Propagation Of Uncertainty In Input Parameters Of A LWR Model By Sampling MCNP Calculations - Criticality Analysis (English)
- New search for: De A. M. Campolina, D.
- New search for: Pereira, C.
- New search for: Veloso, M.A.F.
- New search for: De A. M. Campolina, D.
- New search for: Pereira, C.
- New search for: Veloso, M.A.F.
In:
Advances in nuclear power plants
;
556-560
;
2013
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ISBN:
- Conference paper / Print
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Title:Propagation Of Uncertainty In Input Parameters Of A LWR Model By Sampling MCNP Calculations - Criticality Analysis
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Contributors:
-
Conference:International congress, Advances in nuclear power plants ; 2013 ; Jeju Island, Korea
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Published in:Advances in nuclear power plants ; 556-560
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Publisher:
- New search for: Korean Nuclear Society
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Place of publication:Daejeon
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Publication date:2013-01-01
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Size:5 pages
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Remarks:Includes bibliographical references and index; British Library not licensed to copy
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ISBN:
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Type of media:Conference paper
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Type of material:Print
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Language:English
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Keywords:
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Source:
© Metadata Copyright the British Library Board and other contributors. All rights reserved.
Table of contents conference proceedings
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.
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- 10
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Performances of UO~2-BeO Composite Fuel Using FRAPTRANRevankar, S.T. / Chandramouli, D. et al. | 2013
- 17
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- 24
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- 38
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- 46
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TRACE/PARCS Evaluation of Potentially Limiting ATWS Events with Core Instability for the ABWRYarsky, P. et al. | 2013
- 56
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- 65
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- 73
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- 81
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- 97
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Development of Hydride Neutron Absorber for Fast Reactor - High Temperature Stability of Hafnium HydrideKonashi, K. / Yato, T. / Yumi / Yamada et al. | 2013
- 1046
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Development of Calculation Method of Sensitivities for Light Water ReactorsTakeda, T. / Foad, B. et al. | 2013
- 1053
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Development of Low Pressure Drop Steam SeparatorSumikawa, T. / Yasuda, K. / Nishida, K. / Katono, K. / Ishida, N. et al. | 2013
- 1062
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Fluoride-Salt-Cooled High-Temperature Reactor Market Strategy With Peak Electricity And Process HeatCurtis, D. / Short, M. / Forsberg, C. et al. | 2013
- 1069
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State of SAMPSON Code Development for the Analysis of Fukushima Daiichi Severe AccidentPellegrini, M. / Mizouchi, H. / Suzuki, H. / Naitoh, M. et al. | 2013
- 1077
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Preliminary Design of a Prismatic Core Fluoride Salt-Cooled High Temperature Test Reactor (FHTR)Richard, J. / Short, M.P. / Don, S. / Romatoski, R.R. / Hu, L.W. / Forsberg, C. et al. | 2013
