Zobrazeno 1 - 10
of 56
pro vyhledávání: '"CHENG Maosong"'
Publikováno v:
He jishu, Vol 46, Iss 11, Pp 110604-110604 (2023)
BackgroundMolten salt reactors (MSRs) are fourth-generation advanced nuclear energy systems that exhibit characteristics such as high safety, high economy, nonproliferation, and sustainability. To ensure the safe operation of MSRs, identifying transi
Externí odkaz:
https://doaj.org/article/b435953c7c6f4d3c92568e29b27f1565
Publikováno v:
He jishu, Vol 46, Iss 11, Pp 10601-10601 (2023)
BackgroundNuclear power simulation technology has been widely applied in areas such as reactor design, safety analysis, independent safety evaluation, accident mitigation measures, design and optimization of control and protection system, verificatio
Externí odkaz:
https://doaj.org/article/b168e5a183674e759880e3851b42e556
Publikováno v:
He jishu, Vol 46, Iss 9, Pp 090402-090402 (2023)
BackgroundNuclear science and technology are closely related to the lives of people. However, nuclear radiation may harm the health of the general public; hence, nuclear radiation monitoring must be strengthened. A wired nuclear radiation monitoring
Externí odkaz:
https://doaj.org/article/c748d5809f1142c6b20dc3584fd94559
Autor:
ZONG Zhiwei, CHENG Maosong
Publikováno v:
He jishu, Vol 46, Iss 2, Pp 020602-020602 (2023)
BackgroundThe high-fidelity neutron transport calculation requires refined geometric modeling whilst the unstructured meshes have strong adaptability to copy with the changes bring by complex geometry structure, and overcome the deficiencies of struc
Externí odkaz:
https://doaj.org/article/c613b0e347bc4c1ea4331737889bb971
Publikováno v:
He jishu, Vol 45, Iss 9, Pp 090605-090605 (2022)
BackgroundWith the improvement of the computer computing power, it has become a feasible scheme to generate few-group constants by two-dimensional full-core transport calculations for molten salt reactors (MSRs).PurposeThis study aims to implement re
Externí odkaz:
https://doaj.org/article/916c43ee10414a1da4fcd4d5e1a8eaed
Publikováno v:
He jishu, Vol 45, Iss 7, Pp 070602-070602 (2022)
BackgroundThe natural circulation chloride cooled fast reactor (N3CFR) has the characteristics of simple structure, high inherent safety and good economy. It is an advanced fourth-generation nuclear energy system with development potential. However,
Externí odkaz:
https://doaj.org/article/2f52d3d472b1401aa0c034fddbb26a4e
Publikováno v:
He jishu, Vol 45, Iss 3, Pp 030603-030603 (2022)
BackgroundIn molten salt reactors (MSRs), the liquid fuel salt circulates in the whole primary loop. Part of the delayed neutron precursors (DNP) decay outside the reactor core, but most of the reactor fission power releases directly in the fuel salt
Externí odkaz:
https://doaj.org/article/5d2a0acfc61649efa508b4e9159e7e99
Publikováno v:
He jishu, Vol 44, Iss 6, Pp 060603-060603 (2021)
BackgroundThe liquid-fueled molten salt reactor (MSR) is one of the Generation IV advanced reactor concepts, which has unique advantages in aspects of safety, economy and nonproliferation. However, in view of the special neutron dynamics and hydrodyn
Externí odkaz:
https://doaj.org/article/4ac059a049294b3ca1f7b7426a73beea
Publikováno v:
He jishu, Vol 44, Iss 4, Pp 040603-040603 (2021)
BackgroundMolten salt reactor (MSR), a candidate of the Generation IV reactors, has the advantages of inherent safety and good neutron economy. The circulation flow of fuel, on-line refueling and reprocessing are the three features of liquid fuel in
Externí odkaz:
https://doaj.org/article/cec3d182e8da42188db040fdb71740ae
Autor:
Dai, Ming, Cheng, Maosong
Publikováno v:
In Annals of Nuclear Energy 1 December 2024 208