Zobrazeno 1 - 10
of 75
pro vyhledávání: '"Vivek Bhasin"'
Autor:
P. Gandhi, P.K. Singh, Suneel Gupta, Gajendra P. S. Raghava, M. Saravanan, Vivek Bhasin, S. Vishnuvardhan
Publikováno v:
International Journal of Pressure Vessels and Piping. 174:32-41
Fracture studies were carried out on narrow gap welded SA 312 Type 304LN stainless steel straight pipes having circumferential through-wall notch in the weld. Totally six specimens were tested; one specimen was subjected to monotonic loading and the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1161fb73a1cfa129d2812d111adedd0b
https://doi.org/10.1016/j.ijpvp.2019.05.012
https://doi.org/10.1016/j.ijpvp.2019.05.012
Publikováno v:
Journal of Nuclear Materials. 513:16-32
The chemical interaction of U−Zr based fast reactor fuel with T91 grade steel cladding was investigated by employing DTA (differential thermal analysis), diffusion couple experiment and SEM/EDS, SEM/EBSD analyses. The DTA results revealed a strong
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4a1f4226d4e8ad6d3f917203289d2147
https://doi.org/10.1016/j.jnucmat.2018.10.041
https://doi.org/10.1016/j.jnucmat.2018.10.041
Publikováno v:
Lecture Notes on Multidisciplinary Industrial Engineering ISBN: 9789811532535
Cellular polymer foams find extensive applications as energy absorbers under static, impact and blast loads due to their capacity to absorb energy under constant stress up to full densification strain (Ashby et al. Metal foams: a design guide. Butter
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b6924ebf5f919b6302c9e5d34685c775
https://doi.org/10.1007/978-981-15-3254-2_5
https://doi.org/10.1007/978-981-15-3254-2_5
Publikováno v:
Journal of Nuclear Materials. 504:234-250
Uranium-rich U–Zr–Nb alloy is considered as a good alternative fuel for fast reactors from the perspective of excellent dimensional stability and desired thermo-physical properties to achieve higher burnup. Detailed investigations related to the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::215f9e6fd4c08c6e185cd2f5a3a86eac
https://doi.org/10.1016/j.jnucmat.2018.03.044
https://doi.org/10.1016/j.jnucmat.2018.03.044
Autor:
K.K. Vaze, Kamal Sharma, A.K. Ghosh, K. Madhusoodanan, R.N. Singh, B Gaur, Vivek Bhasin, E. Ramadasan, K.V. Kasiviswanathan, K. S. Balakrishnan, P.K. Singh, B.B. Rupani, V. Karthik, S. Anantharaman
Publikováno v:
Nuclear Engineering and Design. 330:303-316
This paper presents outcome of round robin exercise on usage of ball indentation technique to predict strength properties of three different materials which are used in Indian nuclear reactors. The main objectives were to evolve a standardized proced
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7e46d54b0ce6662e281c31679249fb7d
https://doi.org/10.1016/j.nucengdes.2018.01.015
https://doi.org/10.1016/j.nucengdes.2018.01.015
Publikováno v:
Nuclear Engineering and Design. 327:286-298
In case of severe accidents like loss of coolant accident with failure of emergency core cooling system, the pressure tubes get heated quickly causing severe deformation. In this paper, an analytical solution technique has been used for calculating t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cb61288d81f1b0811c3e4557a111ea7d
https://doi.org/10.1016/j.nucengdes.2017.12.004
https://doi.org/10.1016/j.nucengdes.2017.12.004
Publikováno v:
Journal of Nuclear Materials. 495:332-342
This paper presents the results of the investigation on the deformation and rupture characteristics of Indian pressurized heavy water reactor (IPHWR) fuel pins under simulated loss of coolant accident (LOCA) condition in steam environment. Transient
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fa23720041edde5adf3a3221e46010f0
https://doi.org/10.1016/j.jnucmat.2017.08.008
https://doi.org/10.1016/j.jnucmat.2017.08.008
Autor:
J.L. Singh, Suparna Banerjee, J.S. Dubey, Baidyanath Rath, Sunil Kumar, Tapan K. Sawarn, Vivek Bhasin, R.S. Shriwastaw
Publikováno v:
Journal of Nuclear Materials. 493:460-470
The present study involves the estimation of ring tensile properties of Indian Pressurised Heavy Water Reactor (IPHWR) fuel cladding made of Zircaloy-4, subjected to experiments under a simulated loss-of-coolant-accident (LOCA) condition. Isothermal
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7009abd4ac9eb4f01f7429850d9adba4
https://doi.org/10.1016/j.jnucmat.2017.06.032
https://doi.org/10.1016/j.jnucmat.2017.06.032
Autor:
I.A. Khan, Vivek Bhasin
Publikováno v:
International Journal of Solids and Structures. 108:203-215
Detailed three-dimensional finite element based cell model studies are carried out to understand the role of secondary voids and their distribution in the mechanism of void growth and coalescence in a porous plastic solid. In contrast to most of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4c9af01e8f9aeec6e38e77f43f0f28a3
https://doi.org/10.1016/j.ijsolstr.2016.12.016
https://doi.org/10.1016/j.ijsolstr.2016.12.016
Publikováno v:
International Journal of Fatigue. 95:204-215
The present study aims at quantification of Fatigue Crack Growth Rate (FCGR) parameters under different dissolved oxygen levels in water at room temperature (RT) and 300 °C for SA312 Type 304L(N). The tests were conducted under 0.005 Hz loading freq
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ee0b5a07a82070cd81298c33638b286d
https://doi.org/10.1016/j.ijfatigue.2016.10.022
https://doi.org/10.1016/j.ijfatigue.2016.10.022