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WRFPM 2017

Today: 2017.10.24
END

List of Posters

Program  >  List of Posters
Track 1 Fuel Performance and Operational Experience
Board No. Abstract No. Presentation
01 A-013

Neutronic Evaluation of Thorium-Uranium Fuel in Heavy Water Research Reactor

Hadi SHAMORADIFAR (Payam-e Noor University, Iran, Islamic Republic of)
Behzad TEIMURI, Parviz PARVARESH, Saeed MOHAMMADI
02 A-080

Pre-transition Oxide Characterization of Zirconium Alloy Cladding on the Zinc Injection and the High Dissolved Hydrogen Condition

Sun Gyu KIM (Pusan National University, Korea, Republic of)
Taeho KIM, Ji Hyun KIM, Chi Bum BAHN
03 A-161

Disassembly and Visual Inspection of CANDU Modified 37-Element Bundle

Sangkyun WOO (KEPCO Nuclear Fuel Company, Korea, Republic of)
Myoungjun KIM, Hansang KIM
04 A-196

Quantifying the Stress Field of Hydrides Precipitation by Microxrd Tomography

Mélanie CHOLLET (Paul Scherrer Institute, Switzerland)
Weijia GONG, Dario SANCHEZ-FERREIRA, Vallerie Ann SAMSON, Johannes BERTSCH
05 A-239

An Investigation on Irradiation Growth Behaviours in Korean PWR Nuclear Fuels

Young Ki JANG (KEPCO Nuclear Fuel Company, Korea, Republic of)
Yong Hwan KIM, Jung-Tack KWON
06 A-246

Evaluation of CRUD Induced Local Corrosion Using FALCON Code

Jinho JEONG (Korea Hydro & Nuclear Power Co., Ltd., Korea, Republic of)
Yongdeog KIM
Track 2 Advances and Innovation in Fuel Technologies
Board No. Abstract No. Presentation
07 A-075

Preliminary Evaluation of FeCrAl Performance as Fuel Rod Cladding

Shixin GAO (Science and Technology on Reactor System Design Technology Laboratory, China)
Wenjie LI, Ping CHEN, Hui WANG, Yi ZHOU
08 A-111

Aligning Mo Metal Strips in UO2 Fuel Pellets for Enhancing Radial Thermal Conductivity

Dong Seok KIM (Korea Atomic Energy Research Institute, Korea, Republic of)
Keon Sik KIM, Jong Hun KIM, Dong-Joo KIM, Jangsoo OH, Jae Ho YANG, Yang-Hyun KOO
09 A-131

Neutronic Analysis of the Candidate Multi-Layer Cladding Materials with Enhanced Accident Tolerance for VVER Reactors

Martin SEVECEK (Massachusetts Institute of Technology, United States)
Ondrej NOVAK, Jakub KREJCI
10 A-132

Development of Chromium and Chromium Nitride Coated Cladding for VVER Reactors

Martin SEVECEK (Massachusetts Institute of Technology, United States)
Jakub KREJCI, Ladislav CVRCEK
11 A-139

Preliminary Evaluation of Anodic Oxidation and Electrophoretic Deposition for Heat Transfer Enhancement in Accident Tolerant Fuel Cladding

Minrak KIM (Pohang University of Science and Technology, Korea, Republic of)
Jun Young KANG, Jin Man KIM, Hyunwoo NOH, Gi Cheol LEE, Ho Jae KWAK, Tong Kyun KIM, Hwasung YEOM, Hangjin JO, Michael CORRADINI, Kumar SRIDHARAN, Hyun Sun PARK
12 A-147

Tribological Evaluation of Surface Modified Zr-Based Fuel Cladding with Corrosion Resistant Coating

Youngho LEE (Korea Atomic Energy Research Institute, Korea, Republic of)
Dong-Jun PARK, Hyun-Gil KIM, Jae Ho YANG
13 A-150

Fabrication of Yttria Stabilized Zirconia Pellets Containing Lumped Gd2O3 for Advanced Burnable Absorber Fuel

Qusai MISTARIHI (Korea Advance Institute of Science and Technology, Korea, Republic of)
Wooseong PARK, Kyungseok NAM, Mohd-Syukri YAHA, Yonghee KIM , Ho Jin RYU
14 A-159

Quench Behavior of SiC/SiC Cladding after a High Temperature Ramp under Steam Conditions

