KNS 2017 Spring 춘계학술발표회

www.kns.org KNS 2017 Spring 춘계학술발표회 korean nuclear society 2017 5 17 ~ 19

www.kns.org KNS 2017 Spring 춘계학술발표회 2017 5 17 19

CONTENTS 03 04 05 06 07 08 09 10 11 12 13 14 15 16 29 2017 17 18 18 19 19 20 20 21 21 22 22 23 23 24 Workshop A 4 B C R D D E F V G H I International Workshop on Prospects for the Trump Administration s Nuclear Policy and the U S ROK Nuclear Cooperation J K L ipower HSI Workshop 4 Asian Zr Workshop 25 26 31 33 37 42 55 61 63 66 69 73 75 78 79 1 Reactor System Technology 2 Reactor Physics and Computational Science 3 Radioactive Waste Management 4 Nuclear Fuel and Materials 5 Thermal Hydraulics and Safety 6 Radiation Utilization and Protection 7 Quantum Engineering and Nuclear Fusion 8 Nuclear Power Plant Construction and Operation Technology 9 Nuclear Policy Human Resources and Cooperation 10 Nuclear I C Human Factors and Automatic Remote System Competition Session [ ]

2017 5 17 19 2016 1 20 50 2025 15 2017 5 황주호 3

2017 201A 2F 201B 2F 202A 2F 202B 2F 201A 2F 201B 2F 202A 2F 202B 2F 203 2F A 3F B 3F A 3F B 3F 3 300 3F 301 3F 302 3F 303A 3F 303B 3F 304 3F 400 4F 401A 4F 203 2F 5 17 ( ) 5 18 ( ) 5 19 ( ) (12:30 ~ 17:30) (08:00 ~ 17:30) (08:00 ~ 16:30) 09 00-10 00 10 00-11 00 11 00-12 00 12 00-13 00 13 00-14 00 14 00-15 00 15 00-16 00 16 00-17 00 17 00-18 00 18 00-19 00 09 00-10 00 10 00-11 00 11 00-12 00 12 00-13 00 13 00-14 00 14 00-15 00 15 00-16 00 16 00-17 00 17 00-18 00 18 00-19 30 09 00-10 00 10 00-11 00 11 00-12 00 12 00-13 00 13 00-14 00 14 00-15 00 15 00-16 00 16 00-17 00 [L] ipower HSI [4A] [4B] [4C] [E] [1A] [D] [9A] [5E] [9B] [5I] [9C] [C] R D [8A] [8B] [8C] [A] 4 [1B] [1C] [F] V [H] [5B] [5A] [5F] [5G] [1D] [5J] [5K] [J] [I] International Workshop on Prospects for the Trump Administration s Nuclear Policy and the U S -ROK Nuclear Cooperation [ ] [5C] [5D] [10A] [10B] [ 13 00 15 00] A 3F 401B 4F 402A 4F 402B 4F 2017 [5H] [5L] [K] [10C] [10D] 4 1 Competition Session 2 Competition Session 4 Asian Zirconium 4 Asian Zirconium [G] [3A] [7A] 4 Asian Zirconium [3B] 3 Competition Session [6A] [6B] [6C] [B] [2A] B 3F A 3F B+C 5F 77 B 3F 3 5F [2B] [2C] 17 00-18 00 300 3F 301 3F 302 3F 303A 3F 303B 3F 304 3F 400 4F 401A 4F 401B 4F 402A 4F 5 17 18 00 20 00 5 18 07 45 08 45 402B 4F B+C 5F 5F 4

2017 5 17 19 201 A B 2F 202 A B 3F 203 301 A B 302 300 303 A B 304 A B A B 2F 4F 401 A B 400 402 A B 5F A B C C B A 5

2017 29 6

2017 5 17 19 7

2017 [ ] 8

2017 5 17 19 Shinya Nagasaki Hideo Nakamura Won Sik Yang Akio Gofuku Didier Jacquemain John C Jin Jean Noirot Horst-Michael Prasser Shripad Revankar Guanghui Su Belle R Upadhyaya 9

2017 / UAE IAEA Europe 10

2017 5 17 19 / 11

2017 2017 5 18 15 30 17 50 3F [ ] 15 30 16 00 2016 2016 Competition Session 2017 16 00 16 55 16 55 17 50-2017 5 18 18 00 19 30 B C 5F 18 00 19 30 [ ] 2017 12

2017 5 17 19 2017 5 18 15 30 3F The Ohio State University 2015 03 2017 03 2011 12 2014 03 2010 01 2011 11 2008 12 2010 01 2007 03 2008 11 2005 09 2007 08 13

2017 2017 5 18 16 00 17 50 3F bankability project finance risk allocation power purchase agreement Key Player? - GMO 100 200 100 10 100 1000 100 14

2017 5 17 19 2017 2017 5 18 15 30 3F 2016 Muritala Amidu KAIST / Competition Session 2016 ACT Co Ltd 15

2017 2017 5 18 15 30 3F 2017 J Mayaka K Zabrzycki M Salam 16

www.kns.org Workshop 17

Workshop A 제 4 차산업혁명과소듐냉각고속로 2017 5 17 13 30 18 00 2 203 13 30 13 35 13 35 14 05 14 05 14 35 14 35 15 05 15 05 15 35 15 35 15 50 15 50 16 20 16 20 16 50 16 50 17 20 17 20 17 30 4 ETRI ETRI 3D Printing Technology KAIST Coffee Break AI Based Monitoring and Diagnosis of Severe Accidents Roadmap of AI Application in Nuclear Engineering Development Plans to Realize Autonomous Operation of PGSFR KAERI 30 000 042 868 2279 sjkim3@kaeri re kr 042 868 8979 ksahn@kaeri re kr B 최신노심출력분포측정및노심보호감시기술워크샵 2017 5 17 13 30 18 00 4 402B 12 30 13 30 13 30 13 40 13 40 13 50 13 50 14 30 14 30 15 00 15 00 15 20 15 20 15 50 15 50 16 20 16 20 16 40 16 40 17 10 17 10 17 40 17 40 18 00 KAIST KHNP CRI KNF KHNP CRI UNIST KEPCO E C 50 000 010 5578 3055 shin hocheol@khnp co kr 18

Workshop C 원전해체 R&D 현황 2017 5 17 13 30 18 00 2 202B 13 30 13 30 13 45 13 45 14 00 14 00 14 50 14 50 15 00 15 00 15 30 15 30 16 00 16 00 16 30 16 30 17 00 17 00 17 10 17 10 18 00 18 00 18 10 18 10 Victor K Der R D PD KETEP R D KHNP R D KAERI R D KINS R D Q A 50 000 010 2312 5495 hockey@ketep re kr Professor of Columbia University President of VKDER Assistant Secretary acting at the US Department of Energy DOE D 핵연료기술동향과미래기술수요전망 2017 5 17 12 30 18 00 2 202A 12 30 13 20 13 20 13 30 13 30 14 00 14 00 14 30 14 30 15 00 15 00 15 30 15 30 15 50 15 50 16 20 16 20 16 50 16 50 17 10 17 10 17 30 17 30 18 00 Part 1 KNF KAERI KINS KHNP CRI Part 2 KHNP CRI KAIST SFR KAERI KAERI KAERI KHNP CRI 50 000 010 2027 4507 hyochankim@kaeri re kr 010 5001 3085 jongd@kaeri re kr 19

Workshop E 국내원전인간신뢰도분석현안 2017 5 17 13 00 18 00 2 201B 13 00 13 30 13 30 13 40 13 40 14 15 14 15 14 50 14 50 15 25 15 25 15 55 15 55 16 30 16 30 17 05 17 05 17 40 17 40 17 50 18 30 20 00 KAERI 1 HRA KINS 2 Human Factors digital HRA KINS 3 K HRA ACT 4 Level 1 HRA CRI KEPCO E C 5 Level 1 HRA KAERI 6 Level 2 HRA KAERI 50 000 042 868 2186 kshpjk@kaeri re kr 042 868 2289 smshin@kaeri re kr F 동위원소도전과기회 V : 국제동위원소기술전문가발표및회의 2017 5 17 14 00 18 00 3 A 14 00 14 30 14 30 15 00 15 00 15 30 15 30 16 00 16 00 16 30 16 30 17 00 17 00 17 30 17 30 18 00 Welcoming Address Mr Oh Soo Youl KAERI A stable molybdenum 99 supply for a changing market Mr Michael Druce ANSTO Significance of kijang research reactor Mr Lee Kye Hong KAERI Coffee Break Photo The status of production and application of radioisotopes in Vietnam Mr Duong Van Dong NRI The status of supply and demand of radioisotopes in Korea Ms Park Chan Hee KARA The status of production and application of radioisotopes in Japan Mr Tsuchiya Kunihiko JAEA Development of fission based Mo 99 production process and facility Mr Lee Jun Sig KAERI 042 868 8344 limjc@kaeri re kr 20

