Zobrazeno 1 - 10
of 381
pro vyhledávání: '"SHAN Jianqiang"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 4, Pp 1213-1224 (2024)
The liquid lead-bismuth cooled fast reactor has been in a single-phase, low-pressure, and high-temperature state for a long time during operation. Considering the requirement of calculation efficiency for long-term transient accident calculation, bas
Externí odkaz:
https://doaj.org/article/6b747edc6082456a81a91d51a7f7308b
Publikováno v:
He jishu, Vol 47, Iss 2, Pp 93-108 (2024)
Background A megawatt-class nuclear power system has been developed by coupling a heat pipe reactor with a supercritical carbon dioxide (S-CO2) Brayton cycle. This system offers advantages in terms of high safety, power density, and compactness.
Externí odkaz:
https://doaj.org/article/37c674317b42476d923f14ad67e52281
Publikováno v:
He jishu, Vol 47, Iss 1, Pp 115-123 (2024)
BackgroundA heat pipe reactor is ideal for underwater unmanned vehicles (UUV) because it is simple, is compact, and has high inherent safety.PurposeA passive residual heat removal system that uses natural circulation to cool the adiabatic section of
Externí odkaz:
https://doaj.org/article/6073e6c1e62e46139b041cb4b1418e1a
Publikováno v:
Yuanzineng kexue jishu, Vol 57, Iss 3, Pp 493-502 (2023)
An accurate two-phase flow model is an important basis for nuclear reactor safety analysis. The classical two-fluid six-equation model used in many current thermal-hydraulic programs has an ill-posed problem, if a small disturbance is introduced, the
Externí odkaz:
https://doaj.org/article/2c0d8ef56ffe44f6ace72e341bae40c8
Publikováno v:
He jishu, Vol 46, Iss 11, Pp 110606-110606 (2023)
BackgroundThe in-vessel retention (IVR) strategy is an important measure for mitigating severe reactor accidents. It has been successfully applied to the severe-accident management of advanced pressurized water reactors such as the AP1000, HPR1000, a
Externí odkaz:
https://doaj.org/article/a8d7cb541c104f02b0fb85a26aeae6f3
Publikováno v:
He jishu, Vol 46, Iss 11, Pp 110603-110603 (2023)
BackgroundThe kilowatt reactor using stirling technology (KRUSTY) is a heat-pipe-cooled reactor experimental system that uses a Stirling engine to convert thermal energy to electricity, it is the only one published experimental data for heat-pipe-coo
Externí odkaz:
https://doaj.org/article/004fb1c3dc2a469faa401bdb606af3d5
Publikováno v:
He jishu, Vol 46, Iss 10, Pp 100607-100607 (2023)
BackgroundLoss of Coolant Accidents (LOCAs) is a crucial research topic for nuclear reactor safety analysis, and understanding the thermal–hydraulic behavior of the rod bundle channels during the reflooding stage of a LOCA is essential.PurposeThis
Externí odkaz:
https://doaj.org/article/ee6aa8007ecc43659b32d79a13664c74
Publikováno v:
He jishu, Vol 46, Iss 7, Pp 070606-070606 (2023)
BackgroundIn a pressurized water reactor (PWR) loss-of-coolant accident (LOCA), high temperature and high internal pressure of the fuel rod can lead to ballooning of fuel rod cladding, which causes a partial blockage of flow area in a subchannel. Suc
Externí odkaz:
https://doaj.org/article/fa8b849cddcc4afb930556c9ddc00b0e
Publikováno v:
He jishu, Vol 46, Iss 5, Pp 050604-050604 (2023)
PurposeThis study aims to improve the low accuracy of the aerosol model in the ISAA code by developing high-precision natural deposition model of aerosol in the containment.MethodsFirstly, the aerosol dynamic shape factor was introduced to correct th
Externí odkaz:
https://doaj.org/article/6228fc34182c4c788598392760e3d3fa
Publikováno v:
He jishu, Vol 45, Iss 11, Pp 110604-110604 (2022)
BackgroundHeat pipe cooled reactors (HPR) have good inherent safety. In the early stage of core design, heat pipe failure accident is usually one of the design basis accidents that need to be considered.PurposeThis study aims to analyze the neutronic
Externí odkaz:
https://doaj.org/article/de090f591bc7442aa57016c38c89b85d