Zobrazeno 1 - 10
of 18
pro vyhledávání: '"Liang-Che Dai"'
Autor:
Liang-Che Dai, 戴良哲
104
This study consists of two objectives. The first objective is the implementation and assessments of the Moody HEM model of RELAP5-3D code. The second objective is the applicability and assessments for RELAP5-3D light water reactor containmen
This study consists of two objectives. The first objective is the implementation and assessments of the Moody HEM model of RELAP5-3D code. The second objective is the applicability and assessments for RELAP5-3D light water reactor containmen
Externí odkaz:
http://ndltd.ncl.edu.tw/handle/45552093546812636110
Publikováno v:
Nuclear Science and Engineering. 182:96-103
According to “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants” (NUREG-0800) of the U.S. Nuclear Regulatory Commission, the homogeneous and thermal equilibriu...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3c51207ca1784d8968df98de03fe7263
https://doi.org/10.13182/nse14-145
https://doi.org/10.13182/nse14-145
Publikováno v:
Nuclear Engineering and Design. 280:86-93
Units 1 and 2 of the Maanshan nuclear power station are the typical Westinghouse three-loop PWR (pressurized water reactor) with large dry containments. In this study, the containment analysis program GOTHIC is adopted for the dry containment pressur
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1a24d9edd26fe158352cb286af9cfe58
https://doi.org/10.1016/j.nucengdes.2014.09.007
https://doi.org/10.1016/j.nucengdes.2014.09.007
Publikováno v:
Nuclear Engineering and Design. 247:106-115
Lungmen Nuclear Power Plant in Taiwan is a GE-designed twin-unit Advanced Boiling Water Reactor (ABWR) plant with rated thermal power of 3926 MWt. Both units are currently under construction. In the Lungmen Final Safety Analysis Report (FSAR) section
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e1b4a812428119a074f617a48adde37b
https://doi.org/10.1016/j.nucengdes.2012.02.012
https://doi.org/10.1016/j.nucengdes.2012.02.012
Publikováno v:
Nuclear Engineering and Design. 241:1548-1558
Chinshan Nuclear Power Plant in Taiwan is a GE-designed twin-unit BWR/4 plant with original licensed thermal power (OLTP) of 1775 MWt for each unit. Recently, the Stretch Power Uprate (SPU) program for the Chinshan plant is being conducted to uprate
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b366867e07e8d13089a081e35d9093cd
https://doi.org/10.1016/j.nucengdes.2011.02.004
https://doi.org/10.1016/j.nucengdes.2011.02.004
Publikováno v:
Nuclear Technology. 169:50-60
The limiting blowdown event for the design of an advanced boiling water reactor (ABWR) containment shifts from a conventional recirculation line break to a feedwater line break (FWLB) by implementing reactor internal pumps. As a result, coupled blowd
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b92115ba3b3b06c0ad233664ce402a5f
https://doi.org/10.13182/nt10-a9342
https://doi.org/10.13182/nt10-a9342
Publikováno v:
Annals of Nuclear Energy. 36:917-922
The fourth nuclear power plant in Taiwan is an advanced boiling water reactor (ABWR) and is scheduled to be in commercial operation in late 2009. However, it is highly suspected by the reactor vendor that the turbine-driven reactor feedwater pumps (T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ebbc96191e43717b3b0f77a3073ab1a1
https://doi.org/10.1016/j.anucene.2009.03.008
https://doi.org/10.1016/j.anucene.2009.03.008
Publikováno v:
Nuclear Technology. 166:146-155
In the innovative design of the advanced boiling water reactor (ABWR), conventional recirculation loops are removed and replaced by multiple reactor internal pumps. Therefore, there is no major penetration of the reactor pressure vessel (RPV) below t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::331bfc242e15d6c6b836d099b918f7ca
https://doi.org/10.13182/nt09-a7401
https://doi.org/10.13182/nt09-a7401
Publikováno v:
Annals of Nuclear Energy. 36:520-526
Because a greater risk than expected is introduced during midloop operation for typical PWRs, the performance of training simulator of Taiwan’s Maanshan 3-loop PWR plant was verified and upgraded for midloop operation (MLO) simulation. Besides, pla
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4bfd7603765e3605d581708951e0b23a
https://doi.org/10.1016/j.anucene.2008.12.014
https://doi.org/10.1016/j.anucene.2008.12.014
Publikováno v:
Nuclear Technology. 153:184-196
The blowdown of feedwater (FW) line breaks (FWLBs) has been successfully analyzed by using the Appendix K version of RELAP5-3D. To adequately simulate a feedwater blowdown event, one must consider the main steam system, the turbine system, the moistu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b4afa7d85d145c5af1c08ef10a7dcfb
https://doi.org/10.13182/nt06-a3699
https://doi.org/10.13182/nt06-a3699