Christophe LORRETTE (CEA, France)
Thomas GUILBERT, Fredrique BOURLET, Cedric SAUDER, Laurent BRIOTTET, Herve PALANCHER, Jeremy BISCHOFF, Edouard POUILLIER
15 A-173

The Effect of End Plug Shape on the Torque Strength of End Plate Weld and Dimensional Integrity of CANDU Fuel Bundle

Choon Ho PARK (KEPCO Nuclear Fuel Company, Korea, Republic of)
Young Ho HEO, Kang Moon LEE, Suk Won KANG, Yongdeog KIM
16 A-204

Analysis of the Combined Effects on the Fuel Performance of UO2-BeO as Fuel and Iron-Based Alloy as Cladding

Claudia GIOVEDI (University of São Paulo, Brazil)
Alfredo ABE, Rafael MUNIZ, Daniel GOMES, Antonio SILVA, Marcelo MARTINS
17 A-215

UO2-Based Accident-Tolerant Hybrid Fuel: A Comparative Study of High Thermal Conductivity Additives

Jungsu AHN (Ulsan National Institute of Science and Technology, Korea, Republic of)
Myongkyu LEE, Sangjoon AHN
18 A-217

Acoustic Emission and Crack Propagation in Multi-Layered SiC Composite Tubes

Daejong KIM (Korea Atomic Energy Research Institute, Korea, Republic of)
Seung Ho LEE, Hyeon-Geun LEE, Ji Yeon PARK, Weon-Ju KIM
19 A-222

Fabrication and Characterization of SiC Matrix Coating Layer With ZrC Particle

Hyeon-Geun LEE (Korea Atomic Energy Research Institute, Korea, Republic of)
Seung Ho LEE, Daejong KIM, Ji Yeon PARK, Weon-Ju KIM
20 A-226

Fuel Behavior Analysis for Accident Tolerant Fuel with SiC Cladding Using Adapted FEMAXI-7 Code

Shinichiro YAMASHITA (Japan Atomic Energy Agency, Japan)
Noriko SHIRASU, Hiroaki SAITO, Fumihisa NAGASE
21 A-229

Study on Upgrading Power of 600MWe PWR with Annular Fuel

Xiaojun HE (China Institute of Atomic Energy, China)
Songtao JI, Junhui DIAO, Baolei SHI, Yi ZHANG, Zhaodong XIA
22 A-234

Corrosion Behavior of Fully Ceramic Micro-Encapsulated Fuel during High Temperature Steam Exposure

Kwang-Young LIM (KEPCO Nuclear Fuel Company, Korea, Republic of)
Yeon-Soo NA, Seung Jae LEE, Young-Wook KIM
23 A-267

ATTICUS - Accident Tolerant Fuel Test on the Interaction of Coolant with Uranium Silicide

Konstantina LAMBRINOU (Belgian Nuclear Research Centre (SCK-CEN), Belgium)
Brian BOER, Jason HARP
Track 3 Fuel Behaviors in Transient and Accident Conditions
Board No. Abstract No. Presentation
24 A-088

Investigation of the VVER-1000 Fuel Rods Behavior under LOCA Conditions. In-Reactor Experiments MIR-LOCA/45 and MIR-LOCA/69

Andrey BURUKIN (JSC SSC RIAR, Russian Federation)
Oleg DREGANOV, Aleksandr ALEXEYEV, Aleksandr GORYACHEV
25 A-090

Simulated High Burnup Fuel Cladding and Its Ballooning and Burst Behavior under Loss-of-Coolant Accident Condition

Dong-Jun PARK (Korea Atomic Energy Research Institute, Korea, Republic of)
Yang Il JUNG, Jung-Hwan PARK, Byoung Kwon CHOI, Hyun-Gil KIM, Jae Ho YANG, Yang-Hyun KOO
26 A-096

Power Ramp Tests of Fuel Rods Provided with a Thinned Cladding and Fuel Pellets without Central Hole in the MIR Reactor

Andrey BURUKIN (JSC SSC RIAR, Russian Federation)
Anton ESHCHERKIN, Vladimir OVCHINNIKOV, Aleksandr GORYACHEV
27 A-097

Experiments at Reactor MIR to Justify Safe Operation of VVER Fuel of Improved Design

Andrey BURUKIN (JSC SSC RIAR, Russian Federation)
Vladimir LIKHANSKY, Yury KUDRIN, Sergey ILIENKO
28 A-126

Study for Models Simulating the Oxides of the Cladding When Analyzing CEA Ejection

