Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Troy Haskin"'
Publikováno v:
Nuclear Science and Engineering. 197:S45-S56
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ffea948b4579b909273ebf425ec4bc5f
https://doi.org/10.1080/00295639.2023.2177076
https://doi.org/10.1080/00295639.2023.2177076
Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY Short Term Station Black Out
Autor:
Xiaomeng Dong, Xianmao Wang, Troy Haskin, Jun Wang, Lei Wu, Mckinleigh Mccabe, Michael L. Corradini
Publikováno v:
Nuclear Engineering and Design. 313:458-469
Accident tolerant fuel and cladding materials are being investigated to provide a greater resistance to fuel degradation, oxidation and melting if long-term cooling is lost in a Light Water Reactor (LWR) following an accident such as a Station Blacko
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::28708c50144ceb100adce2c9d8caee7a
https://doi.org/10.1016/j.nucengdes.2017.01.002
https://doi.org/10.1016/j.nucengdes.2017.01.002
Autor:
Suizheng Qiu, Jun Wang, Chen Wang, Michael L. Corradini, Wenxi Tian, Troy Haskin, Guanghui Su
Publikováno v:
Nuclear Engineering and Design. 307:119-129
Recently, MAAP and MELCOR research teams completed a set of accident simulations to reconstruct the Fukushima-Daiichi accident in order to better understand severe accident progression. One result from this work is that the predicted hydrogen generat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::78f875ce1392029ccd781df7b8bb0a0e
https://doi.org/10.1016/j.nucengdes.2016.06.034
https://doi.org/10.1016/j.nucengdes.2016.06.034
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 4
Accident tolerant fuels (ATF) and steam generator (SG) auxiliary feedwater (AFW) extended operation are two important methods to increase the coping time for nuclear power plant safety response. In light of recent efforts to investigate such methods,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cf5650a3c0f6191f599d6f33d2b73b13
https://doi.org/10.1115/1.4040887
https://doi.org/10.1115/1.4040887
Autor:
Troy Haskin, Guanghui Su, Wenxi Tian, Jun Wang, Michael L. Corradini, Suizheng Qiu, Wen Fu, Yapei Zhang
Publikováno v:
Annals of Nuclear Energy. 85:193-204
Core degradation evaluation of probability, progression and consequences of a core degradation accident is critical for evaluation of risk as well as its mitigation. However, research and modeling of severe accidents to date are limited, and their ac
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fe2efa9ca4972079a667af598c1c825e
https://doi.org/10.1016/j.anucene.2015.05.015
https://doi.org/10.1016/j.anucene.2015.05.015
Autor:
Wenxi Tian, Suizheng Qiu, Qing Lu, Yapei Zhang, Troy Haskin, Guanghui Su, Michael L. Corradini, Jun Wang
Publikováno v:
Nuclear Technology. 192:25-34
To better understand the MELCOR oxidation and degradation models, past work compared the MELCOR model to a CORA experiment (CORA Test 13). These MELCOR analyses specifically focused on fuel bundle heatup and clad oxidation when compared to CORA test
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f69fd0ba113b1cac6d8a00fefe3e7ef9
https://doi.org/10.13182/nt14-96
https://doi.org/10.13182/nt14-96
Publikováno v:
Volume 6: Thermal-Hydraulics.
Since the Fukushima accident, an increasing number of studies have considered Accident Tolerant Fuels and cladding properties that can improve the safety performance during an accident in a nuclear reactor. In a research project funded by the US Depa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5c0ad07e2e5771b72fef22378017dcc6
https://doi.org/10.1115/icone25-66523
https://doi.org/10.1115/icone25-66523
Autor:
Suizheng Qiu, Wenxi Tian, Yapei Zhang, Michael L. Corradini, Troy Haskin, Wen Fu, Guanghui Su, Jun Wang
Publikováno v:
Nuclear Engineering and Design. 276:191-201
MELCOR is widely used and sufficiently trusted for severe accident analysis. However, the occurrence of Fukushima has increased the focus on severe accident codes and their use. A MELCOR core degradation calculation was conducted at the University of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f03a30949c5812e0926280d3c09f09e3
https://doi.org/10.1016/j.nucengdes.2014.05.041
https://doi.org/10.1016/j.nucengdes.2014.05.041