, Saurav Sunil, A.K. Bind, Asok Ghosh, H. K. Khandelwal, P. Dhandharia, Sunil Kumar, J.K. Chakravartty
Publikováno v:
Nuclear Engineering and Design. 293:138-149
The pressure tubes of Indian Pressurized Heavy Water Reactor (IPHWR) of 220 MWe are made of Zr–2.5Nb alloy manufactured either from Double Melted (DM) or from Quadruple Melted (QM) ingots. These pressure tubes are manufactured by hot extrusion, two
Autor:
H. K. Khandelwal, G. Avinash, Per Ståhle, J.K. Chakravartty, Saurav Sunil, R. N. Singh, A.K. Bind
Publikováno v:
Journal of Nuclear Materials. 465:177-188
For the safety assessment of PHWR, it is required to study the flaw tolerance capacity of the pressure tubes as a function of the loading rate. In this work, the effect of loading rate and hydrogen content on the fracture behaviour of a Zr-2.5Nb allo
Autor:
B. N. Rath, R. N. Singh, J.K. Chakravartty, A.K. Bind, H. K. Khandelwal, Saurav Sunil, Per Ståhle
Publikováno v:
Materials Science and Engineering: A. 621:190-197
Previous work by one of the authors reported the stress-field for a fully-constrained hydride embedded in matrix computed using finite element method to develop an understanding of the temperature dependence of susceptibility of Zr-alloys to hydride
Publikováno v:
Materials Science and Engineering: A. 579:157-163
The stress fields of expanding (precipitation) and contracting (dissolution) hydride plates were computed by finite element method using Zr-H solid solution and hydride properties at 25, 200 and 400 degrees C for fully and semi-constrained hydride pl
Publikováno v:
Engineering Fracture Mechanics. 105:200-210
The fracture toughness of Zr–2.5Nb pressure tube alloy used in Indian Pressurized Heavy Water Reactor was determined in the temperature range of 30–300 °C using load normalization technique ( LNT ) and a comparison between the crack initiation a
Autor:
Rampal Singh, Nagaiyar Krishnamurthy, H. K. Khandelwal, B.K. Shah, C Gargi, Abhishek Mukherjee, I.S. Batra
Publikováno v:
Journal of Nuclear Materials. 434:389-394
In a recent experiment, a high density of much stronger sites for nucleation of hydrides than available otherwise in a Zr-alloy was created by the authors by a synergistic effect of addition of a small quantity of Y to Zr and microstructural modifica
Publikováno v:
Advanced Materials Research. 585:342-346
This work studied the ball indentation test at room temperature to characterize the local tensile properties of bi-metallic weld joints. The weld specimens used were fabricated by joining between SA 508 Gr. 3 ferritic steel and Type 304LN stainless s
Publikováno v:
Journal of Minerals and Materials Characterization and Engineering. 11:1095-1110
A weld joint is composed of three principal zones viz., base metal, Heat Affected Zone (HAZ), and weld zone. Thus, the variation in mechanical behavior exists not only among these zones, but also from point to point in each individual zone. Being des