Workshop G 국내방사선계측기및입자검출기기술워크샵 2017 5 17 13 00 18 00 4 401B 12 00 13 00 13 00 13 25 13 25 13 50 13 50 14 15 14 15 14 40 14 40 14 50 14 50 15 15 15 15 15 40 15 40 16 05 16 05 16 15 16 15 16 40 16 40 17 05 17 05 17 30 17 30 17 55 17 55 18 00 Synchrotron XFEL 2 X X Coffee break Coffee break Radiation Imaging Techniques for Radiological Environment KAIST 30 000 010 5283 0610 srhuh7@kaeri re kr H 원전형상관리추진현황및향후계획 2017 5 17 13 00 18 00 3 B 13 00 13 20 13 20 13 50 13 50 14 20 14 20 14 50 14 50 15 20 15 20 15 40 15 40 16 10 16 10 16 40 16 40 17 10 17 10 17 40 17 40 18 00 Break Time KINS DB NSE AVEVA 50 000 KINS 042 868 0852 k730kjh@kins re kr 21

Workshop I J International Workshop on Prospects for the Trump Administration s Nuclear Policy and the U.S.-ROK Nuclear Cooperation 2017 5 17 13 30 17 30 3 301 2015 13 00 13 30 13 30 14 00 14 00 15 40 15 40 16 00 16 00 17 30 [Registration] [Opening Session] Opening Remark Jooho Whang President Korea Nuclear Society Welcoming Remark Sanghyun Lee President Korea Nuclear Policy Society Keynote Speech Sangwook Ham Director General Bureau of Nuclear Energy and Nonproliferation MOFA [Session ] U S -ROK Relation and Nuclear Policies under the Trump Administration Moderator Florence Lowe Lee President Global America Business Institute The Prospect for the U S ROK Relation under the Trump Administration Korean Perspective Sanghyun Lee President Korea Nuclear Policy Society The Prospect for the U S ROK Relation under the Trump Administration U S Perspective Scott Snyder Director Program on US Korea Policy Council on Foreign Relation The Prospect for Nuclear Energy Policies under the Trump Administration Jack Spencer Vice President Heritage Foundation Break [Session ] Challenges and Opportunities of the U S -ROK Nuclear Cooperation Moderator Chungwon Cho Visiting Professor Seoul National Univ of S T Current Status and Prospects of U S ROK Nuclear Cooperation Kwang Seok Lee Director Center for ROK U S Nuclear Cooperation KAERI Challenges and Opportunities for Further Nuclear Cooperation between the US and ROK Paul Dickman Senior Policy Fellow Argonne National Laboratory Advance Reactor Development under Trump Administration and Possible Avenue for International Collaboration Donald Wolf Chairman and CEO Advanced Reactor Concepts LLC ARC 17 30 [Closing] 042 868 4893 mijin@kaeri re kr 원자력인력의질적향상방안과정책적제언 2017 5 17 13 20 17 30 3 B KINGS 13 20 13 25 13 25 13 30 13 30 13 40 13 40 13 50 13 50 14 00 14 00 15 00 15 00 15 10 15 10 15 20 15 20 15 30 15 30 16 30 16 30 16 40 16 40 17 20 17 20 17 30 KINGS KAIST BSC KINGS KINGS 010 3630 3460 ms roh@kings ac kr 22

Workshop K 지역주민의원자력인식과수용성증진워크숍 2017 5 19 09 20 12 00 3 302 09 00 09 20 09 20 09 30 09 30 10 00 10 00 10 30 10 30 10 50 10 50 11 20 11 20 12 00 1 2 Coffee Break 3 02 2191 1453 hjkim@knea or kr L ipower 인간기계연계 (HSI) 설계개발 Workshop 2017 5 17 13 00 18 00 2 201A 13 00 13 10 KHNP CRI 13 10 13 30 ipower HSI Top Tier Requirement KHNP CRI 13 30 13 50 13 50 14 10 14 10 14 30 14 30 14 50 14 50 15 10 15 10 15 30 15 50 16 10 16 10 16 30 16 30 16 50 16 50 18 00 Roadmap of Big data and AI Application in ipower Intelligent systems to reduce control risk failures UNIST KAERI SD AE 042 870 5419 ygkim stpn@khnp co kr 23

Workshop 제 4 회아시안지르코늄워크샵 (Asian Zr Workshop) 2017 5 17 5 19 4 400 5 17 ( ) 14 00 14 20 14 20 14 40 14 40 15 00 15 00 15 20 15 40 16 00 16 00 16 20 16 20 16 40 16 40 17 00 17 00 17 20 Effect of Mo and Bi additions on the microstructure of Zr Cr Fe alloy after quenching LUAN Baifeng Chongqing Univ The anisotropic surface segregation of Sn in zirconium alloys XIE Shijing Shanghai Univ Microstructure and properties of new zirconium alloys for CAP1400 fuel assembly ZENG Qifeng SNERDI Development of CZ zirconium alloys in China TAN Jun CGNPC A study on classification method of heterogeneous Zr alloys KIM Donghui Kepco NF A study on mechanical characteristics of pilger mandrel material under different heat treatment conditions PARK Min Young Kepco NF The evolution of SPPs in N36 alloy during the tube manufacturing DAI Xun NPIC The analysis and solution of Ti contamination on Zr 4 strip LI Gang SNZ Anisotropic tensile behaviors of recrystallized Zr 1 8Nb alloy sheet YANG Huilong Univ of Tokyo 5 18 ( ) 09 20 09 40 09 40 10 00 10 00 10 20 10 20 10 40 11 00 11 20 11 20 11 40 11 40 12 00 14 00 14 20 14 20 14 40 14 40 15 00 15 00 15 20 15 40 16 00 16 00 16 20 16 20 16 40 16 40 17 00 17 00 17 20 Corrosion behavior of Zr 1Nb xge ybi alloys YAO Meiyi Shanghai Univ The corrosion resistance of Zr alloy containing Sn and Fe element PENG Jianchao Shanghai Univ Study on corrosion behaviors of HANA 6 and M2 Zr 1 55wt Nb 0 2wt Cu alloys in simulated PWR primary water JANG Hun KNF Microstructure analysis of pre transition oxide formed on Zr Nb Sn alloy under various Zn and dissolved hydrogen concentrations KIM Sungyu Pusan Univ First principles study of the oxygen adsorption on Zr surface with Nb or Ge XIE Yao Ping Shanghai Univ Corrosion behavior of Cr and Cr alloy coatings for accident tolerant fuel cladding PARK Jung Hwan KAERI Characteristics of Nd Zr hydride MUTA Hiroaki Osaka Univ Development status of surface modified Zr cladding for ATF KIM Hyun Gil KAERI Laser induced formation of a dispersed oxide layer on Zircaloy 4 JUNG Yang Il KAERI Behavior of Zr fuel claddings with oxidation resistant coating layer under loss of coolant accident condition PARK Dong Jun KAERI Physical properties of molten Zr Ni and Zr Cr alloy KONDO Toshiki Osaka Univ Hydride induced degradation of Zircaloy 4 cladding tubes in the longitudinal and circumferential directions ZHAO Z Univ of Tokyo A study on effects of hydrogen content and peak temperature on threshold stress for hydride reorientation LEE Ji Min HanyangUniv Uniaxial tensile properties of fully partially recrystallized Zr Nb alloys under a wide temperature range KANO Sho Univ of Tokyo Study on low cycle fatigue property of Zr Sn Nb alloy sheet weld joint LI Shunping NPIC High temperature fatigue characteristics of Zr alloy sheet material KIM Joongjin Kepco NF 5 19 ( ) 10 10 10 30 10 30 10 50 10 50 11 10 11 10 11 30 11 30 11 50 Air oxidation of Zry 4 at 600 1600C PARK Sanggil ACT Oxidation of Nb precipitates in Zr 2 5Nb alloy studied by ATP and HRTEM techniques LIANG Xue Shanghai Univ Effect of Cu and Ge on the corrosion resistance of zirconium alloys ZHANG Jin L Shanghai Univ Influence of internal pressure on oxidation behavior of Zircaloy 2 cladding tube IOKA Ikuo JAEA Electronic structure and hybridization effects of zirconium alloy in high temperature water KIM Taeho UNIST 30 15 042 868 8279 yijung@kaeri re kr 24