- 1087
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Maintenance Activities To Guarantee The Performances Of The Steam Generators In The Nuclear Power PlantD Annucci, F. et al. | 2013
- 1098
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The EUR: A Great Achivement And Still On Its WayDe Fraguier, E. / Vanhoenacker, L. / Rousselot, O. / Bellens, V. / Beolet, M. et al. | 2013
- 1104
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Insights From Development Of Standard Equipment Management Model In Nuclear Power PlantsChang, H.-S. / Ju, T.-Y. / Kim, J.-W. et al. | 2013
- 1111
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Comparison of 0.8 MeV Electron-Irradiation Effects on the Oxidation of Selected Nuclear Graphite Grades for VHTRChi, S.-H. / Hong, S.-D. et al. | 2013
- 1119
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Innovation & Integration of Processes for Preventing Unplanned Plant Trips from an Equipment Life Cycle Management PerspectiveLee, B.-S. / Lee, E.-C. / Chi, M.-G. et al. | 2013
- 1123
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Establishment of a Maintenance Program to Prevent Loss of Offsite Power in Nuclear Power PlantsLee, E.-C. / Bae, Y.-K. / Chi, M.-G. et al. | 2013
- 1126
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Verification and Validation of the Coupled CUPID/MARS CodePark, I.K. / Lee, S.W. / Lee, J.R. / Yoon, H.Y. et al. | 2013
- 1138
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Evaluation on Structural Integrity for the Postulated Primary Water Stress Corrosion Cracking on Bottom-Mounted Nozzles in a Pressurized Water Reactor Nuclear Power PlantLee, K. / Lee, S. / Kim, J. / Na, M. et al. | 2013
- 1145
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Development of Ulchin Vitrification Facility for Vitrifying Radioactive Wastes Generated From Nuclear Power PlantsKim, C.-W. / Jo, H.-J. et al. | 2013
- 1151
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Effects of Seawater Flooding on the Properties of CSPEKim, I.-Y. / Goo, C.-S. / Lee, J.-H. / Jin, B.-S. / Kang, M.-K. / Shin, Y.-D. et al. | 2013
- 1156
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Design Improvement to Prevent Low-Pressure CO2 Fire Suppression System from Plugging up with Dry iceJee, M.-H. / Kim, H.-T. / Kim, Y.-J. et al. | 2013
- 1161
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Optimum Design of Lead Spectrometer for Spent Fuel Fissile AssayLee, Y. / Park, C.J. / Song, K.C. et al. | 2013
- 1165
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Evaluation of Two-phase Flow and Water-hammer Effects on a Nuclear Power Plant having Non-Safety Related Cooling Water SystemShin, H.-Y. / Won, S.-Y. / Lee, K.-S. / Lee, J.-Y. / Lee, K.-H. et al. | 2013
- 1170
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Optimum Alternate Injection Strategy for the Severe Accident Initiated from LOCAHuong, V.T. / Kim, T. / Kim, D. / Song, J. et al. | 2013
- 1177
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Thermal-hydraulic Analysis for Reactor Vessel Upper Plenum of Sodium-cooled Fast ReactorYoon, J. / Kim, S.-O. / Lee, T.-H. et al. | 2013
- 1184
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Out-of pile Mechanical Properties of HT9 Fuel Cladding Tube for Sodium-cooled Fast Reactor (SFR)Kim, J.H. / Baek, J.H. / Kim, S.H. / Lee, C.B. et al. | 2013
- 1188
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Severe Accident Research Efforts after Fukushima AccidentSong, J.H. / Kim, D.H. / Hong, S.W. / Kim, H.Y. / Ha, G.S. / Song, Y.M. / Park, R.J. et al. | 2013
- 1193
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Performance Test of Very High Temperature Helium Experimental LoopKim, C.S. / Chae, J.S. / Hong, S.-D. et al. | 2013
- 1201
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Effects of Channel Configuration on Thermal Performance of the Printed-Circuit Heat ExchangerLee, S.-M. / Kim, K.-Y. et al. | 2013
