Safety evaluation of small-break LOCA with various locations and sizes for SMART adopting fully passive safety system using MARS code (English)
- New search for: Chun, Ji-Han
- New search for: Chung, Bub-Dong
- New search for: Lee, Guy-Hyung
- New search for: Bae, Kyoo-Hwan
- New search for: Kim, Young-In
- New search for: Chung, Young-Jong
- New search for: Kim, Keung-Koo
- New search for: Chun, Ji-Han
- New search for: Chung, Bub-Dong
- New search for: Lee, Guy-Hyung
- New search for: Bae, Kyoo-Hwan
- New search for: Kim, Young-In
- New search for: Chung, Young-Jong
- New search for: Kim, Keung-Koo
In:
Nuclear Engineering and Design
;
277
;
138-145
;
2014
-
ISSN:
- Article (Journal) / Electronic Resource
-
Title:Safety evaluation of small-break LOCA with various locations and sizes for SMART adopting fully passive safety system using MARS code
-
Contributors:Chun, Ji-Han ( author ) / Chung, Bub-Dong ( author ) / Lee, Guy-Hyung ( author ) / Bae, Kyoo-Hwan ( author ) / Kim, Young-In ( author ) / Chung, Young-Jong ( author ) / Kim, Keung-Koo ( author )
-
Published in:Nuclear Engineering and Design ; 277 ; 138-145
-
Publisher:
- New search for: Elsevier B.V.
-
Publication date:2014-06-22
-
Size:8 pages
-
ISSN:
-
DOI:
-
Type of media:Article (Journal)
-
Type of material:Electronic Resource
-
Language:English
-
Source:
Table of contents – Volume 277
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
- 1
-
Hydride fuel irradiation in MITR-II: Thermal design and validation resultsKim, Sung Joong / Carpenter, David / Kohse, Gordon / Hu, Lin-wen et al. | 2014
- 15
-
Influence of stiffness on CHF for horizontal tubes under LPLF conditionsBaburajan, P.K. / Bisht, Govind Singh / Gaikwad, Avinash J. / Prabhu, S.V. et al. | 2014
- 28
-
Numerical modelling of radionuclide inventory for RBMK irradiated nuclear fuelŠmaižys, A. / Poškas, P. / Narkūnas, E. / Bartkus, G. et al. | 2014
- 36
-
Safety verification for the ECCS driven by the electrically 4 trains during LBLOCA reflood phase using ATLASPark, Yusun / Park, Hyun-sik / Kang, Kyoung-ho / Choi, Nam-hyun / Min, Kyoung-ho / Choi, Ki-yong et al. | 2014
- 46
-
Experimental study of the role of nanoparticles in sodium–water reactionPark, Gunyeop / Kim, Soo Jae / Kim, Moo Hwan / Park, Hyun Sun et al. | 2014
- 55
-
Irradiation-induced effects of proton irradiation on zirconium carbides with different stoichiometriesHuang, Y. / Maier, B.R. / Allen, T.R. et al. | 2014
- 64
-
Evaluation of seismic behavior of soils under nuclear containment structures via dynamic centrifuge testHa, Jeong Gon / Kim, Dong-Soo et al. | 2014
- 76
-
Numerical analysis of steady state and transient analysis of high temperature ceramic plate-fin heat exchangerNagarajan, Vijaisri / Chen, Yitung / Wang, Qiuwang / Ma, Ting et al. | 2014
- 95
-
Actinides in irradiated graphite of RBMK-1500 reactorPlukienė, R. / Plukis, A. / Barkauskas, V. / Gudelis, A. / Gvozdaitė, R. / Duškesas, G. / Remeikis, V. et al. | 2014
- 106
-
Assessment of accident management measures on early in-vessel station blackout sequence at VVER-1000 pressurized water reactorsTusheva, P. / Schäfer, F. / Reinke, N. / Kamenov, Al. / Mladenov, I. / Kamenov, K. / Kliem, S. et al. | 2014
- 117
-
