Zobrazeno 1 - 10
of 10
pro vyhledávání: '"Amod Kishore Mallick"'
Publikováno v:
Physics Open, Vol 17, Iss , Pp 100190- (2023)
Pebble-bed High Temperature reactors (HTR) are proposed to generate heat for power production and process heat application such as Hydrogen (H2) production. A HTR fuel pebble consists of random distribution of several thousands of fuel particles, cal
Externí odkaz:
https://doaj.org/article/c7f272ce6954468b80e59c43eb596cc3
Publikováno v:
Physics Open, Vol 17, Iss , Pp 100179- (2023)
The solution of the neutron transport equation is the basic input for the reactor physics design of a nuclear reactor system. Because of the complexities of geometry and cross-section data, the neutron transport equation is generally solved using num
Externí odkaz:
https://doaj.org/article/7e25ac33fbd746cfa74ce0ce18cf1fd0
Publikováno v:
Nuclear Science and Engineering. 196:927-942
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::99cc8d0a81ed7da1dce38373f444ff61
https://doi.org/10.1080/00295639.2022.2043541
https://doi.org/10.1080/00295639.2022.2043541
Autor:
Rajeev Kumar, Amod Kishore Mallick, Anindita Sarkar, S. Samanta, Umasankari Kannan, Deep Bhandari
Publikováno v:
Materials Today: Proceedings. 38:3041-3045
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::be2dfa941d18c90d2805cde769fa05c1
https://doi.org/10.1016/j.matpr.2020.09.385
https://doi.org/10.1016/j.matpr.2020.09.385
Publikováno v:
Life Cycle Reliability and Safety Engineering. 9:219-223
Monte Carlo criticality calculation is an iterative process which requires a guess fission distribution to start the simulations. It is important to assess when the fission source has converged, so that a sufficient number of the initial batches are
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0c4594bcb6ec9ee81175ea4aa5cc25de
https://doi.org/10.1007/s41872-020-00118-z
https://doi.org/10.1007/s41872-020-00118-z
Autor:
Amod Kishore Mallick, Rajeev Kumar, Sudipta Samanta, Yogesh Upreti, Kapil Deo, Deep Bhandari, Umasankari Kannan, V. Shivakumar, Sharad Kumar Verma, S.K. De, Avaneesh Sharma
Publikováno v:
Nuclear Engineering and Design. 398:111973
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::33ee60f57d72d0e25df0d5b75b1fb75d
https://doi.org/10.1016/j.nucengdes.2022.111973
https://doi.org/10.1016/j.nucengdes.2022.111973
Publikováno v:
Nuclear Science and Engineering. 193:868-883
In a recent paper, we described the development of a method for calculating exact collision probabilities between different regions (namely, fuel kernels, graphite matrix, moderator, and co...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::21199e98066f259c428ec37696d66827
https://doi.org/10.1080/00295639.2019.1576453
https://doi.org/10.1080/00295639.2019.1576453
Autor:
Amod Kishore Mallick, Anurag Gupta
Publikováno v:
Annals of Nuclear Energy. 166:108783
Monte Carlo neutron transport codes are widely used for criticality simulation of full reactor core owing to their ability to model complex geometry in exact details, and of using the best available nuclear data. These codes are generally based on th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::74d0431e18b3542e0093ec64b705f681
https://doi.org/10.1016/j.anucene.2021.108783
https://doi.org/10.1016/j.anucene.2021.108783
Autor:
Kapil Deo, Tej Singh, Ranjit Sharma, Y. S. Rana, SK Prasad, Amod Kishore Mallick, Umasankari Kannan, Prabhakar V. Varde, S. Bhattacharya, S. Samanta, Rajeev Kumar, Abhishek Mishra
Publikováno v:
Life Cycle Reliability and Safety Engineering. 6:149-166
Dhruva is a 100 MW tank-type research reactor with natural metallic uranium as fuel and heavy water as coolant, moderator, and reflector. The reactor is utilized for production of a large variety of radioisotopes for fulfilling growing demands of var
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::66b8db7a8c5fbfe1a75f75549b401ae4
https://doi.org/10.1007/s41872-017-0018-4
https://doi.org/10.1007/s41872-017-0018-4