- 1207
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Innovative Severe Accident Mitigation Measures for a PWRSong, J.H. / Kim, H.Y. / Park, R.J. / Ha, K.S. et al. | 2013
- 1213
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Concept Design of SMART Mounted GBSLee, K.-H. / Lee, J.I. / Woo, I.-G. / Han, J.-H. / Lee, P.-S. et al. | 2013
- 1221
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Removal Of Sludge Accumulated In Nuclear Steam Generator By Ultrasound CavitationJeong, W.-T. / Kim, S.-T. / Yoon, S.-J. / Kim, T.-H. et al. | 2013
- 1226
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Extracting the List of Necessary Information for Supporting Human Reliability Analysis (HRA)Park, J. / Jung, W. et al. | 2013
- 1234
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Design Characteristics Of HIPER16™ Fuel Assembly For OPR1000 And APR1400Jeon, S.-Y. / Park, N.-G. / Suh, J.-M. / Jeon, K.-L. et al. | 2013
- 1241
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Fault-Tolerant Design for Advanced Diverse Protection SystemOh, Y.G. / Yim, H.S. / Baek, S.M. / Lee, S.J. et al. | 2013
- 1248
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Lessons Learned from Validation Tests of SMART MMIS DesignSuh, Y.S. / Kim, S.K. / Park, G.O. et al. | 2013
- 1255
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Challenging Issues In iPWR With Single Phase Water Naturally Circulating SystemWibisono, A.F. / Ahn, Y. / Williams, W.C. / Addad, Y. / Lee, J.I. et al. | 2013
- 1263
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CFD Simulation For The Effect Of Flow Skirt Geometry On Reactor Internal Flow In The Scaled APR+Lee, G.H. / Bang, Y.S. / Woo, S.W. / Kim, D.H. / Kang, M.K. et al. | 2013
- 1271
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Analysis of Hydrogen Induced Cracking for Steel Welds and Its Mitigation by Electrical MethodsPark, J.-S. / Kim, J.-S. / Kim, J.-G. et al. | 2013
- 1275
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Microscale Mechanical Testing of Nuclear Materials for Advanced Reactor SystemsShin, C. / Lim, S. / Jin, H.-H. / Kwon, J. et al. | 2013
- 1282
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Development and Application of Plant Trip Risk Evaluation ModelBae, Y.-K. / Lee, E.-C. / Chi, M.-G. et al. | 2013
- 1286
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Regulatory Safety Assessment for System-integrated Modular Advanced ReactorRyu, Y.H. / Jhung, M.J. et al. | 2013
- 1295
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Study On The Performance And Maximum Acceleration On Fuel Assembly For The Advanced Fuel Handling EquipmentPark, J. / Park, B. / Choi, Y. et al. | 2013
- 1302
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Improved Procedure for Resonance Interaction Treatment in Estimation of Self Shielded Cross-sections with Subgroup MethodSohail, M. / Kim, M.-H. et al. | 2013
- 1309
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Effect on Quenching Performance of SiC/water Nanofluids in a Long Vertical TubeLee, S.W. / Kim, S.M. / Bang, I.C. et al. | 2013
- 1316
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A Study on the Thermal Evaluation of Reactor Coolant Pump Casing for Shin-Ulchin1 & 2 Nuclear Power PlantsKim, I.-J. / Choi, Y.-J. / Kim, O.-S. / Bang, S.-Y. et al. | 2013
- 1323
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Re-Examination of a Scaling Analysis of a CANDU-6 Moderator Circulation Test FacilityRhee, B.W. / Kim, H.T. / Park, S.K. / Cha, J.E. / Choi, H.L. et al. | 2013
- 1328
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Feasibility Study on HfO~2/xGnP Composites for Enhanced Thermal ConductivityLee, S.W. / Kim, I.K. / Bang, I.C. et al. | 2013
- 1333
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Design of Audit Code System to Evaluate the Metal Fuel Performance for SFRYang, Y.S. / Kim, H.C. / Shin, A. / Jeong, H. / Suh, N. et al. | 2013
