Zobrazeno 1 - 10
of 77
pro vyhledávání: '"fuel burn up"'
Akademický článek
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Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 10, Pp 3127-3132 (2021)
Feasibility study of burn-up analysis and monitoring using delayed fast neutrons was investigated at Missouri University of Science and Technology Reactor (MSTR). Burnt and fresh fuel elements were used to collect delayed fast neutron data for differ
Externí odkaz:
https://doaj.org/article/2c1aa6db4bb04c298f12999c6e14f7ba
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
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Publikováno v:
مجله علوم و فنون هستهای, Vol 41, Iss 2, Pp 133-143 (2020)
Monitoring the power distribution of reactor core is one of the most challenging issues in the safe operation of nuclear reactors. The Number and arrangement of detectors in a core monitoring system should be determined in a way that maximum amount o
Externí odkaz:
https://doaj.org/article/030084186742499b8c8ac131ef3c1486
Autor:
Tukiran Surbakti, Mochammad Imron
Publikováno v:
Jurnal Penelitian Fisika dan Aplikasinya, Vol 7, Iss 2, Pp 89-101 (2017)
The neutronic parameters are required in the safety analysis of the RSG-GAS research reactor. The RSG-GAS research reactor, MTR (Material Testing Reactor) type is used for research and also in radioisotope production. RSG-GAS has been operating for 3
Externí odkaz:
https://doaj.org/article/99e93bf0683e4195a1fba569163319b0
Publikováno v:
Nuclear Energy and Technology, Vol 3, Iss 4, Pp 255-259 (2017)
Burnable neutron absorbers such as gadolinium and erbium are used for compensating excess reactivity in nuclear reactors. Their daughter nuclides resulting from neutron absorption by erbium and gadolinium do not play important role from the viewpoint
Externí odkaz:
https://doaj.org/article/33b902c5418f4f52b9e8c783647862d4
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 10, Pp 3127-3132 (2021)
Feasibility study of burn-up analysis and monitoring using delayed fast neutrons was investigated at Missouri University of Science and Technology Reactor (MSTR). Burnt and fresh fuel elements were used to collect delayed fast neutron data for differ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::34f3416c51082b24fcb524ab885ebce1
http://www.sciencedirect.com/science/article/pii/S1738573321002114
http://www.sciencedirect.com/science/article/pii/S1738573321002114
Autor:
Gholamzadeh Zohreh, Hossein Feghhi Seyed Amir, Soltani Leila, Rezazadeh Marzieh, Tenreiro Claudio, Joharifard Mahdi
Publikováno v:
Nukleonika, Vol 59, Iss 4, Pp 129-136 (2014)
Decrease of the economically accessible uranium resources and the inherent proliferation resistance of thorium fuel motivate its application in nuclear power systems. Estimation of the nuclear reactor’s neutronic parameters during different operati
Externí odkaz:
https://doaj.org/article/25a65aa895f747f6be56186185a0ee0f
Publikováno v:
Nuclear Technology and Radiation Protection, Vol 26, Iss 1, Pp 45-49 (2011)
The burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1, reference operating core, has been carried out utilizing standard computer codes WIMS/D4, CITATION, and RELAP5/MOD3.4. Reactor codes WIMS/D4 and CITATION ha
Externí odkaz:
https://doaj.org/article/183a25862d3e487cb424aa2c17e0a159
Publikováno v:
Iranian Journal of Physics Research, Vol 10, Iss 3, Pp 273-280 (2010)
In this work, the Isfahan Miniature Neutron Source Reactor (MNSR) is first simulated using the WIMSD code, and its fuel burn-up after 7 years of operation ( when the reactor was revived by adding a 1.5 mm thick beryllium shim plate to the top of its
Externí odkaz:
https://doaj.org/article/1974840676e64f4cb150303e726712c2