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1 (Reactor System Technology) 1A 5. 18 ( ) (Sodium-Cooled Fast Reactor) Chi Woong Choi Sang Gil Park 201B 09 00 09 40 10 00 10 20 10 40 11 00 11 20 11 40 12 00 PGSFR BOP System Design Features Young Sik Jang Hyun Kyu Lee Kag Su Jang and Kil Jung Kim KEPCO E C Validation of MARS-LMR Code Using EBR-II Unprotected Loss of Heat Sink Test Chiwoong CHOI Taekyung Jeong and Kwilim Lee KAERI Review of SFR Severe Accident Experiments Si Won Seo Sang Gil Park Chul Kyu Lim and Bong Jin Ko ACT Co Ltd Sang Ji Kim KAERI A Review of Various Stages of the Severe Accident and Different Physical Phenomena for the Sodiumcooled Fast Reactor Chul Kyu Lim Bong Jin Ko Sang Gil Park and Si Won Seo ACT Co Ltd Sang Ji Kim KAERI Coffee Break Reivew of the Regulation Status of Source Term for Sodium-cooled Fast Reactor in US Bong Jin Ko Chul Kyu Lim Sang Gil Park Si Won Seo and Sang gu Han ACT Co Ltd Sang Ji Kim KAERI Evaluation on In-vessel Source Term in PGSFR 2017 Results Seung Won Lee Sang June Ahn Chi Woong Choi Kwi Lim Lee Taekyeong Jeong and Sunghyuk Im KAERI Possible Hydrodynamic Fragmentation Behaviors of Molten Metallic Fuel in a SFR Fuel Assembly under Initiating Phase of Severe Accidents Hyo Heo Min Ho Lee and In Cheol Bang UNIST Dong Wook Jerng CAU Safety Evaluation for Steam Generator Sodium-water Reaction Event in PGSFR Sang Jun Ahn Kwi Lim Lee Chi Woong Choi Seung Won Lee Jae Ho Jeong Taekyeong Jeong and Sunghyuk Im KAERI 1B 5. 18 ( ) (High Temperature Gas Cooled Reactor) Chan Soo Kim Sung Nam Lee 203 09 00 09 40 10 00 10 20 10 40 11 00 Creep Crack Growth Behavior of Candidate Materials for Use in a VHTR System Woo Gon Kim Jae Young Park Eung Seon Kim Yong Wan Kim and Min Hwan Kim KAERI GAMMA Simulation of Phase 1 Exercise 2 of the OECD NEA MHTGR-350 Benchmark Nam il Tak and Hong Sik Lim KAERI CORONA Code Verification on One-sixth Core of VHTR Sung Nam LEE and Nam il TAK KAERI Heat Transfer Correlation for 800HT PCHE with Wavy Channel in HELP Chan Soo Kim Byung Ha Park and Eung Sun Kim KAERI Dong Hyun An and Jae Sool Shim YU Coffee Break Demonstration of Diffusion Welding Performance of Alloy 617 Injin Sah Eung Seon Kim and Min Hwan Kim KAERI Jong Bae Hwang CNU 26

11 20 11 40 12 00 Design of Dry Cooling Tower Using Solar Energy for MMR Young Jae Choi Yacine Addad and Yong Hoon Jeong KAIST Experimental Study on the Mixed Convection Phenomena in the Air-cooled RCCS Riser Dong Ho Shin Sin Yeob Kim Hyoung Kyu Cho and Goon Cherl Park SNU Chan Soo Kim KAERI A Preliminary Study for Prediction of Supercritical CO2 Compressor Surge Line Seong Kuk Cho Seong Gu Kim Seungjoon Baik and Jeong Ik Lee KAIST 1C 5. 19 ( ) 09 00 09 20 09 40 10 00 10 20 10 40 11 00 11 20 11 40 (Sodium-Cooled Fast Reactor) Hyungmo Kim Hoe Woong Kim 203 A Study on Diversity and Independent Features of Shutdown System of the PGSFR Jae Han Lee and Sung Kyun Kim KAERI Drop Performance Test of Recently Designed Control Rod Assembly for PGSFR Jin Gwan Son Hoe Woong Kim Sang Jin Park Sun Hee Choi Jong Bum Kim and Sung Kyun Kim KAERI Scaling Analysis of Various Simulants for Sodium Thermal-hydraulic Experiment in a Reduced-height Scale Test Facility Dong Eok Kim and Jae Min Choi KNU Jaehyuk Eoh KAERI Moo Hwan Kim POSTECH Design Evaluations of High Temperature Piping System in Sodium Test Facility Seok Kwon Son Hyeong Yeon Lee and Ji Young Jeong KAERI Debris Bed Analysis in Discharge of the Molten Fuel through Lower Structure of Fuel Assembly in PGSFR Min Ho Lee Hyo Heo and In Cheol Bang UNIST Dong Wook Jerng CAU Coffee Break Measurements of Enhanced Mixing with U-pattern Wire Wrap Spacer in 19-pin Rod Bundle Using Particle Image Velocimetry Yeong Shin Jeong Ji Yong Kim and In Cheol Bang UNIST Experimental Study on Natural Convection Air Flow Characteristics in a Finned-tube Type Sodium-to-Air Heat Exchanger System Jaehong Min and Weon Gyu Shin CNU Hyungmo Kim Jaehyuk Eoh and Ji Young Jeong KAERI Estimation of Ultrasonic Beam Profile Radiated from a Plate-type Ultrasonic Waveguide Sesnor in Sodium Sang Jin Park Hoe Woong Kim Young Sang Joo Sung Kyun Kim and Jong Bum Kim KAERI 1D 5. 19 ( ) / / (Light Water Reactor/Small-Medium Size Reactor/Research Reactor) KyoungWoo Seo Seung Chan Lee 203 13 30 13 50 14 10 Development and Verification of Siphon Breaker Simulation Program Kwon Yeong Lee and Wan Soo Kim HGU Design for Joint Module of NTD Hydraulic Rotation Device Joon Yong Chang Ki Jung Park Seong Hoon Kim Dae Young Chi and Cheol Park KAERI Preliminary Safety Classification of SSCs for a Pool-Type Research Reactor Suki Park KAERI 27

14 30 14 50 15 10 15 30 15 50 16 10 A Study of Residence Time Distributions Using Various Numerical Methods Minkyu Jung Kyoungwoo Seo Daeyoung Chi Seonghoon Kim and Cheol Park KAERI Beyond-design-basis Accident Analysis using Bayesian Network Application to Research Reactor Shinyoung Kwag Jinho Oh and Jong Min Lee KAERI Coffee Break A Study on Securing Core Cooling Ability in Case of Total Loss of Feedwater for 2-Loop Westinghouse NPP Seung Chan Lee KHNP CRI Young Chan Park ACT Co Ltd Sensitivity Analysis on Pressurizer Safety Valve Capacity for Overpressure Protection of Integral Reactor Minkyu Lee June Woo Kee Seungyeob Ryu Juhyeon Yoon and Young In Kim KAERI Preliminary Study of Conceptual Design of the ATOM Safety System Gwang Hyeok Seo Doyoung Shin Hong Hyun Son and Sung Joong Kim HYU 1E 5. 18 ( ) - 19 ( ) / / / (Light Water Reactor/Small-Medium Size Reactor/High Temperature Cas Cooled Reactor/Research Reactor) - POSTER Eung Seon Kim Dae Young Chi 3 5 18 13 00 18 00 5 19 09 00 17 00 5 18 13 00 15 00 P01E01 P01E02 P01E03 P01E04 P01E05 P01E06 P01E07 P01E08 P01E09 P01E10 P01E11 A Study on Critical Water Level during Mid-Loop Operation Seonggi Jeong Kunwoo Yi Byung Ryul Jung Yong Sang Ko Yoon Jae Choe Seok Jeong Yune and Seong Chan Park KEPCO E C Advisory Committee on Reactor Safeguards Review of Reactor for the APR1400 Design Certification Jeong kwan Suh and Yun ho Kim KHNP CRI PCHE Off-design Performance Model for S-CO2 Power Cycle under SMART Condition Jinsu Kwon and Jeong Ik Lee KAIST Effect of Magnetic Drive Shaft on Magnetic Forces of the IV-CEDM Jinseok Park Myounggoo Lee Yeonho Cho Hyunmin Kim and Chulsoo Maeng KEPCO E C Preliminary Study of Cycle Layout and Modeling for SMR Jae Jun Lee Won Woong Lee Jinsu Kwon and Jeong Ik Lee KAIST Conceptual Design of IV-CEDM Installation Structure Wonho Lee Jinseok Park Myounggoo Lee Yeonho Cho and Hyunmin Kim KEPCO E C Implementation and Verification of the Chemical Reaction Models in the GAMMA-FP Fission Products Analysis Tool for VHTR Applications Churl Yoon and Hong Sik Lim KAERI Numerical Simulation of H2SO4 Thermal Decomposer for a Bench-scale Nuclear Hydrogen Production Test Facility Youngjoon Shin Taehoon Lee Kiyoung Lee Changkeun Jo and Minhawn Kim KAERI Stress Analysis for Process HX of VHTR Hydrogen Production System Y W Kim and E S Kim KAERI An Investigation of Technical Issues on VHTR Off-site Dose Analysis Nam il Tak and Sung Nam Lee KAERI Analysis of Beyond Design Basis Accident of S-CO2 Cooled KAIST Micro Modular Reactor with GAMMA Code Bong Seong Oh Seong Gu Kim and Jeong Ik Lee KAIST 28

