Zobrazeno 1 - 10
of 47
pro vyhledávání: '"Un Chul Lee"'
Sensitivity Analysis of Depletion Parameters for Heat Load Evaluation of PWR Spent Fuel Storage Pool
Autor:
Un-Chul Lee, In-Young Kim
Publikováno v:
Journal of the Korean Radioactive Waste Society. 9:237-245
As necessity of safety re-evaluation for spent fuel storage facility has emphasized after the Fukushima accident, accuracy improvement of heat load evaluation has become more important to acquire reliable thermal-hydraulic evaluation results. As grou
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3500e25f529859891ef058884935fa11
https://doi.org/10.7733/jkrws.2011.9.4.237
https://doi.org/10.7733/jkrws.2011.9.4.237
Publikováno v:
Annals of Nuclear Energy. 38:1527-1544
The purpose of this study was to develop a valid method to assess ageing effects on thermal-hydraulic elements for CANDU reactors. This method consisted of six steps. The ageing elements used in this method allowed for the immediate consideration of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cec5df75ea2ceaa8c64215117707d616
https://doi.org/10.1016/j.anucene.2011.03.009
https://doi.org/10.1016/j.anucene.2011.03.009
Autor:
Tae-Ho Woo, Un-Chul Lee
Publikováno v:
Energy Exploration & Exploitation. 29:337-355
The safeguard assessment has been investigated for the nuclear material in the nuclear power plants (NPPs). It is important to keep the secure operation in NPPs against possible terror attacks. The random sampling of Monte-Carlo method is used for th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::89311f9f5c883bcea1ece89d40ec24c2
https://doi.org/10.1260/0144-5987.29.3.337
https://doi.org/10.1260/0144-5987.29.3.337
Autor:
Un-Chul Lee, Tae-Ho Woo
Publikováno v:
Nuclear Engineering and Design. 241:826-831
Life extension is investigated as a safeguard assessment for the stability on the operation of the nuclear power plants (NPPs). The Cobb–Douglas function, one of the production functions, is modified for the nuclear safeguard in NPPs, which was dev
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7e513066e5fd49f6a29206f50e7219f4
https://doi.org/10.1016/j.nucengdes.2011.01.022
https://doi.org/10.1016/j.nucengdes.2011.01.022
Autor:
Un-Chul Lee, Tae-Ho Woo
Publikováno v:
Energy Exploration & Exploitation. 28:433-449
Power operations for secure performance are investigated using non-linear algorithm. The object of the simulation is to find the safe operation with safeguard for the life-extension of the operations. The network effect of the game theory is used for
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0b01e059ff3b47c9327fc8a5f2918587
https://doi.org/10.1260/0144-5987.28.6.433
https://doi.org/10.1260/0144-5987.28.6.433
Autor:
Tae-Ho Woo, Un-Chul Lee
Publikováno v:
Progress in Nuclear Energy. 52:456-461
The probabilistic safety assessment (PSA) has been investigated for the very high temperature reactor (VHTR). It is difficult to make the quantification of the PSA because the operation and experience data are deficient. Therefore, the necessity of t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c536ba1e0b271c9a14b0fbb51e7fe2a1
https://doi.org/10.1016/j.pnucene.2009.10.001
https://doi.org/10.1016/j.pnucene.2009.10.001
Publikováno v:
Annals of Nuclear Energy. 37:730-739
The purpose of this study is to develop a severe accident (SA) analysis method that is more reliable thorough transferring the physical status of the plant predicted by RELAP5 computer code to MAAP4 computer code. The methodology of the linkage analy
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::305e4b2e4bcc0a3429e0c9974375197b
https://doi.org/10.1016/j.anucene.2010.01.012
https://doi.org/10.1016/j.anucene.2010.01.012
Autor:
Tae-Ho Woo, Un-Chul Lee
Publikováno v:
Energy. 35:1799-1804
The probabilistic safety assessment (PSA) for gas-cooled nuclear power plants has been investigated where the operational data are deficient, because there is not any commercial gas-cooled nuclear power plant. Therefore, it is necessary to use the st
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::849d5ef0289b4601cebd0a126ea24165
https://doi.org/10.1016/j.energy.2009.12.034
https://doi.org/10.1016/j.energy.2009.12.034
Autor:
Un-Chul Lee, Tae-Ho Woo
Publikováno v:
Nuclear Engineering and Design. 239:3014-3020
The probabilistic safety assessment (PSA) has been studied for the very high temperature reactor (VHTR). There is a difficulty to make the quantification of the PSA due to the deficiency of the operation and experience data. So, it is necessary to us
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::27294d959eb1d0a3e841a57635fc5435
https://doi.org/10.1016/j.nucengdes.2009.08.002
https://doi.org/10.1016/j.nucengdes.2009.08.002
Autor:
Tae-Ho Woo, Un-Chul Lee
Publikováno v:
Annals of Nuclear Energy. 36:1299-1306
A dynamic safety assessment has been developed for the passive system in the very high temperature gas cooled reactor (VHTR), when the operational data are insufficient. It was required to make use of the characteristics of the reactor in order to co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cf15232fa113af4b526d955939a3255b
https://doi.org/10.1016/j.anucene.2009.07.011
https://doi.org/10.1016/j.anucene.2009.07.011