- 1338
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Study of the Nanoparticle Coating Thickness On Critical Heat Flux in Pool Boiling Heat TransferPark, S.D. / Moon, S.B. / Bang, I.C. et al. | 2013
- 1346
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Conceptual Nuclear Design of an Experimental Sodium-cooled Fast ReactorNa, J.-H. / Kim, M.H. et al. | 2013
- 1356
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Review on Application of Environmental Fatigue Analysis to Class 1 PipingNam, I.K. / Lee, D.J. / Yang, K.J. / Lee, H.H. et al. | 2013
- 1362
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Plate-type Waveguide Sensor for Under-sodium Viewing in a Sodium-cooled Fast ReactorKim, H.-W. / Joo, Y.-S. / Bae, J.-H. / Park, C.-G. / Kim, J.-B. et al. | 2013
- 1368
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Containment Sump Monitoring for Unidentified Leakage Detection Using the Siphon PrincipleNoh, J.J. / Kim, J.K. / Cho, B.S. et al. | 2013
- 1375
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Conceptual Design of Reactor Protection System for Prototype SFRSeong, S.-H. / Kim, D.-H. / Son, K.-S. / Jang, G.-S. / Jeong, K.-I. / Keum, J.-Y. / Choi, J.-G. et al. | 2013
- 1383
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Forward Osmosis Sea Water Desalination Using Advanced Reactor Waste HeatPark, M.Y. / Park, G.C. / Kim, E.S. et al. | 2013
- 1394
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Assessment of SPACE Code Using Main Steam Line Break TestsKim, Y.-H. / Kim, S. / Ha, S.J. et al. | 2013
- 1402
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A Method for Inferring Local Bubble Size Distribution from the Chord Length Data Measured in a Vertical Air-Water ColumnHoang, N.H. / Yun, B.J. / Euh, D.J. / Song, C.H. et al. | 2013
- 1410
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Stability Evaluation of Foaming Agents for Decontamination FoamYoon, I.-H. / Jun, C.-H. / Yoon, S.B. / Kim, C.-K. / Moon, J.-K. / Choi, W.-K. et al. | 2013
- 1418
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CFD Analysis for an Overpressure Buildup Phenomenon of SRI Hydrogen Explosion Test at Fuel Lean and Fuel Rich Conditions in an Open SpaceKang, H.S. / Kim, S.B. / Kim, M.-H. / No, H.C. et al. | 2013
- 1428
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LBLOCA Analysis Of OPR1000 With Deployment Of Severe Accident Tolerable SIC Fuel CladdingSeo, G. / Kim, Y. / Ahn, S. / Kim, S.J. et al. | 2013
- 1436
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Design and Evaluation of Passive Decay-heat Removal System using Mercury ThermosyphonYou, B.-H. / Jeong, Y.H. et al. | 2013
- 1442
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Analysis on Duty Cycle and Capacity Design of Lead-Acid Battery Bank for the Class 1E DC Power System of Nuclear Power PlantKim, D. / Cha, H. et al. | 2013
- 1447
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Validation of Numerical Methods to Calculate Bypass Flow in a Prismatic Gas-Cooled Reactor CoreTak, N.-I. / Kim, M.-H. / Lim, H.-S. / Noh, J.M. / Drzewiecki, T.J. / Seker, V. / Downar, T.J. / Kelly, J. et al. | 2013
- 1456
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Investigation on Stress Concentration of Sharp Corner Using Finite Element Analysis and Photo-Elastic ExperimentKong, J.-P. / Ha, C.-H. / Cho, M.-K. / Park, T.-J. et al. | 2013
- 1462
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Scoping Analysis On Core Explosion And Energy Release Of Liquid Metal Fast Reactor During Core Meltdown Severe AccidentKang, S.H. / Jeong, H.-Y. et al. | 2013
- 1474
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Numerical Study for CANDU Moderator Thermal Hydraulics by using the Two-phase Flow Analysis Code, CUPIDLee, J.R. / Yoon, H.Y. / Kim, H.T. / Jeong, J.J. et al. | 2013
- 1483