P01E12 P01E13 P01E14 P01E15 P01E16 P01E17 P01E18 P01E19 P01E20 P01E21 P01E22 P01E23 P01E24 P01E25 P01E26 P01E27 Effect of Packing Ratio on the Flow Field and Heat Transfer Characteristics of an FCC Pebble Bed Leisheng Chen and Jaeyoung Lee HGU A Conceptual Study of Using an Isothermal Compressor on a Supercritical CO2 Cycle for Various Nuclear Applications Jin Young Heo and Jeong Ik Lee KAIST Control Logic Development of KAIST Micro Modular Reactor for the Replacement of the Container Ship s Propulsion Engine Do Kyu Kim Bong Seong Oh and Jeong Ik Lee KAIST Flow Distribution Analysis of Core of Prismatic VHTR using Looped Network Analysis Method Jeong Hun Lee Dong Ho Shin Hyoung Kyu Cho and Goon Cherl Park SNU External Loss Analysis of a Supercritical CO2 Radial Compressor Seong Gu Kim Seong Kuk Cho and Jeong Ik Lee KAIST Jekyoung Lee and Si Woo Lee Jinsolturbo Machinery Co Ltd Yacine Addad KUSTAR Jae Eun Cha KAERI A Conceptual Study of an Integrated Passive Safety System for a Research Reactor Kwon Yeong Lee HGU Hyun gi Yoon KAERI Experimental Study on Rotation Characteristic by Material Difference of NTD Hydraulic Rotation Device Ki Jung Park Han Ok Kang Seong Hoon Kim Dae Young Chi and Cheol Park KAERI Flow Rate Measurement of the Primary Cooling System Pump through the Motor Performance Data during Commissioning Hyun Gi Yoon Kyoung Woo Seo and Dae Young Chi KAERI Pool Cooling Evaluation in the Open-Pool Research Reactor Jungwoon Choi Sunil Lee Ki Jung Park Dae Young Chi and Cheol Park KAERI CFD Study on Hot Water Layer Formation for KIJANG Research Reactor Yong Seok Choi Dae Young Chi Seung Hoon Kim and Cheol Park KAERI Design Guideline for Cooling Tower as Heat Sink in a Research Reactor Sunil Lee Kyoung Woo Seo Seong Hoon Kim Dae Young Chi and Cheol Park KAERI Natural Convection Cooling in a 3-dimensional Pool Model of KJRR Donghyun Kim and Suki Park KAERI Application of Siphon Breaker Simulation Program for Small Scale Siphon Breaker Sung Hoon Kim Jin Ho Kim Dae Yun Ji and Kwon Yeong Lee HGU Investigation on Core Downward Flow by a Passive Residual Heat Removal System of Research Reactor Won Koo Lee So Jung Kim Dong Yeong Lee Won Ki Hwang and Kwon Yeong Lee HGU Development of Movable Pool Hanger in Research Reactor Pool Jongmin Lee and Byungho Kwag KAERI A Plausible Method to Reduce the Noise from Nuclear Instruments of Research Reactors Sanghoon Bae Dane Bang and Hanju Cha KAERI 1F 5. 18 ( ) - 19 ( ) P01F01 (Sodium-Cooled Fast Reactor) - POSTER Chungho Cho Nak Hyun Kim 5 18 13 00 18 00 5 19 09 00 17 00 5 18 13 00 15 00 3 Scoping Analysis on Core Disruptive Accident in PGSFR 2017 Results Seung Won Lee Sang June Ahn Chi Woong Choi Kwi Lim Lee Taekyeong Jeong and Sunghyuk Im KAERI 29

P01F02 P01F03 P01F04 P01F05 P01F06 P01F07 P01F08 P01F09 P01F10 P01F11 P01F12 P01F13 P01F14 P01F15 P01F16 P01F17 P01F18 P01F19 P01F20 Review of Radionuclide behavior in the Soduim Pool for MST Analysis Bong Jin Ko Chul Kyu Lim Sang Gil Park and Si Won Seo ACT Co Ltd Sang Ji Kim KAERI Developmental Status of TRACE-SFR Code for the DBA Assessment of SFR Andong SHIN and Yong Won Choi KINS EBR II Unprotected Loss of Heat Sink Prediction and Preliminary Test using MARS-LMR Code Seok Ju Kang Doo Hyuk Kang and Jae Seung Suh SenTech Hae Young Jeong and Chi Woong Choi Sejong Univ Sung Won Bae and Chi Woong Choi KAERI Structural Integrity Evaluation of Reactor Enclosure System for PGSFR Seong Hyeon Lee and Sung Kyun Kim KAERI Structural Integrity Evaluation for the Dual Rotating Plug in PGSFR Seok Hoon Kim and Seong Gyun Kim KAERI Structural Evaluation of FHX for PGSFR at Transient Condition Nak Hyun Kim and Sung Kyun Kim KAERI Integrity Evaluation of the UIS Bottom Plate in PGSFR Regarding the Thermal Striping Jae Hun Cho Chang Gyu Park Sung Kyun Kim and Jong Bum Kim KAERI Refueling System Design for Protoype Gen-IV Sodium-cooled Fast Reactor Dong Won Lim Seok Hoon Kim and Sung Kyun Kim KAERI Preliminary Design Evaluation of IHTS-Combined Steam Generator Concepts for a Sodium-cooled Fast Reactor Hyungmo Kim Jung Yoon and Jaehyuk Eoh KAERI Namhyeong Kim and Moo Hwan Kim POSTECH Dong Eok Kim KNU Design of Small Annular Linear Induction Electromagnetic Pumps for STELLA-2 Eui Kwang Kim Jung Yoon Jong Bum Kim and Jiyoung Jeong KAERI Performance Test of Electromagnetic Flow Meter in Sodium Thermal Hydraulic Experiment Loop for Finned-tube Sodium-to-Air Heat Exchanger SELFA Byeong Yeon Kim Hyungmo Kim Youngil Cho Jong Man Kim Yung Joo Ko Min Hwan Jung and Ji Young Jeong KAERI Evaluation of the Insulation Performance of Auxiliary System for STELLA-2 Chungho Cho Jong Man Kim Yung Joo Ko Byeongyeon Kim Youngil Cho Yong Bum Lee Ji Young Jeong and Jong Bum Kim KAERI Design and Performance Analysis of the Vessel Air Cooling System of STELLA-2 Youngchul Jo Sang Min Park Jaehyuk Eoh and Ji Young Jung KAERI Experimental Verification of Ranging Inspection Technique for Sodium-cooled Fast Reactor using Horizontal Beam Waveguide Sensor Young Sang Joo Hoe Woong Kim Sang Jin Park Sung Kyun Kim and Jong Bum Kim KAERI Development and Performance Test of Electro-magnetic Acoustic Transducer for Reactor Vessel Inspection in PGSFR Hoe Woong Kim Snag Jin Park Jin Gwan Son Young Sang Joo Sung Kyun Kim and Jong Bum Kim KAERI Study of S-CO2 Power Cycle Off-design Performances for SFR Applications Seungjoon Baik Seong Kuk Cho and Jeong Ik Lee KAIST Development of Computational Code for Heat Balance Analysis in N2 Brayton Cycle Power Conversion System Coupled with an SFR Jung Yoon Jaehyuk Eoh and Hyungmo Kim KAERI Dong Eok Kim KNU Moohwan Kim POSTECH Preliminary Analysis of Airfoil PCHE for the N2-PCS Recuperator Design Jin Gyu Kwon Joo Hyun Park Tae Ho Kim Hyun Sun Park and Moo Hwan Kim POSTECH Jaehyuk Eoh KAERI Dong Eok Kim KNU Drop Behavior Analysis of Control Rod Assembly for PGSFR Using HEXCON Code Kyungho Yoon KAERI 30

