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pro vyhledávání: '"G. Pandikumar"'
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Akademický článek
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Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 325:913-921
In a nuclear reactor, heat generated by the decay of fission products and radioactive materials is called decay heat or decay power. For measuring decay heat from radioactive samples, bismuth germanate scintillators based whole energy absorption spec
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::33eef31ec004a59800ea50c18daa5eac
https://doi.org/10.1007/s10967-020-07229-y
https://doi.org/10.1007/s10967-020-07229-y
Autor:
Rajeev Ranjan Prasad, D. Venkata Subramanian, Bagchi Subhrojit, A. John Arul, M. M. Shanthi, D. Sunil Kumar, G. Pandikumar
Publikováno v:
Nuclear Science and Techniques. 30
In fast reactors, the inherent neutron source strength is often insufficient for monitoring the reactor start-up operation with ex-core detectors. To increase the subcritical neutron flux, an auxiliary neutron source subassembly (SSA) is generally us
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cc19a9c5f7cb66fca4aa7630eba7142f
https://doi.org/10.1007/s41365-019-0653-8
https://doi.org/10.1007/s41365-019-0653-8
Publikováno v:
Thorium—Energy for the Future ISBN: 9789811326578
The third stage of India’s nuclear program envisages utilization of thorium through Th–U233 cycle in view of the better abundance and relative merits of thorium. For early introduction of Thorium into the nuclear energy system, several R&D progra
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d13204cf33081db30d40120d76c1bfb7
https://doi.org/10.1007/978-981-13-2658-5_11
https://doi.org/10.1007/978-981-13-2658-5_11
Publikováno v:
Annals of Nuclear Energy. 138:107189
We study the relative contribution of decay heat compared to sodium fire and solar radiation to the temperature and pressure evolution in the containment of a medium-size SFR following a postulated severe accident. This is an important problem for co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eeb1987538c3d8c37f9e6cf3ddca0e5e
https://doi.org/10.1016/j.anucene.2019.107189
https://doi.org/10.1016/j.anucene.2019.107189
Publikováno v:
Pramana. 90
The radiation damage in the structural materials of a 500 MWe Indian prototype fast breeder reactor (PFBR) is re-assessed by computing the neutron displacement per atom (dpa) cross-sections from the recent nuclear data library evaluated by the USA, E
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4efa18620abb7685904ade4287e2d9df
https://doi.org/10.1007/s12043-018-1536-y
https://doi.org/10.1007/s12043-018-1536-y
Publikováno v:
Pramana. 85:667-683
A fast breeder reactor (FBR) closed fuel cycle involves recycling of the discharged fuel, after reprocessing and refabrication, in order to utilize the unburnt fuel and the bred fissile material. Our previous study in this regard for the prototype fa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c6de04e521351c610919003632d94174
https://doi.org/10.1007/s12043-014-0900-9
https://doi.org/10.1007/s12043-014-0900-9
Publikováno v:
Pramana. 77:315-333
An FBR closed fuel cycle involves recycling of the discharge fuel, after reprocessing and refabrication, to utilize the unburnt fuel remains and the freshly bred fissile material. Our previous study in this regard for the PFBR indicated a comfortable
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::672d5f39bb1d57569f7a06a656c8fa3c
https://doi.org/10.1007/s12043-011-0137-9
https://doi.org/10.1007/s12043-011-0137-9
Publikováno v:
Pramana. 72:819-832
In a thermal neutron reactor, multiple recycle of U-Pu fuel is not possible due to degradation of fissile content of Pu in just one recycle. In the FBR closed fuel cycle, possibility of multi-recycle has been recognized. In the present study, Pu-239
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::715a760e6093f3abad5bb48b531a9b52
https://doi.org/10.1007/s12043-009-0074-z
https://doi.org/10.1007/s12043-009-0074-z