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pro vyhledávání: '"K. Umasankari"'
Akademický článek
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Neutron transport in a nuclear reactor in both space and time domain has been elucidated in the previous chapters. Theoretical models are used to study neutron transport behavior in both multiplying and nonmultiplying medium and are used in design ca
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ce0cb7772ca064bf4d397f3ceb85dd7f
https://doi.org/10.1016/b978-0-12-822441-0.00014-5
https://doi.org/10.1016/b978-0-12-822441-0.00014-5
Autor:
A. John Arul, Abhitab Bachchan, Kapil Deo, K. Devan, V. Gopalakrishnan, Anurag Gupta, R.S. Keshavamurthy, Suhail Ahmad Khan, D. Sunil Kumar, Rajeev Kumar, P. Mohanakrishnan, K. Obaidurrahman, Rajeev Ranjan Prasad, M. Ramakrishnan, Om Pal Singh, K. Umasankari
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a8d52ce8736f6eff14a63787c5316057
https://doi.org/10.1016/b978-0-12-822441-0.09990-8
https://doi.org/10.1016/b978-0-12-822441-0.09990-8
Autor:
K. Umasankari, P. Mohanakrishnan
Energy extracted from a nuclear fuel is a measure of its potential. Estimation of fuel performance is an essential aspect of reactor design. Fuel cycle physics entails an entire gamut of studies from the front end which deals with efficient use in re
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::728d3c9b4f609744de11d0a00a43061f
https://doi.org/10.1016/b978-0-12-822441-0.00005-4
https://doi.org/10.1016/b978-0-12-822441-0.00005-4
This chapter discusses the various methods and codes used in analyzing thermal (light-water reactors) and fast reactor (sodium-cooled fast reactors) cores. Multigroup nuclear data libraries and details of lattice physics calculations to account spati
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https://explore.openaire.eu/search/publication?articleId=doi_________::98e16c32927897efa306c7b425e3c854
https://doi.org/10.1016/b978-0-12-822441-0.00012-1
https://doi.org/10.1016/b978-0-12-822441-0.00012-1
Physics of Nuclear Reactors presents a comprehensive analysis of nuclear reactor physics. Editors P. Mohanakrishnan, Om Pal Singh, and Kannan Umasankari and a team of expert contributors combine their knowledge to guide the reader through a toolkit o
Publikováno v:
Nuclear Engineering and Design. 320:1-8
In the present paper, preliminary steady-state neutronic evaluations are carried out to understand the dynamics of a molten salt reactor. Oak Ridge National Laboratory’s (ORNL) Molten Salt Reactor Experiment(MSRE) is selected for the case study and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::97287c8e25a2d1db7015548ff0eccfa3
https://doi.org/10.1016/j.nucengdes.2017.05.005
https://doi.org/10.1016/j.nucengdes.2017.05.005
Akademický článek
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Publikováno v:
Nuclear Engineering and Design. 370:110881
India is developing 100kWth Compact High Temperature Reactor (CHTR) to demonstrate the technology enabling high-temperature process heat applications such as hydrogen production. The reactor core is envisaged with 233U-Th based TRISO coated fuel part
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ba33183d1c6648a2c2e6f2d9612ca9b8
https://doi.org/10.1016/j.nucengdes.2020.110881
https://doi.org/10.1016/j.nucengdes.2020.110881