2 (Reactor Physics and Computational Science) 2A 5. 18 ( ) 09 00 09 25 09 50 10 15 10 35 11 00 11 25 (Reactor Physics General) Donghwan Park Sunghwan Yun 402B Investigation of Spatial Self-shielding Effects on Control Rod Worth for PGSFR Min Jae Lee Jong Hyuck Won and Jae Yong Lim KAERI Testing of Improved Thermal Scattering Library for Heavy Water in ENDF B-. 4 Haelee Hyun Do Heon Kim and Young Ouk Lee KAERI Three-dimensional Multi-Physics Analysis of an Unprotected LOCA in the CANDU6 System Jaeha Kim Min Gil Kim and Yonghee Kim KAIST Sun Oh Yu KINS Coffee Break Shielding Benchmark Calculation on a Multilayer One-dimensional Cylindrical Geometry with AETIUS ANISN and MCNPX Jong Woon KIM Jae Hoon SONG and Young Ouk LEE KAERI Derivation and Numerical Solution of Multi-group Neutron Diffusion Equation Using Radial Point Interpolation Method Hae Sun Jeong and Kyung O Kim KAERI Core Follow Calculation for a Hanbit Unit 1 in Cycles 1 through 7 using DeCART2D MASTER Yonghee Choi Hee Jeong Jeong Cheonbo Shim and Kyunghoon Lee KAERI 2B 5. 19 ( ) 09 00 09 25 09 50 10 15 10 35 11 00 11 25 11 50 (Reactor Analysis Method) Ho Jin Park Hyun Chul Lee 402B Diffusion Synthetic Acceleration DSA for the Linear Discontinuous Expansion Method with Subcell Balance LDEM-SCB Habib Muhammad and Ser Gi Hong KHU Three-dimensional Pin-by-Pin Reactor Core Analysis by the HCMFD Algorithm Jaeha Kim and Yonghee Kim KAIST Refinements of On-The-Fly Doppler Broadening via Gauss-Hermite Quadrature in Monte Carlo Reactor Analysis YuGwon Jo and Nam Zin Cho KAIST Coffee Break Feasibility of the APEC Method in Physics Analysis of a Burned PWR Core Kyunghoon Lee Woosong Kim and Yonghee Kim KAIST Real Variance Reduction in Continuous-Energy Monte Carlo Whole-Core Calculation Via p-cmfd Feedback YuGwon Jo and Nam Zin Cho KAIST A CMFD Acceleration with SP3 Approximation for the Monte Carlo Neutron Transport Inhyung Kim and Yonghee Kim KAIST Establishment and Preliminary Verification of the ntracer-renus Core Analysis System Jun Ho Jeong Young Suk Ban and Han Gyu Joo SNU 31

2C 5. 19 ( ) 13 30 13 55 14 20 14 45 15 05 15 30 15 55 (Advanced Reactor Research) Yonghee Kim Jong Woon Kim 402B Multi-cycle Analysis on Spent Fuel Re-utilization in PWR Reload Core Design Yun Seo PARK and Myung Hyun KIM KHU Soluble-Boron- Free SMR Design with Centrally Shielded Burnable Absorbers Ahmed Amin E Abdelhameed Chihyung Kim and Yonghee Kim KAIST Feasibility of Long-Cycle Core Design for PGSFR Young Ho PARK and Myung Hyun KIM KHU Coffee Break Design of Water-Cooled Small Modular Reactor Core with UO2 Caramel Fuel Shi Do Lee and Hyung Jin Shim SNU Hyeong Heon Kim KEPCO E C Shutdown Margin Analysis on the ipower Equilibrium Core according to the Contorl Rod Pattern Jongwoo Lee Jeongpyo Jeon Junggyw Lee Kibong Seong and Chaejoon Lim KEPCO NF Analysis of Fission Reaction Rate Distributions for the BFS-84-1 Experiments Sunghwan Yun and Jae Yong Lim KAERI 2D 5. 18 ( ) - 19 ( ) P02D01 P02D02 P02D03 P02D04 P02D05 P02D06 (Reactor Physics and Computational Science) - POSTER Jin Young Cho Chang Keun Jo 5 18 13 00 18 00 5 19 09 00 17 00 5 18 13 00 15 00 Core Follow Calculation for Hanbit unit 3 Using DeCART2D MASTER Sungmin Kim Cheonbo Shim Yonghee Choi and Kyunghoon Lee KAERI Evaluation of DNBR-POL Algorithm in SMART Core Monitoring System DongYeong Kim Hyuk Kwon and BonSeung Koo KAERI Core Follow Calculation of DeCART2D MASTER4 0 System for Palo Verde Unit 1 in Cycles 1 through 4 Hee Jeong Jeong Yonghee Choi Sungmin Kim and Kyunghoon Lee KAERI Examination of Economics of Small Modular Reactor Based on Overnight Capital Cost Phil Seo Kim and Man Sung Yim KAIST A Reactivity Evaluation of Hypothetical Misloadings for WEC 3-Loop Type Plant Seong ho Park Seung beom Son Ki bong Seong and Chae joon Lim KNFC 3 A New Genetic Representation Based on Initial Multiplicity of Assembly for In-Core Fuel Management Optimization Problem Myeong Hyeon WOO Jae Hyun KIM Jong Woo KIM Chan Ho SHIN and Jong Kyung KIM HYU 32

3 (Radioactive Waste Management) 3A 5. 18 ( ) I (Radioactive Waste Management I) Ho Jin Ryu Min Hoon Baik 401A 09 00 09 30 09 50 10 10 10 30 10 50 11 10 11 30 11 50 A Safety Case of the Conceptual Disposal System for Pyro-processing High-level Waste Based on the KURT Site AKRS-16 Min Hoon Baik Nak Youl Ko Jongtae Jeong Kyung Su Kim KAERI Characteristics of U IV Nanoparticles and Their Interactions with Natural and Synthetic Macromolecules in Aqueous Solutions Wansik Cha Sun Tae Kim Deok Beom Seo Hye Ryun Cho and Euo Chang Jung KAERI Sintering of Hydroxyapatite at Extra Ordinary Low Temperature of 200 - A Way Forward to the Effective Immobilization of Radioiodine Muhmood ul Hassan and Hojin Ryu KAIST Experimental Study of Methyl Iodide Absorption by Zeolite Dry Filtration Gi Ppeum Kim and Jae Young Lee HGU Fire Test Using a 1 3 Slice Model of the KORAD-B II Shipping Package K S Bang S H Yu J C Lee and W S Choi KAERI D G Lee KONES Coffee Break Conceptual Design Hybrid Cutting System for Type B Radwaste Kwang Soo Park DOOSAN Hyeon Gon Lee KODA Colin Smith and Charles Spencer Pitcher ITER A Study on Shielding Performance Evaluation to Discern Suitability of New Shielding Material in Korean Dual Purpose Cask Jae Hyun Kim Myung Hyun Woo Jong Woo Kim Do Hyun Kim Chang Ho Shin and Jong Kyung Kim HYU A Comparative Study on Age Determination of Uranium Oxides by Different Chemical Separation Methodologies Based on TEVA and UTEVA Sang Ho Lim Eun Ju Choi Sun Ho Han Ranhee Park Jinkyu Park and Chi Gyu Lee KAERI 3B 5. 19 ( ) 09 00 09 20 09 40 10 00 II (Radioactive Waste Management II) Wansik Cha Chang Je Park 401A Development of Integrated Operation Model for Pyroprocessing IOMP Hyo Jik Lee Hun Suk Im Hong Jang and Jeong Hoe Ku KAERI David Krahl and Jian Luo Kromite Examination of Uncertainty in Modeling Mass Transfer and Electrodeposition from Electrorefining Simulation Young Eun Jung and Man Sung Yim KAIST Effect of Cu Ion on the Corrosion of PWR Materials in HyBRID Decontamination Solution Jun Young Jung Sang Yoon Park Hui Jun Won Wang Kyu Choi Seon Byeong Kim and Jei Kwon Moon KAERI So Jin Park CNU Advanced Treament Process of Secondary Waste Solution of HyBRID Decontamination Agent Man Soo Choi Hui Jun Won Sang Yoon Park Wang Kyu Choi Joon Young Jung Jung Soon Park and Seon Byoung Kim KAERI 33