Changyeon YOO (KEPCO Nuclear Fuel Company, Korea, Republic of)
Sungju CHO, Jaeil LEE
29 A-136

Evaluation of Multi-Metallic Layered Composite (MMLC) Accident-Tolerant Fuel Cladding

Joonho MOON (Pusan National University, Korea, Republic of)
Sun Gyu KIM, Chi Bum BAHN, Michael P. SHORT, Ji Hyun KIM
Track 4 Spent Fuel Transportation, Storage and Treatment
Board No. Abstract No. Presentation
30 A-036

Cladding Integrity Evaluation of Simulated Spent Fuel during Dry Storage Conditions

Jong-Dae HONG (Korea Atomic Energy Research Institute, Korea, Republic of)
Euijung KIM, Chang Hwan SHIN, Donghak KOOK
31 A-125

Creep Behaviour Evaluation for Spent Nuclear Fuel in Dry Storage

Yongdeog KIM (Korea Hydro & Nuclear Power Co., Ltd., Korea, Republic of)
Seonghwan CHUNG, Jinho JEONG
32 A-133

Preliminary Study on Handling Integrity Evaluation of Nuclear Spent Fuel

Nam-Gyu PARK (KEPCO Nuclear Fuel Company, Korea, Republic of)
Jae-Jun LEE, Hyeong-Koo KIM, Kyoung-Joo KIM, Ki-Tae KIM, Seongki LEE, Jongsung YOO
33 A-135

PWR Spent Nuclear Fuel Research Status for Dry Storage and Transportation in Korea

Donghak KOOK (Korea Atomic Energy Research Institute, Korea, Republic of)
Jae Ho YANG, Yang-Hyun KOO
34 A-160

B-10 Evaluation of BORAL Neutron Absorber

Kiyoung KIM (Korea Hydro & Nuclear Power Co., Ltd., Korea, Republic of)
Sunghwan CHUNG, Yunsik KIM
35 A-189

Evaluation of Neutron Flux Accounting for Shadowing Effect among Dry Storage Casks

Kwang Pyo KIM (Kyung Hee University, Korea, Republic of)
Jin Ho PARK, Woo Jin KIM, Heejun CHUNG
36 A-218

Analysis of Parameters Used to Calculate Radiation Dose to Handlers during Radioactive Material Transportation

Kwang Pyo KIM (Kyung Hee University, Korea, Republic of)
Woo Jin KIM, Jin Ho PARK, Jung Hwan JANG, Won Chul CHOI
37 A-227

Preliminary Shielding Analysis to Set Optimal Operating Conditions of Metal Cask for Spent Nuclear Fuel in Dry Storage

Taeman KIM (Korea Radioactive Waste Agency, Korea, Republic of)
Hoseong DHO, Chunhyung CHO, Jeahun KO
38 A-245

Analysis on the Effect of Thermal Performance with Heat Distribution for Spent Nuclear Fuel Storage System

Tae Hyeon KIM (Korea Hydro & Nuclear Power Co., Ltd., Korea, Republic of)
Sunghwan CHUNG, Yongdeog KIM
39 A-288

A Thermal Analysis of a Dry Storage System - TN-24P Cask

Taehun KIM (Kyung Hee University, Korea, Republic of)
Kwangheon PARK, Hyungju YUN
40 A-289

A Criticality Evaluation and Bias and Bias Uncertainty Estimation of GBC-32 Cask from the Viewpoint of Burnup Credit

Taehun KIM (Kyung Hee University, Korea, Republic of)
Kwangheon PARK, Hyungju YUN
Track 5 Fuel Modeling, Analysis and Methods
Board No. Abstract No. Presentation
41 A-014

Neutronic Calculations for Central Test Loop (CTL) in Hypothetical Heavy Water Research Reactor

Hadi SHAMORADIFAR (Payam-e Noor University, Iran, Islamic Republic of)
Behzad TEIMURI, Parviz PARVARESH, Saeed MOHAMMADI
42 A-015

Reactivity Effect of As-Built Fuel on WEC PWR Cores in Republic of Korea

Sang Rin SHON (KEPCO Nuclear Fuel Company, Korea, Republic of)
Hwan Soo KIM, Gyoo Hwan CHOI, R. P. HARRIS
43 A-060