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Development and Application of POSAFE-Q PLCLee, M.K. / Yun, D. et al. | 2013
- 1488
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Preliminary Studies of Ocean SMART Construction and Safety EnhancementKim, M.-G. / Kim, S.G. / Woo, I.-G. / Han, J.H. / Lee, P.-S. / Lee, J.I. et al. | 2013
- 1495
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Constitutive Models of CUPID-SG for a Performance Analysis of PWR Steam GeneratorsKim, S.H. / Kim, H. / Lee, S.-J. / Park, I.K. / Yoon, H.Y. et al. | 2013
- 1505
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Prerequisites to the Integration of EOP and SAMGLee, J. / Rawls, S. / Moon, S.-R. et al. | 2013
- 1517
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On The Gravity Driven Force Terms of Single Pressure One-Dimensional Multi-Fluid Flow Model in Horizontal Channel and Their ValidationLee, S.Y. / Park, C.E. / Ransom, V.H. et al. | 2013
- 1523
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A Decomposition Analysis of Sodium Void Reactivity in the KALIMER-600 TRU Burner CoreHa, P.N.V. / Yoo, J. / Baek, M.-H. / Tai, L.S. / Kim, S.-J. et al. | 2013
- 1531
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Boiling Heat Transfer Mechanism of Graphene Films on Sapphire Substrate with Infrared ThermometrySeo, H. / Bang, I.C. et al. | 2013
- 1537
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Multi-dimensional Thermal-hydraulic Response and Uncertainty of Calculation for LBLOCA of APR1400Bang, Y.S. / Cheong, A.-J. / Woo, S.-W. et al. | 2013
- 1546
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Experimental Study on Two-dimensional Liquid Film for Emergency Core Coolant Injection in a Reactor Vessel DowncomerYang, J.-H. / Cho, H.-K. / Euh, D.J. / Park, G.-C. et al. | 2013
- 1554
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Verification Of Omega-2 CHF Loop Reliability Via Benchmarking CHF TestPark, H. / Kim, K. / Park, E. / Clement, P. / Cubizolles, G. et al. | 2013
- 1562
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Modeling of Safety Injection Tank with Fluidic Device and Its Effect on LBLOCA CalculationBang, Y.S. / Cheong, A.-J. / Song, C.Y. / Lee, G.H. / Kim, K. / Woo, S.-W. et al. | 2013
- 1567
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Electrochemical Impedance Spectroscopy Analysis of HT9, Gr.92 and SiC in Liquid Sodium Environment for UCFR ApplicationShin, S.H. / Kim, J.J. / Choi, K.J. / Choi, S.I. / Kim, S.H. / Choi, A.Y. / Kim, J.H. et al. | 2013
- 1577
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A Scaling Study of the EU-APR1400 Core Catcher Cooling System Test Facility and Test Progress StatusRhee, B.W. / Noh, S.W. / Ha, K.S. / Park, R.J. / Song, J.H. et al. | 2013
- 1582
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Uncertainty Quantification Of Physical Models In System Thermal-Hydraulic Code MARS-KS1.3Tram, T.T. / Chung, B.D. et al. | 2013
- 1590
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Pressure/Temperature Transient Analysis of the Steam Bunker Following the Main Steam Line BreakSong, D.-S. / Lee, H. / Kim, D.-S. et al. | 2013
- 1598
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Development Of The Optimized Maintenance Support System For The Major Facilities In Nuclear Plants Based On Maintenance History For The Purpose Of Stable Operation Of The PlantLee, P. / Ahn, G. / Kim, M. et al. | 2013
- 1606
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A Sensitivity Study of DNBR to Patterns of Subchannel Control VolumeKim, B. / Kim, K. / Park, H. / Park, E. et al. | 2013
- 1614
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Preliminary Study Of Helium Brayton Cycle Turbomachinery For Small Modular High Temperature Gas Cooled Reactor ApplicationLee, J. / Lee, J.I. / Ahn, Y. / Choi, M. et al. | 2013
- 1621
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The Optimized Cable Routing Design Process for Nuclear Power Plants Using KCMS 3DLee, K. / Kim, W. / Jung, S. et al. | 2013
