Zobrazeno 1 - 10
of 1 395
pro vyhledávání: '"htgr"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 9, Pp 3835-3850 (2024)
The high-temperature gas-cooled reactor (HTGR) with spherical fuel elements contains complex pebble flow. The flow behavior of pebbles is influenced by various factors, such as pebble density, friction coefficient, wall structure, and discharge port
Externí odkaz:
https://doaj.org/article/d53f82b4d69c41be920b3115a93cc960
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 4, Pp 1310-1319 (2024)
The reactor cavity cooling system (RCCS) is a passive reactor safety system commonly present in the designs of High-Temperature Gas-cooled Reactors (HTGR) that removes heat from the reactor pressure vessel by means of natural convection and radiation
Externí odkaz:
https://doaj.org/article/0ac46b06f50241a5aee52901d956f687
Akademický článek
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Autor:
Seddon Atkinson, Takeshi Aoki
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 3, Pp 785-792 (2024)
This article provides an overview of the design methodology used to develop a conceptual set of reactivity control mechanism of a micro reactor based on the U-Battery. The U-Battery is based on remote deployment and therefore it is favourable to prov
Externí odkaz:
https://doaj.org/article/fab2f168ef6f426a9cbfd03502e2e3ec
Autor:
Kuniyoshi Takamatsu, Shumpei Funatani
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 3, Pp 832-845 (2024)
Reactor cavity cooling systems (RCCSs) comprising passive safety features use the atmosphere as a coolant, which cannot be lost. However, their drawback is that they are easily affected by atmospheric disturbances. To realize the commercial applicati
Externí odkaz:
https://doaj.org/article/c6751d5acba34e33b7fc5f0f88ff0965
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 3, Pp 933-940 (2024)
A macroscopic cross section generation model was developed for the conceptual horizontal, compact high temperature gas reactor (HC-HTGR). Because there are many sources of spectral effects in the design and analysis of the core, conventional LWR meth
Externí odkaz:
https://doaj.org/article/4bde5891291b4358b9aaa513b4c54a97
Autor:
M.C. Potgieter, C.G. du Toit
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 3, Pp 959-965 (2024)
The High Temperature Test Unit (HTTU) was an experimental set-up to conduct separate and integral effects tests of the Pebble Bed Modular Reactor (PBMR) core. The annular core consisted of a randomly packed bed of uniform spheres. Natural convection
Externí odkaz:
https://doaj.org/article/1c30d2af13fa402f9fa0ea0f7040e56f
Autor:
ZHENG Wei1, HE Xuedong1, YIN Huaqiang1, DU Bin1, LI Haoxiang1, MA Tao1, PU Yang2, WANG Shangjun
Publikováno v:
Yuanzineng kexue jishu, Vol 58, Iss 1, Pp 189-197 (2024)
The helium coolant in the primary circuit of the high-temperature gas-cooled reactor (HTGR) contains trace of impurities such as CO, H2, H2O, and CH4, which have an adverse effect on the structural materials at elevated temperature. Mainly, the corro
Externí odkaz:
https://doaj.org/article/114ce1df61664f13b7debeb8a51d7f8c
Publikováno v:
Energies, Vol 17, Iss 22, p 5702 (2024)
This study analyzes the thermodynamic and economic viability of modified high-temperature gas-cooled reactor (HTGR) gas-steam combined heat and power (CHP) systems compared to conventional CHP plants. The research addresses the critical need for effi
Externí odkaz:
https://doaj.org/article/db05af38f45d41ddbb0d8594ce1cb7f3
Publikováno v:
Energies, Vol 17, Iss 21, p 5366 (2024)
Preventing severe corrosion incidents caused by air ingress accidents in high-temperature gas-cooled reactors (HTGRs) while improving heat removal efficiency from the core is of paramount importance. To enhance both safety and efficiency, a sleeveles
Externí odkaz:
https://doaj.org/article/29960ea6cb724342a468b715d5f0e5c3