Performance and first results of fission product release and transport provided by the VERDON facilityGallais-During, A. / Bonnin, J. / Malgouyres, P.-P. / Morin, S. / Bernard, S. / Gleizes, B. / Pontillon, Y. / Hanus, E. / Ducros, G. et al. | 2014
- 124
-
A first system/CFD coupled simulation of a complete nuclear reactor transient using CATHARE2 and TRIO_U. Preliminary validation on the Phénix Reactor Natural Circulation TestBavière, R. / Tauveron, N. / Perdu, F. / Garré, E. / Li, S. et al. | 2014
- 124
-
A first system/CFD coupled simulation of a complete nuclear reactor transient using CATHARE2 and TRIO_U. Preliminary validation on the Phenix Reactor Natural Circulation TestBaviere, R. / Tauveron, N. / Perdu, F. / Garre, E. / Li, S. et al. | 2014
- 138
-
Safety evaluation of small-break LOCA with various locations and sizes for SMART adopting fully passive safety system using MARS codeChun, Ji-Han / Chung, Bub-Dong / Lee, Guy-Hyung / Bae, Kyoo-Hwan / Kim, Young-In / Chung, Young-Jong / Kim, Keung-Koo et al. | 2014
- 146
-
Comparison between continuous and localized methods to evaluate the flow rate through containment concrete structuresJason, L. / Masson, B. et al. | 2014
- 154
-
Numerical analysis on supercritical flow instabilities using APROSLi, Yan / Lu, Daogang / Liu, Yu / Zeng, Xiaokang et al. | 2014
- 163
-
Experimental studies of spent fuel burn-up in WWR-SM reactorAlikulov, Sh. A. / Baytelesov, S.A. / Boltaboev, A.F. / Kungurov, F.R. / Menlove, H.O. / O’Connor, W. / Osmanov, B.S. / Salikhbaev, U.S. et al. | 2014
- 166
-
Use of curium neutron flux from head-end pyroprocessing subsystems for the High Reliability Safeguards methodologyBorrelli, R.A. et al. | 2014
- 173
-
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactorLuzzi, Lelio / Cammi, Antonio / Di Marcello, Valentino / Lorenzi, Stefano / Pizzocri, Davide / Van Uffelen, Paul et al. | 2014
- 188
-
Transient thermal analysis for radioactive liquid mixing operations in a large-scaled tankLee, Si Y. / Smith, Frank G. et al. | 2014
- 198
-
Evaluation of radioactivity and gamma spectra in the secondary coolant system of PWRLiu, Zhaohuan / Chen, Yixue / Li, Lu / Song, Wen / Sun, Yeshuai et al. | 2014
- 203
-
Passive systems failure probability estimation by the meta-AK-IS2 algorithmCadini, Francesco / Santos, Francisco / Zio, Enrico et al. | 2014
- 212
-
Preliminary conceptual design and cost estimation for Korea Advanced Pyroprocessing Facility Plus (KAPF+)Ko, Won Il / Lee, Ho Hee / Choi, Sungyeol / Kim, Sung-Ki / Park, Byung Heung / Lee, Hyo Jik / Kim, In Tae / Lee, Han Soo et al. | 2014
- 225
-
Preliminary conceptual design and cost estimation for SFR Fuel Manufacturing Facility (SFMF)Ko, Won Il / Lee, Ho Hee / Choi, Sungyeol / Kim, Ki Hwan / Kim, Sung-Ki / Park, Byung Heung / Lee, Hyo Jik / Kim, In Tae / Lee, Han Soo et al. | 2014
- 234
-
Dynamic analysis of once-through and closed fuel cycle economics using Monte Carlo simulationChoi, Sungyeol / Lee, Hyo Jik / Ko, Won Il et al. | 2014
- 248
-
A proposed aging management program for alkali silica reactions in a nuclear power plantSaouma, Victor E. / Hariri-Ardebili, Mohammad A. et al. | 2014
- 265
-
Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysisLazaro, A. / Schikorr, M. / Mikityuk, K. / Ammirabile, L. / Bandini, G. / Darmet, G. / Schmitt, D. / Dufour, Ph. / Tosello, A. / Gallego, E. et al. | 2014