- 1629
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A Study for the Communication Design Methods of Plant Control System in KSNPChung, Y.M. et al. | 2013
- 1639
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Safety of Lead-bismuth Cooled Nuclear Transmutation SystemsCho, J.H. / Shin, Y.H. / Hwang, I.S. et al. | 2013
- 1642
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Feasibility Study of Fuel Cladding Performance for Ultra-long Cycle Fast Reactor (UCFR) ApplicationJung, J.A. / Kim, S.H. / Shin, S.H. / Bang, I.C. / Kim, J.H. et al. | 2013
- 1653
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Integrated Passive Safety System and Security Design for SMARTJoung, S.Y. / Kim, S.H. / Chang, S.H. et al. | 2013
- 1658
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In-Vessel Downstream Effect Tests For The APR1400Suh, J.-K. / Kim, J.-W. / Lee, J.-Y. / Park, M.-G. / Oh, S.-J. et al. | 2013
- 1666
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Design And Analysis Of Integrated Passive Safety System (IPSS) For OPR1000Kim, S.H. / Joung, S.Y. / Chang, S.H. et al. | 2013
- 1672
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Flow Boiling CHF Characteristics of Magnetic Nanofluid under the Magnetic Field ConditionLee, T. / Lee, J.H. / Jeong, Y.H. et al. | 2013
- 1678
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Theoretical Modeling Method on Worst-Case Execution Time in Real-Time I&C SystemsKeum, J.-Y. / Suh, Y.-S. / Seong, S.-H. / Kim, H.-S. et al. | 2013
- 1686
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Experimental Investigation On The CHF Enhancement Of Pool Boiling Using Water-Based Nanofluid At Higher PressureLee, J.H. / Lee, T. / Jeong, Y.H. et al. | 2013
- 1693
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Assessment of Critical Heat Flux (CHF) Performance in Water Using SiC-Coated Plate and alpha -SiC Pipe under Atmospheric PressureKam, D.H. / Lee, J.H. / Lee, T. / Jeong, Y.H. et al. | 2013
- 1701
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Experimental Study on the Cooling Capability of the PAFS (Passive Auxiliary Feedwater System) during a FLB (Feedwater Line Break) AccidentBae, B.-U. / Kim, S. / Park, Y.-S. / Kang, K.H. et al. | 2013
- 1709
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Integral Effect Test on Operational Performance of PAFS (Passive Auxiliary Feedwater System) for a SLB (Steam Line Break) AccidentKim, S. / Bae, B.-U. / Park, Y.-S. / Kang, K.-H. et al. | 2013
- 1716
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Evaluation of the POSTEC Condensation Model and Natural Circulation Cooldown Performance of the SMART PRHRS using MARS-KS CodeSim, S.K. / Kim, K.S. / Kim, S.K. / Bae, K.-H. / Bang, Y.-S. / Park, J.-Y. / Seol, K.-W. et al. | 2013
- 1723
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Design Studies of Helium Brayton Cycle for Multi-purpose Mobile ReactorAhn, Y. / Lee, J. / Kim, S.G. / Lee, J.I. / Jeong, K.H. et al. | 2013
- 1733
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Experimental CHF Study on the Effect of Heater Material and Coolant Additives for the Top of the Reactor Vessel Lower HeadPark, H.M. / Jeong, Y.H. et al. | 2013
- 1740
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Evaluation of the Effect of Condensation Heat Transfer on Performance of the Passive Auxiliary Feedwater SystemCho, Y.-J. / Kim, S. / Bae, B.-U. / Park, Y. / Kang, K.-H. et al. | 2013
- 1748
-
OECD-SERENA Phase-2: A Program Devoted To Ex-Vessel Steam Explosion Issues-PerspectivesHong, S.-W. / Piluso, P. / Leskovar, M. et al. | 2013
- 1754
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A Physics Study on Alternative Reflectors in a Compact Sodium-Cooled Breed-and-Burn Fast ReactorHartanto, D. / Kim, Y. et al. | 2013
- 1761
-
Physics Study of Nuclear Reactors for Space and Rocket PropulsionsVenneri, P. / Kim, Y. et al. | 2013
- 1769