10 20 10 40 11 00 11 20 Preliminary Application of Laser Ablation Inductively Coupled Plasma Mass Spectrometry for Characterization of U-Mo Dispersion Fuel Jeongmook Lee Jai Il Park Young Sang Youn Yeong Keong Ha and Jong Yun Kim KAERI Coffee Break A Scenario Study on PWR Spent Characteristics Using Updated AMORES Program Gyeong Mi Kim Geon Hee Jung and Ser Gi Hong KHU Dae Sik Yook KINS Physical and Chemical Properties of Simulated Spent Fuel Urania Doped with Gd III and or Th IV Jandee Kim Jeongmook Lee Young Sang Youn Jong Goo Kim Yeong Keong Ha Sang Eun Bae Sang ho Lim and Jong Yun Kim KAERI Nazhen Liu and David W Shoesmith UWO 3C 5. 18 ( ) - 19 ( ) P03C01 P03C02 P03C03 P03C04 P03C05 P03C06 P03C07 P03C08 P03C09 P03C10 P03C11 P03C12 P03C13 P03C14 (Radioactive Waste Management) - POSTER Jongtae Jeong Sang Ho Lim 5 18 13 00 18 00 5 19 09 00 17 00 5 18 13 00 15 00 Slitting Test of Zry-4 and SUS316 Tube Using 2-CUT Module Young Hwan Kim Yung Zun Cho and Young Soon Lee KAERI Electron Probe Microanalysis of an Unirradiated Simulated Fuel Heated at 750 for SFR Y S Choo Y J Kim B O Yoo S J Baik Y G Jin K S Heo H M Kim and S B Ahn KAERI Electrochemical Behavior on Sm and Bi Ion in LiCl-KCl Eutectic Salt Using W Electrode Beom Kyu Kim Byung Gi Park Hwa Jeong Han Won Ki Kim and Ji Hye Park SCH A New Method for Mass Separation of Radioactive Waste Using Magnetic Nozzle Kyoung Jae Chung June Young Kim K S Chung Seongcheol Kim and Y S Hwang SNU Study on the Improvement of Regulatory Framework of LILW Transportation Sung Il Kim Yoon Ji Lee and Sangmyeon Ahn KINS 3 Consideration on Potential Measures Against Human Intrusion for a Near Surface Disposal Facilities Dong Keun Cho Jung Woo Kim Jongtae Jeong and Min Hoon Baik KAERI Hyosub Kim HYU Model Development for the Post-Closure Safety Assessment of LILW Complex Disposal Facilities Jung Woo Kim and Dong Keun Cho KAERI Hyosub Kim HYU Case Study - US NRC Concentration Averaging and Encapsulation Branch Technical Position Revision1 Dong Ju Lee Jongjin Kim Dae Seok Hong Won Hyuk Jang Il Sik Kang and Ki Baek Shin KAERI A Study on the Effects of Key Parameters Using A Post-closure Safety Assessment Model for the LILW Disposal Facilities Hyosub Kim and Moosung Jae HYU Jung Woo Kim Dong Keun Cho Jongtae Jeong KAERI Development of Resin Separation Equipment for Spent Resin Mixture in Heavy Water Reactors HWR Kyu Tae Park Jung Min Yoo and Young Ku Choi Sunkwang T S Co Ltd A Review on Uncertainty Analysis Methodologies for the Safety Case of a HLW Repository Jongtae Jeong Dong Keun Cho and Min Hoon Baik KAERI Comparison of DCF Values between ICRP 30 and ICRP 60 Using RESRAD-RECYCLE Sang Ho Lee Hyung Woo Seo and Chang Lak Kim KINGS Dose Assessment Considering Worker s Internal Exposure Factors Affecting Contaminated Metallic Waste Recycling Hyung Woo Seo Kessel David and Chang Lak Kim KINGS Scope Management System for Decommissioning Project Kook Nam Park Seung Kook Park Jae Hyun Ha and Young San Choe KAERI Jin Ho Park NuDecom 34

P03C15 P03C16 P03C17 P03C18 P03C19 P03C20 P03C21 P03C22 P03C23 P03C24 P03C25 P03C26 P03C27 P03C28 P03C29 P03C30 P03C31 P03C32 P03C33 P03C34 P03C35 P03C36 Laser Cutting Experiment of 100mm-stainless Steel Plate for Nuclear Decommissioning Seong Y Oh Jae Sung Shin Sangwoo Seon Taek Soo Kim Hyunmin Park Lim Lee Chin Man Chung Byung Seon Choi Jei Kwon Moon and Jonghwan Lee KAERI Fabrication of Silver-graphene Fiber Composite for Radioactive Iodine Adsorption Minseok Lee and Ho Jin Ryu KAIST Particle Separation of Non-Decontamination Soil Using Attrition and Washing Daeseo Koo Hyun Hee Sung Seung Soo Kim Sang Bum Hong Bum Kyoung Seo and Jong Won Choi KAERI The Impact of Below Detection Limit Samples in NPP Decommissioning Residual Risk Assessment Jung Hwan Kim Carol Hornibrook and Man Sung Yim KAIST Dissolution of Chemical Decontaminating Agent for a Foam Decontamination Chong Hun Jung In Ho Yoon Sang Yoon Park Wang Kyu Choi and Jei Kwon Moon KAERI So Hyeon Lee JNU Technical Review of Historical Site Assessment Experiences at U S Nuclear Power Plants DongHee Lee Wook Sohn SukBon Yoon and JeongJu Kim KHNP CRI Experience Review of Full System Decontamination for Decommissioned NPPs Jaeyong Lee Kyoungmin Kim Seo yeon Cho and Yong soo Kim HYU A Model Addressing Effect of Growing Oxide Layer on Tritium Permeation in a High Temperature Gas- Cooled Reactor Yunjeong Hong and Hyung Gon Jin KAERI Status of the Decommissioning Project Management Information System Development of KAERI in 2017 Yunjeong Hong Heeseong Park and Seungkook Park KAERI Review on Environmental Impact Assessment during Decommissioning of Foreign Nuclear Power Plants for Domestic Approach after Decommissioning Seo Yeon Cho Yong Soo Kim and Jaeyong Lee HYU How to Remove the Radioactive Cesium in Contaminated Soil Byoung Jik Kim Jee Yon Lee and Hee Yeul Choi KINS Min Wook Oh Hanbat Nat l Univ Comparison of Vacuum and Forced Helium Drying Methods for Dry Storage of Spent Nuclear Fuel Ju Chan Lee K S Bang S H Yu K S Seo and W S Choi KAERI Radioisotope Assessment of CANDU Spent Fuel Packages through Least Square Fitted Scaling Factors Chang Je Park Hyuk Han and Seunguk Yoo Sejong Univ Junhyeuk Kim and Hong Ju Ahn KAERI Structural Assessment Method of Spent Fuel Assembly under 0 3 m Horizontal Drop Condition of Transportation Cask Ki Seog Seo Sang Soon Cho and Woo Seok Choi KAERI Ken B Sorenson and Paul E McConnell SNL A Thermal Analysis of TN-24P Dry Storage Cask System Hyungju Yun and Kwangheon Park KHU Sensitivity Evaluations of Responses with Gamma Shield using SAMPLER Kyoon Ho Cha Min Chul Kim and Seo Jeong Lee KHNP CRI Fabrication and Properties of Metal Matrix Composites as a Neutron Absorber Material of the Spent Nuclear Fuel Dry Storage System Ji Won Mun Tae Gyu Lee and Ho Jin Ryu KAIST Thermal Performance Sensitivity of SNF Storage Rack Depend on Heat Distribution Tae Hyeon Kim and Sunghwan Chung KHNP CRI Dongkyu LEE KONES An Assessment of Uncertainty for a Head End Process in the Pyroprocessing Wonjong Song Hoyoung Shin Myeonghyeon Woo and Moosung Jae HYU Bounding Fuel Type for Criticality Analysis of Dry Storage Cask Kiyoung Kim and Sunghwan Chung KHNP CRI Design Features of an OASIS-32D Metal Cask for both Transport and Storage of SNF Kwang Jeok Ko Sung Hwan Kim Min Gyu Kim Yeon Ho Cho Hyun Min Kim and Joon Gi Ahn KEPCO E C Project Management System for Pyro Project Jeong Guk Kim Won Il Ko Geun Il Park and Hyo On Nam KAERI Hyuck Jong Kim 35

