Zobrazeno 1 - 10
of 36
pro vyhledávání: '"T. Nitheanandan"'
Autor:
T. NITHEANANDAN, M.J. BROWN
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 5, Pp 589-596 (2013)
In a pressurized heavy water reactor, following loss of the primary coolant, severe core damage would begin with the depletion of the liquid moderator, exposing the top row of internally-voided fuel channels to steam cooling conditions on the inside
Externí odkaz:
https://doaj.org/article/788a6839090141e4a2a0c6facc3b9c7b
Publikováno v:
CNL Nuclear Review. 9:1-10
The National Research Universal (NRU) reactor is a major research facility that provides a beam of slow neutrons with a minimum of gamma rays and other types of radiation for experimental purposes. The thermal column consists of 5 graphite radial sec
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6333aa911a94872484ed8117f0040e61
https://doi.org/10.12943/cnr.2018.00005
https://doi.org/10.12943/cnr.2018.00005
Publikováno v:
Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation.
This paper describes the work conducted by the Canadian Nuclear Safety Commission (CNSC) related to the numerical simulations of reinforced concrete (RC) structures under deformable missile impact. The current paper is a continuation of the work cond
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::90faf55ec3316a377c1e15ee3147dc49
https://doi.org/10.1115/icone2020-16523
https://doi.org/10.1115/icone2020-16523
Autor:
Ramesh Kumar, T. Nitheanandan, Balbir Kumar Singh, Ritu J. Singh, Matthias Krause, Avinash J. Gaikwad
Publikováno v:
Nuclear Engineering and Design. 328:188-196
In-depth understanding of the thermo-structural behaviour of structure system and components (SSCs) of a nuclear power plant is necessary for both safety margin assessment, and for devising appropriate prevention and accident mitigation strategies. I
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1af9473bc535cd7e650b4d7670d9550f
https://doi.org/10.1016/j.nucengdes.2017.12.035
https://doi.org/10.1016/j.nucengdes.2017.12.035
Publikováno v:
CNL Nuclear Review. 5:67-84
The sag behaviour of a simulated nuclear fuel element during high-temperature transients has been investigated in an experiment utilizing an internal indirect heating method. The major motivation of the experiment was to improve understanding of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ddc47dda8250b24278c74a09f8261f14
https://doi.org/10.12943/cnr.2016.00005
https://doi.org/10.12943/cnr.2016.00005
Publikováno v:
CNL Nuclear Review. 5:85-93
The emissivity of pre-oxidized and un-oxidized pressure-tube specimens has been measured at high temperatures under vacuum. The emissivity values of un-oxidized tube specimens decreased only slightly from 0.34 at 600 °C to 0.30 at 800 °C and change
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f9d1ab44a7ae93048d18913ab846a33a
https://doi.org/10.12943/cnr.2016.00006
https://doi.org/10.12943/cnr.2016.00006
Autor:
F. Barré, Hideo Nakamura, T. Nitheanandan, Luis E. Herranz, Sevostian Bechta, F. D'Auria, R. Lee, Didier Jacquemain, K.-Y. Choi, N. Sandberg
Publikováno v:
Progress in Nuclear Energy. 127:103432
The Working Group on the Analysis and Management of Accidents (WGAMA) was created on December 31st, 1999 to assess and strengthen the technical basis needed for the prevention, mitigation and management of potential accidents in NPP and to facilitate
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f2a43966fe16a6e1fa12374d0413f82a
https://doi.org/10.1016/j.pnucene.2020.103432
https://doi.org/10.1016/j.pnucene.2020.103432
Autor:
H. P. Rammohan, Arun K. Nayak, D.-H. Kim, H. G. Lele, Daniel Dupleac, T. Nitheanandan, X. Cao, J.-H. Choi
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 3
The International Atomic Energy Agency (IAEA) organized a coordinated research project (CRP) on “Benchmarking Severe Accident Computer Codes for Heavy Water Reactors (HWR) Applications,” (IAEA TECDOC Series No. 1727), and the activity was complet
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::43e07ca78c8b0aba6b3e8e6d59e3c44a
https://doi.org/10.1115/1.4035726
https://doi.org/10.1115/1.4035726
Publikováno v:
Journal of Enhanced Heat Transfer. 8:137-146
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f7e72832d385a89977b10df2789ed560
https://doi.org/10.1615/jenhheattransf.v8.i2.60
https://doi.org/10.1615/jenhheattransf.v8.i2.60
Autor:
T. Nitheanandan, H. M. Soliman
Publikováno v:
The Canadian Journal of Chemical Engineering. 72:26-34
A mechanistic model has been developed for determining the stratified boundary for condensing flows in horizontal and slightly inclined tubes. Two formulations, a complete and a simplified version are considered for the equilibrium liquid level. Good
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e6bef37c603dda353de16e2fd80b3312
https://doi.org/10.1002/cjce.5450720105
https://doi.org/10.1002/cjce.5450720105