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Design of Small-size Ultra-long Cycle Fast Reactor with PWR Spent FuelTak, T. / Lee, H. / Choi, S. / Lee, D. et al. | 2013
- 1776
-
Feasibility Study of Load Follow Operation for OPR1000Choe, J. / Lee, K.J. / Lee, D. et al. | 2013
- 1781
-
Korean Status of Environmental Fatigue Tests of Structural Materials in a Simulated Primary Coolant System WaterJang, C. / Jang, H. / Hong, J.-D. / Kim, T.S. et al. | 2013
- 1786
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Feasibility Study on Continuous Monitoring of Subcriticality by Noise Analysis MethodsKong, C. / Lee, E. / Lee, D. et al. | 2013
- 1795
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Accident Tolerance of FCM Replacement Fuel for LWRsLim, S.W. / Chun, J.H. / Chung, B.D. / Lee, W.J. et al. | 2013
- 1803
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Application of the Dispersant for Sludge Removal at the YGN Unit 6Sung, K.-B. / Kwon, H.-C. / Kim, J.-M. / Park, K.-R. / Lee, H.-C. et al. | 2013
- 1806
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Effects Of Heat Treatments On Microstructures And Mechanical Properties Of Dual Phase ODS Steels For High Temperature StrengthNoh, S. / Choi, B.-K. / Han, C.-H. / Kang, S. / Jang, J. / Jeong, Y.-H. / Kim, T.K. et al. | 2013
- 1812
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Improvement of Safety Parameters by Using Erbium-Loaded CANFLEX Fuel Bundle in the CANDU ReactorKim, W. / Kim, Y. et al. | 2013
- 1821
-
Cross Flow Modeling in Direct Whole Core Transport Calculation with a Subchannel SolverShin, C.B. / Jung, Y.S. / Joo, H.G. / Seo, K.W. et al. | 2013
- 1829
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A Neutronic Feasibility Study of an OPR-1000 Core Design Fully Loaded with FCM FuelLee, K.-H. / Park, S.-Y. / Lee, C.-C. / Cho, J.-Y. / Jo, C.-K. / Lee, W.-J. et al. | 2013
- 1837
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Fully Ceramic Micro-encapsulated (FCM) Replacement Fuel Assembly for LWRsLee, W.J. / Snead, L.L. / Venneri, F.G.V. et al. | 2013
- 1843
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The Design Study of Supercritical Carbon Dioxide Integral Experiment Loop with Consideration of Future Application to SFRAhn, Y. / Lee, J. / Kim, S.G. / Lee, J.I. / Cha, J.E. et al. | 2013
- 1851
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Uncertainty Propagation Analysis for Yonggwang Nuclear Unit 4 by McCARD/MASTER Core Analysis SystemPark, H.J. / Lee, D.H. / Shim, H.J. / Cho, J.Y. / Song, J.S. et al. | 2013
- 1859
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A Fuel Performance Analysis for an FCM Fuel under LWR ConditionsKim, Y.M. / Jo, C.K. / Lee, W.J. / Venneri, F. et al. | 2013
- 1869
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An Evaluation on the Critically Bias Caused by Manufacturing Uncertainties fo MHTGR-350 ReactorSeo, J.S. / Kim, S.H. / Noh, J.M. / Kim, J.K. et al. | 2013
- 1874
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A Preliminary Study on Neutronic Effect of Local Burn-up Distribution in MHTGR-350 Single AssemblyLee, S.H. / Kim, S.H. / Won, B.-H. / Noh, J.M. / Kim, J.K. et al. | 2013
- 1879
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Measurements of Small Bubbles using Miniature Optical Fiber Probes in Turbulent Bubbly FlowsNguyen, V.T. / Chu, I.-C. / Euh, D.J. / Song, C.-H. et al. | 2013
- 1886
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Transport and Storage of Used Nuclear Fuel under Uncertain and Changing ConditionsAndrieu, D. et al. | 2013
- 1896
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Existing Nuclear Fleet : Plant Safety after Fukushima The AREVA Safety Alliance ApproachLetourneaux, J.-M. et al. | 2013
- 1899
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SPACE-CAP Coupling Methodology for LBLOCA Analysis and Preliminary ResultsChoo, Y.J. / Hong, S.J. / Lee, B.C. / Ha, S.J. / Choi, H. / Lee, T.B. et al. | 2013