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WRFPM 2017

Today: 2017.05.01
D - 132

List of Posters

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

Reduction of Plutonium Production in Heavy Water Research Reactor: A Feasibility Study through Neutronic Analysis Using Mcnpx2.6 and Cinder90 Codes

Hadi SHAMORADIFAR (Payam Noor University, Iran, Islamic Republic of), Behzad TEIMURI, Parviz PARVARESH, Saied 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 of Modified Candu Type Fuel Bundle

Sangkyun WOO (KEPCO NF, 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 NF, Korea, Republic of)
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
07 A-292

Assessment of Annual Tritium Release from New Designed Fuel in Liquid Effluents of Bushehr Nuclear Power Plant (BNPP)

Majid ZAMANI (Atomic Energy Organization of Iran (AEOI), Iran, Islamic Republic of), Hassan ROSTAMI, Hedayat ABBASPOOR, Mohammad JAFARI, Kamran SEPANLOO
Track 2 Advances and Innovation in Fuel Technologies
Board No. Abstract No. Presentation
08 A-062

High Entropy Alloy Coatings on the Surface of Zircaloy-4 for Accident Tolerance Fuel Cladding

JaeJoon KIM (KAIST, Korea, Republic of), Ho Jin RYU
09 A-075

Preliminary Analysis of Fecral Cladding for Accident Tolerant Fuel

Shixin GAO (Science and Technology on Reactor System Design Technology Laboratory, China), Wenjie LI, Ping CHEN, Yongjun JIAO
10 A-079

The Effects of the Substrate Bias Voltage on the Structure and Corrosion Behavior of Protective Cr Coating on Zirconium Using Cathodic Arc Ion Plating

Jung-Hwan PARK (Korea Atomic Energy Research Institute, Korea, Republic of), Yang-Il JUNG, Dong-Jun PARK, Hyun-Gil KIM, Eui-Jung KIM, Jae-Ho YANG
11 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, Jang Soo OH, Jae Ho YANG, Yang-hyun KOO
12 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
13 A-132

Development of Chromium and Chromium Nitride Coated Cladding for Vver Reactors

Martin SEVECEK (Massachusetts Institute Of Technology, United States), Jakub KREJCI
14 A-139

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

Minrak KIM (POSTECH, 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
15 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
16 A-150

Fabrication of Yttria Stabilized Zirconia Pellets Containing Lumped Gd2o3 for Advanced Burnable Absorber Fuel

Qusai MISTARIHI (KAIST, Korea, Republic of), Wooseong PARK, Kyungseok NAM, Mohd-syukri YAHA, Yonghee KIM , Hojin RYU
17 A-159

Quench Behavior of Sic/sic Cladding after High Temperature Ramp under Steam Conditions

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

Study on the Effect of the End Plug Shape on the Integrity of Candu Fuel Bundle

Choon Ho PARK (KEPCO NF, Korea, Republic of), Young Ho HEO, Kang Moon LEE, Suk Won KANG, Yong Duk KIM
19 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
20 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
21 A-217

Damage Characterization of Multi-layered Sic-based Composites by Acoustic Emission

Daejong KIM (Korea Atomic Energy Research Institute, Korea, Republic of), Sungho LEE, Hyun-geun LEE, Ji Yeon PARK, Weon-ju KIM
22 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
23 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
24 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
25 A-234

Corrosion Behavior of Fully Ceramic Micro-encapsulated Fuel during Hydrothermal Exposure

Kwang-Young LIM (KEPCO NF, Korea, Republic of), Yeon-soo NA, Seung-jae LEE, Young-wook KIM
26 A-267

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

Brian BOER (Belgian Nuclear Research Centre (SCK-CEN), Belgium), Jason HARP
Track 3 Fuel Behaviors in Transient and Accident Conditions
Board No. Abstract No. Presentation
27 A-055

Analysis of M5 Cladding Crack under Loca

Kai HE (China Nuclear Power Engineering Co., Ltd., China), Xiaochuan JIANG, Zifan SONG, Siyang ZHU, Teng SHEN, Nirong YANG
28 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
29 A-126

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

Changyeon YOO (KEPCO NF, Korea, Republic of), Sungju CHO, Jaeil LEE
30 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
31 A-172

Burst Behaviors of Hana-6 Cladding in Loca Conditions and Its Model Development

Hun JANG (KEPCO NF, Korea, Republic of), Sung Yong LEE, Dae Il KIM, Jea Young LIM, Yoon Ho KIM, Yong Kyoon MOK, Jong Sung YOO
32 A-251

Evaluation of Tellurium As a Source Term in Severe Nuclear Accident Situations

Fredrik ESPEGREN (Chemistry and Chemical Engineering, Sweden), Christian EKBERG
Track 4 Spent Fuel Transportation, Storage and Treatment
Board No. Abstract No. Presentation
33 A-028