PLUS7™ EOL Grid and Fuel Assembly Tests

Sang-Youn JEON (KEPCO Nuclear Fuel Company, Korea, Republic of)
Hak-In LEE, Heon-Jeong HA, Il-Kyu KIM, Yong-Hwan KIM, Jae-Hoon JEONG, Chang-Suk CHO, Dong-Hak KIM, Do-Hwan LEE, Jill G. SINEGAR, Roger Y. LU, Jeff L. NORRELL
44 A-061

Composite Material Properties Simulation for the Fuel Performance Evaluation of Gadolinia-Cored UO2 Fuel

Faris SWEIDAN (Korea Advance Institute of Science and Technology, Korea, Republic of)
Ho Jin RYU
45 A-091

Development of Finite Element Models for Evaluating Mechanical Integrity of Spent Nuclear Fuel during Handling and Transportation

Ocheol KWON (KEPCO Nuclear Fuel Company, Korea, Republic of)
Youngik YOO, Kyounghong KIM, Nam-Gyu PARK, Seongki LEE, Jongsung YOO
46 A-095

Influence of Trivalent- and Tetravalent-Dopants on the Surface Structural and Electrochemical Properties of Uranium Dioxide

Jeongmook LEE (Korea Atomic Energy Research Institute, Korea, Republic of)
Jandee KIM, Young-Sang YOUN, Jong-Goo KIM, Yeong-Keong HA, Jong-Yun KIM
47 A-109

The Effect of Deflection Angle of Mixing Vane on the Flow Characteristics in Rod Bundle Channel Based on CFD Methods

Zhongchun LI (Science and Technology on Reactor System Design Technology Laboratory, China)
Sijia DU, Songwei LI, Shuhua DING, Hong ZHANG, Yu ZHANG
48 A-113

Benchmarking Results for the FUELDUTYDRV Code System

Gregory VINCENT (Westinghouse Electric Company, LLC, United States)
Michel KRAMMEN
49 A-119

Principles of Modelling of Technological Processes

Mstislav SHUSTOV (PJSC , Russian Federation)
Igor LOKTEV, Aleksandr STRUKOV, Evgeniy MILCHAKOV, Evgeniy VICHODCEV
50 A-134

A Parametric Sensitivity Analysis of Nuclear Fuel Behavior under RIA in Commercial LWR Conditions

Chando JUNG (KEPCO Nuclear Fuel Company, Korea, Republic of)
Okjoo KIM, Jaemyeong CHOI, Kyuseok LEE, Sangwon PARK
51 A-137

A Conservative Method to Estimate Normal CANDU Fuel Performance

Eun Ki LEE (Korea Hydro & Nuclear Power Co., Ltd., Korea, Republic of)
52 A-151

Prediction of 17x17 Grid Crush Behavior with a 2D Finite Element Model

Jooyoung RYU (KEPCO Nuclear Fuel Company, Korea, Republic of)
Nam-Gyu PARK, Youngik YOO, Jongsung YOO
53 A-174

Integrity Evaluation of ZrN Coating on U-Mo Fuel Surface in the Dispersion Fuel

Gwan Yoon JEONG (Ulsan National Institute of Science and Technology, Korea, Republic of)
Yeon Soo KIM, Tae Won CHO, Jihyun KIM, Cheol Min LEE, Youngjin JEONG, Dong Seong SOHN
54 A-192

Sensitivity Calculations for Criticality and Shielding Analyses Using Sampler

Kyoon-Ho CHA (Korea Hydro & Nuclear Power Co., Ltd., Korea, Republic of)
Min-Chul KIM, Seo-Jeong LEE, Do-Yeon KIM, Tai-Wan KIM
55 A-200

Practical Application of Detailed Thermomechanical FEM Model of Fuel Rod

Martin DOSTÁL (UJV Rez, A. A., Czech Republic)
Jan KLOUZAL, Vitezslav MATOCHA
56 A-243

Study on Manufacturing Technology of MnO-Al2O3 Doped UO2 Pellets for Remedy of PCI Failure

Seung Jae LEE (KEPCO Nuclear Fuel Company, Korea, Republic of)
Taesik JUNG, Yeon-Soo NA, Kwang-Young LIM, Jae Ho YANG, Dong-Joo KIM, Keon Sik KIM, Jangsoo OH
57 A-291

Economic and Safety Improvement of Nuclear Fuel Cycle by Using Nuclear Fuel Codes

Armando MARINO (Comisión Nacional De Energía Atómica, Argentina)
Edith LOSADA, Gustavo DEMARCO

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