P03C37 P03C38 P03C39 P03C40 Improvement of Particle Recovery Method for Uranium Isotope Analysis Using SIMS Taehee Kim Jinkyu Park Chi Gyu Lee Sang Ho Lim and Sun Ho Han KAERI Age-dating of UO2 Based on 230 Th 234 U Determination by New Chemical Separation Method Using UTEVA Resin Eun Ju Choi Sang Ho Lim Sun Ho Han Ranhee Park Jinkyu Park and Chi Gyu Lee KAERI A Perylenediimide-Based Organic Microcrystal for the Efficient Removal of Uranium Dissolved in Aqueous Solution Jinkyu Park KAERI Jaeyeon Bae and Jinhee Park DGIST Determination of Organically Bound Tritium OBT in a Wheat Sample and Its Interlaboratory Comparison Study Young Gun Ko Chang Jong Kim Young Hyun Cho Geun Sik Choi Kun Ho Chung and Mun Ja Kang KAERI 36

4 (Nuclear Fuel and Materials) 4A 5. 18 ( ) (Materials Degradation) Yun Soo Lim Hyung Ha Jin 201A 09 00 09 40 10 00 10 20 10 40 11 00 11 20 11 40 12 00 12 20 Review on Hydride Reorientation Phenomena in the Zirconium Alloy Cladding in the Long-term Dry Storage Yong Soo Kim HYU The Role of Surface Oxidation on Primary Water Stress Corrosion Cracking of Ni-base Alloys Yun Soo Lim Seong Sik Hwang Sung Woo Kim Dong Jin Kim and Hong Pyo Kim KAERI Role of Minor Alloying Elements on the Oxidation Behavior of Ni-base Alloys in a High Temperature Steam Environment Sung Hwan Kim Chaewon Kim and Changheui Jang KAIST PWSCC Behavior of Alloy 600 under Long-term Thermal Aging and Triaxial Stress Seung Chang Yoo Kyoung Joon Choi and Ji Hyun Kim UNIST Ji Soo Kim Byoung Ho Choi and Yun Jae Kim KU Jong Sung Kim Sejong Univ Coffee Break Evaluation of Thermal Aging Effect on Stress Corrosion Cracking Resistance in Fusion Boundary of A533 Gr B and Alloy 152 Kyoung Joon Choi Seung Chang Yoo Taeho Kim Seunghyun Kim and Ji Hyun Kim UNIST The Moat Susceptible Reason of Low Temperature Mill Annealed LTMA Alloy 600 to PWSCC SungSoo Kim and YoungSuk Kim KAERI The Effect of Proton Irradiation on the Micromechanical Hardness of Ferritic Martensitic Steel Jeonghyeon Lee Tae Yong Kim and Ji Hyun Kim UNIST Application of Proton Irradiation for Study on Radiation Damage of Reactor Pressure Vessel Steel Hyung Ha Jin Gyeong Geun Lee Kunok Chang Sangyeob Lim and Junhyun Kwon KAERI The Validity of First-principles Calculation on Evaluation of Density and Bulk Modulus in Liquid Sodium Jeong Hwan Han and Takuji Oda SNU 4B 5. 19 ( ) (Nuclear Materials) Heung Seok Kang Ho Jin Ryu 201A 09 00 09 30 10 00 10 20 10 40 Accident Tolerant Fuel Pellet R D Strategy Review Song Kun Woo KAERI Accident Tolerant Fuel Cladding in Progress Young Jin Kim FNC Tech Recent Fuel Safety Concerns in KINS Joosuk Lee and Hyedong Jeong KINS Development Status of Surface Modified-Zr Cladding Concept for Accident Tolerant Fuel in LWRs Hyun Gil Kim Il Hyun Kim Yang Il Jung Dong Jun Park Jung Hwan Park Byung Kwon Choi Young Ho Lee Jae Ho Yang and Yang Hyun Koo KAERI Coffee Break 37

11 00 11 20 11 40 12 00 12 20 Numerical Study of Crack Behavior in UO2-5 vol Mo Micro-cell Heung Soo Lee and Dong Rip Kim HYU Dong Joo Kim Jae Ho Yang and Yang Hyun Koo KAERI Vibration Tests for PWR Fuel Assemblies Submerged in Still Water with a Modal Shaker and a Seismic Shaker Heung Seok Kang Kang Hee Lee and Soo Ho Kim KAERI Fabrication of Neutron Absorber Containing Ceramic Composite Pellets by Using Microwave Sintering Qusai Mistarihi Mohd Sykuri Yahya Yonghee kim and HoJin Ryu KAIST Wooseong Park and Kyungseok Nam KHU Progress II on the 2nd Irradiation Test of the Metallic Fuel for SFR in the HANARO Bong Goo Kim Junehyung Kim Jin Sik Cheon and Chan Bock Lee KAERI Experimental Observation on Burst Behaviors of HANA-6 Cladding in LOCA Conditions Hun Jang Sung Yong Lee Dae Il Kim Jea Young Lim Yoon Ho Kim and Yong Kyoon Mok KEPCO NF 4C 5. 19 ( ) 13 30 13 50 14 10 14 30 14 50 15 10 15 30 15 50 16 10 16 30 & (Nuclear Fuels & Materials) Hee Sang Shim Sang Gil Park 201A Study on Chemical Variations of Interface between U-Zr Alloy and Fe through Annealing Young Sang Youn Jeongmook Lee Jong Hwan Kim Hoon Song Jeong Yong Park and Jong Yun Kim KAERI Air Oxidation Kinetics of Zircaloy-4 Sanggil Park ACT Co Ltd Yunhwan Maeng and Jaeyoung Lee HGU Effect of Fuel Cladding Surface Modification on Crud Deposition in a Simulated Primary PWR Condition Seung Heon Baek Hee Sang Shim and Do Haeng Hur KAERI Aging Effect on Thermal Transient Behavior of Fuel Cladding of Sodium-cooled Fast Reactor Sang Hun Shin Jun Hwan Kim Woo Seog Ryu and Sung Ho Kim KAERI Hyeong Min Heo HYU Modeling of Molten Pool Flow Simulation for Zr Tube GTAW Process Dae Won Cho KIMM Tae Hyung Na KNFC Coffee Break Effect of Chromium Contents on Corrosion Behavior of Ni-Cr-Fe Alloys in PWR Primary Coolant Hee Sang Shim Hyun Jin Cha and Do Haeng Hur KAERI Analysis on Chemical States of the Second-row Impurity Atoms in Liquid Lead-Bismuth Eutectic Junhyoung Gil and Takuji Oda SNU Effects of Dissolved Hydrogen on General Corrosion of Alloy 690TT and Boron Accumulation within Its Oxide Films in PWR Primary Water Soon Hyeok Jeon Geun Dong Song and Do Haeng Hur KAERI Microstructure Evolution and Chemical Analysis on Carbon Steels and Fe-Cr-Mo Alloys after FAC Simulation Tests Seunghyun Kim Taeho Kim Yun Ju Lee and Ji Hyun Kim UNIST 4D 5. 18 ( ) - 19 ( ) P04D01 (Nuclear Materials) - POSTER Hun Jang Young Gwan Jin 5 18 13 00 18 00 5 19 09 00 17 00 5 18 13 00 15 00 3 An Analysis on the TRISO Failure Due to Pd-SiC Interactions in a 350-MWth Prismatic HTR Fuel Young Min Kim and Chang Keun Jo KAERI 38