Safety Analysis for Prototype Mnsr Heu Core Unloading and Storage

Dan PENG (China Institute of Atomic Energy, China), Yiguo LI, Jin LU, Jingyan HONG, Xiaobo WU
34 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, Dong-hak KOOK
35 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
36 A-133

Preliminary Study on Handling Integrity Evaluation of Nuclear Spent Fuel

Jae-Jun LEE (KEPCO NF, Korea, Republic of), Hyeong-Koo KIM, Kyoung-Joo KIM, Ki-Tae KIM, Seong-Ki LEE, Nam-Gyu PARK, Jong-Sung YOO
37 A-135

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

Donghak KOOK (Korea Atomic Energy Research Institute, Korea, Republic of), Jaeho YANG, Yanghyun KOO
38 A-160

B-10 Evaluation of Boral Neutron Absorber

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

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

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

Analysis of Parameters Used for Radiation Dose Calculation for Handlers during Radioactive Material Transportation

Woo Jin KIM (Kyung Hee University, Korea, Republic of), Jin Ho PARK, Jung Hwan JANG, Won Chul CHOI, Kwang Pyo KIM
41 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
42 A-245

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

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

A Thermal Analysis of a Dry Storage System - Tn-24p Cask

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

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

Hyungju YUN (Kyung Hee University, Korea, Republic of), Kwangheon PARK
Track 5 Fuel Modeling, Analysis and Methods
Board No. Abstract No. Presentation
45 A-015

Reactivity Effect of As-built Fuel on W Pwr Cores in Republic of Korea

Sang Rin SHON (KEPCO NF, Korea, Republic of), Hwan Soo KIM, Gyoo Hwan CHOI, R. P. HARRIS
46 A-014

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

Hadi SHAMORADIFAR (Payam Noor University, Iran, Islamic Republic of), Behzad TEIMURI, Parviz PARVARESH, Saied MOHAMMADI
47 A-017

An Application of Modified 3d Heat Source Model on Simulation of 15

Jiaye PAN (CNNC Jianzhong Nuclear Fuel Co.,Ltd, China)
48 A-022

Asemi-analyticalnodalmethodforsp3equation

Qingquan PAN (Tsinghua University, China), Dongsheng LI, Kan WANG
49 A-060

Plus7(tm) Eol Grid and Fuel Assembly Test

Sang-Youn JEON (KEPCO NF, Korea, Republic of), Hak-in LEE, Heon-jeong HA, Il-kyu KIM, Yong-hwan KIM, Jae-hoon JEONG, Chang-suk CHO
50 A-061

Composite Material Properties Simulation for the Fuel Performance Evaluation of Gadolinia-cored Uo2 Fuel

Faris SWEIDAN (KAIST, Korea, Republic of), Ho Jin RYU
51 A-091

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

Ocheol KWON (KEPCO NF, Korea, Republic of), Youngik YOO, Kyounghong KIM, Namgyu PARK, Seongki LEE, Jongsung YOO
52 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
53 A-106

Fuel Assembly Seismic Analysis Considering the Mutual Effects between Horizontal and Vertical Motions

Qi MIN (Nuclear Power Institute of China, China)
54 A-109

The Effect of Deflection Angle of Mixing Vane on the Flow Characteristics in Fuel 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
55 A-113

Benchmarking Results Forthe Fueldutydrv Code System

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

Principles of Modelling of Technological Processes

Igor LOKTEV (PJSC NCCP, Russian Federation), Aleksandr STRUKOV, Evgeniy MILCHAKOV, Evgeniy VICHODCEV
57 A-134

A Parametric Sensitivity Analysis of Nuclear Fuel Behavior under Ria in Commercial Lwr Conditions

Chando JUNG (KEPCO NF, Korea, Republic of), Okjoo KIM, Jaemyeong CHOI, Kyuseok LEE, Sangwon PARK
58 A-137

Conservative Method to Estimate Normal Candu Fuel Performance

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

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

Jooyoung RYU (KEPCO NF, Korea, Republic of), Namgyu PARK, Youngik YOO, Jongsung YOO
60 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, Mijin KIM , Kyuhong LEE, Dong-seong SOHN
61 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
62 A-200

Practical Application of Detailed Thermomechanical Fem Model of Fuel Rod

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

Study on Manufacturing Technology of Mno-al2o3 Doped Uo2 Pellets for Remedy of Pci Failure

Seung-Jae LEE (KEPCO NF, Korea, Republic of), Tae-Sik JUNG, Yeon-Soo NA, Kwang-Young LIM, Jae-Ho YANG, Dong-Ju KIM, Keon-Sik KIM, Jang-Soo OH
64 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, Lucas FURLANO, Rosendo FAZZARI

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