Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Menglei Cui"'
Publikováno v:
Energies, Vol 16, Iss 4, p 1962 (2023)
The decay branch ratio is evaluated nuclear data related to the decay heat calculation in reactor safety analysis. Decay branch ratio data are inherently subjected to the “sum-to-one” constraint, making it difficult to generate perturbed samples
Externí odkaz:
https://doaj.org/article/e368a4279cf04d38b6da43a968322ecd
Publikováno v:
Energies, Vol 15, Iss 22, p 8369 (2022)
Quantifying fission product yield uncertainty contribution to reactor burnup calculation is an important aspect of pebble-bed High Temperature Gas-cooled Reactor (pebble-bed HTGR) uncertainty analysis. In this work, uncertainty propagation of fission
Externí odkaz:
https://doaj.org/article/e068d385992e40dfa0bcc52476a6cbb5
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
Uncertainty analyses of fission product yields are indispensable in evaluating reactor burnup and decay heat calculation credibility. Compared with neutron cross section, there are fewer uncertainty analyses conducted and it has been a controversial
Externí odkaz:
https://doaj.org/article/1afddcbfd21b4286acfbe26af9628b73
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
The accurate prediction of the neutronic and thermal-hydraulic coupling system transient behavior is important in nuclear reactor safety analysis, where a large-scale nonlinear coupling system with strong stiffness should be solved efficiently. In or
Externí odkaz:
https://doaj.org/article/84e2db9ff0ff4508acde9bf40055b1b5
Publikováno v:
Progress in Nuclear Energy. 150:104291
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e11fe3f4898c10a6ed4cc0640f45f42f
https://doi.org/10.1016/j.pnucene.2022.104291
https://doi.org/10.1016/j.pnucene.2022.104291
Publikováno v:
EPJ Web of Conferences, Vol 247, p 15006 (2021)
Multi-pass refueling scheme is a highlighted feature of pebble bed HTGR which spatially mixes the burnup calculation inside core. Such refueling scheme relate burnup calculation in one region of the core to others and thus affects the uncertainty pro
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::97d8e9bdf95fda5c096e7408c91b2d24
https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_15006.pdf
https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_15006.pdf
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
Uncertainty analyses of fission product yields are indispensable in evaluating reactor burnup and decay heat calculation credibility. Compared with neutron cross section, there are fewer uncertainty analyses conducted and it has been a controversial
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2ababaee5aa6bfad95efa55db4b92bee
Publikováno v:
Progress in Nuclear Energy. 138:103827
There has been increasing demand for uncertainty quantification (UQ) in the nuclear engineering community. Thus far, most uncertainty analyses have focused on light water reactor (LWR). As an innovative reactor, the pebble-bed high-temperature gas-co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f79e05ffaf6266daf2b3d76b229965d6
https://doi.org/10.1016/j.pnucene.2021.103827
https://doi.org/10.1016/j.pnucene.2021.103827