P04D02 P04D03 P04D04 P04D05 P04D06 P04D07 P04D08 P04D09 P04D10 P04D11 P04D12 P04D13 P04D14 P04D15 P04D16 P04D17 P04D18 P04D19 Preliminary Study on the Application of Booster Fuel for HANARO Irradiation Facility Seongwoo Yang Seung Jae Park Yoon Taeg Shin Man Soon Cho and Kee Nam Choo KAERI Tribological Characteristics of Surface-Modified Zr-Based Fuel Cladding Against Pre-Oxidized Spacer Grid Young Ho Lee Dong Jun Park Hyun Gil Kim and Jae Ho Yang KAERI On the Dimensional Change of Coated Fuel Particles Upon Irradiation Testing Young Woo Lee Jihae Yoon Yeon Ku Kim Seunghwan Yeo Youngjun Kim Heemoon Kim Moon Sung Cho and Eung Seon Kim KAERI Three-point Bending Test of Irradiated Fuel Cladding in Hot Cell Y G Jin S J Baik B O Yoo S Y Baek and H M Kim KAERI Experimental Investigation on Transient Thermo-mechanical Behavior of Claddingunder LOCA Using Fuel Simulator Ashwini Kumar Yadav Chang Hwan Shin Sung Uk Lee and Hyo Chan Kim KAERI Dependence of ZrN Coating Failure of U-Mo Particle on Coating Thickness at High Temperature Ji Hyeon Kim and Dong Seong Sohn UNIST Sunghwan Kim Kyu Hong Lee and Chong Tak Lee KAERI Development of Vacuum System for High-temperature Heating Test in Hotcell Young jun Kim Yong Sun Choo Boung Ok Yoo Ki Soo Kim Gil Soo Kim Ju Seong Kim and Junehyung Kim KAERI Effects of U3MoSi2 and Ti-rich Layers on the Diffusion between U and Al JuJin Won Sunghwan Kim KyuHong Lee YongJin Jeong KiNam Kim JongMan Park and ChongTak Lee KAERI Uncertainty of the Oxide Layer Thickness Formed on the Aluminum Cladding of U Mo Al Plate-Type Dispersion Fuel Faris B Sweidan and Ho Jin Ryu KAIST Young Wook Tahk and Jeong Sik Yim KAERI End Plug Weld Properties of FMS Cladding Tube for SFR Fuel Fabrication I Seul Ryu and Sun Ik Hong CNU Jung Won Lee Sung Ho Kim and Jeong Yong Park KAERI Fission Energy Deposition in UO2 through Multi-scale Physics Hierarchy Modeling From the First- Principles and SRIM to Molecular Dynamics Woong Kee Kim and Ji Hoon Shim POSTECH Massoud kaviany U Michigan Preliminary Study on the Preparation of UCO Kernel with C-ADU Gels for VHTR Fuel in Korea Kyung chai Jeong Sung whan Yeo Yeon ku Kim Sung ho Eom Moon sung Cho and Eung sun Kim KAERI Fabrication and Out-of-pile Test of Large Grain UO2 Pellets JangSoo Oh KeonSik Kim Dong Soo Kim JongHun Kim DongSeok Kim and JaeHo Yang KAERI Characterization of Additive-Doped UO2 Pellets with Thermal Annealing Tests Dong Seok Kim Jang Soo Oh Dong Joo Kim Jong Hun Kim Keon Sik Kim and Jae Ho Yang KAERI The Effects of Cr 2 Ion Irradiation on the Formation of Precipitation in Multi-metallic Layer Composite Cladding Processed by Hot Isostatic Pressing Tae Yong Kim Jeong Hyeon Lee and Ji Hyun Kim UNIST Preliminary Conceptual Design for U-Zr Fuel Manufacturing Facility Jong Hwan Kim Ki Hwan Kim SeongWoo Kuk Jung Won Lee Seok Jin Jin Young Ho Lee Jeong Yong Park and Chan Bock Lee KAERI Oxidation Behavior of Zirconium Alloys with Nanostructured Oxide Films in High Temperature Steam Environments Yang Jeong Park Jung Woo Kim and Sung Oh Cho KAIST High Temperature Oxidation Behavior of the Aluminide Coated Refractory Samples in Steam Environment Je Kyun Baek Woojin Lim JaeJoon Kim and Ho Jin Ryu KAIST 39

4E 5. 18 ( ) - 19 ( ) P04E01 P04E02 P04E03 P04E04 P04E05 P04E06 P04E07 P04E08 P04E09 P04E10 P04E11 P04E12 (Materials Degradation) - POSTER Hyung Ha Jin Chi Bum Bahn 5 18 13 00 18 00 5 19 09 00 17 00 5 18 13 00 15 00 Varification of Magnetostrictive Guided Wave Technique with an Elimination of Unwanted Geometry Signals for Detection and Monitoring of Defects in a Pipe Weld Yong Moo Cheong Se Beom Oh Duck Hyun Lee and Kyung Mo Kim KAERI Estimation of Primary Radiation Damage Cross Sections for Iron Junhyun Kwon Gyeong Geun Lee Kunok Chang Hyung Ha Jin and Sangyeob Lee KAERI FAC Test on the Dissimilar Metal Welded Pipeline in High Flow Conditions Kyung Mo Kim Jong Yeon Lee Eun Hee Lee Yong Moo Choeng Se Beom Oh and Dong Jin Kim KAERI Development of Material Databases and Volume Heat Source for Temper Bead Welding Process Jangho Ahn ESI Korea Won Geun Yi DOOSAN Sungbu Choi KINS Sensitization Condition of Alloy 182 Welds Joined by Stainless Steel 304 and Low Alloy Steel SA 508 Jae Young Yoon KAERI Tae Hyun Lee KIMM Il Soon Hwang SNU Eddy Current Simulation for Steam Generator Tube with Deposit Ga Hyun Choi Duck Hyun Lee and Kyung Mo Kim KAERI Development of High Temperature Oxidation Resistant High Entropy Alloys for Coating Materials of Accident Tolerance Fuel Cladding JaeJoon Kim and HoJin Ryu KAIST Radiation Hardening and Swelling in Ti-bearing Reduced Activation Ferritic-Martensitic Steels Jungwoo Huh and Chansun Shin MJU Hyung Ha Jin KAERI Chang Hoon Lee KIMS Effect of Copper Addition on Oxide Properties and Corrosion Resistance of Niobium Containing Zirconium Alloy in High Dissolved Hydrogen Primary Water Chemistry Yunju Lee Taeho Kim and Ji Hyun Kim UNIST Study of Irradiation Defect Kinetics in Metal Systems Sang Il Choi and Ji Hyun Kim UNIST Gyeong Geun Lee and Junhyun Kwon KAERI 3 CRUD Adhesion Test Equipment Set-up Logics under Heat Transfer Thermohydraulic and Computational Simulation Analysis Junhyuk Ham Taeho Kim Yun Ju Lee and Ji Hyun Kim UNIST A Study on Development of Probabilistic Crack Initiation Model for Alloy 182 Weld Jae Phil Park Chanseok Park and Chi Bum Bahn PNU 4F 5. 18 ( ) - 19 ( ) P04F01 P04F02 (Materials Development) - POSTER Min Chul Kim Jun Hyun Kwon 5 18 13 00 18 00 5 19 09 00 17 00 5 18 13 00 15 00 Combinatorial Techniques for Oxidation Resistant Refractory High Entropy Alloys RHEA Ulanbek Auyeskhan and Ho Jin Ryu KAIST Utilization of a Liquid Metal as Thermal Media in the Irradiation Capsule Man Soon Cho Seong Woo Yang Kee Nam Choo and Byung Hyuk Jun KAERI 3 40

P04F03 P04F04 P04F05 P04F06 P04F07 Material Irradiation Testing Schedule after Reoperation of HANARO Kee Nam Choo Man Soon Cho Sung Woo Yang Yoon Taek Shin Seng Jae Park Byung Hyuk Jun and Myong Seop Kim KAERI Evaluation of Heat Treatment on Microstructure and Mechanical Properties of Modified 9Cr-2W Steel by Compression Test Hyeong Min Heo and Jong Ryoul Kim HYU Jun Hwan Kim and Sung Ho Kim KAERI Status of Oxide Dispersion Strengthened High Entropy Alloys Development SeungHyeok Chung and Ho Jin Ryu KAIST Influence of Boron on Precipitation Behavior and Mechanical Properties in Modified 9Cr Steel for SFR Fuel Cladding after Aging Eun Hee Jeong and Young Do Kim HYU Sung Ho Kim KAERI The Effect of Cooling Rate on the Microstructure and Hardness of 9Cr-1Mo ODS Steel Ki Nam Jang and Kyu Tae Kim DGU Sanghoon Noh Suk Hoon Kang Ga Eon Kim and Tea Kyu Kim KAERI 41