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WRFPM 2017

Today: 2018.05.23
END

Daily Program

Program  >  Daily Program

Plenary 2
Enhanced Safety of Current Fuel
  • Time: 09:00-10:30
  • Venue: Ramada Ballroom 1 (2F)
  • Chair(s):  Kwangheon PARK (Kyung Hee University, Korea, Republic of)
    Bo CHENG (Electric Power Research Institute, United States)
09:00-09:30
IA-003

Halden's In-Pile Test Technology for Demonstrating the Enhanced Safety of Water Reactor Fuels

Margaret McGRATH (OECD Halden Reactor Project / IFE, Norway)
09:30-10:00
IA-009

Fuel Technology Development in KNF

Jung-Tack KWON (KEPCO Nuclear Fuel Company, Korea, Republic of)
10:00-10:30
IA-005

New LOCA and RIA Safety Criterai in France

Stephanie GRAFF (IRSN, France) Sandrine BOUTIN, Aude FOUCHER TAISNE, Olivier DUBOIS
Coffee Break & Poster Viewing
  • Time: 10:30-11:00
  • Venue: Ramada Ballroom Foyer (2F)
T2-05
SiC Cladding I
  • Time: 11:00-11:40
  • Venue: Ramada Ballroom 1 (2F)
  • Chair(s):  Weon-Ju KIM (Korea Atomic Energy Research Institute, Korea, Republic of)
    Jeremy BISCHOFF (AREVA, France)
11:00-11:20
A-110

Properties of SiC-SiC Cladding for Accident Tolerant Fuel Irradiation Test Rodlets

Christian DECK (General Atomics, United States) Hesham KHALIFA, George JACOBSEN, Jon SHEEDER, Jiping ZHANG, Carlos BACALSKI, Gokul VASUDEVAMURTHY, Edward LAHODA, Chunghao SHIH, Christina BACK, Rolf HAEFELFINGER, Sarah OSWALD, Kirill SHAPOVAKOV, Eric SONG, Joshua STONE
11:20-11:40
A-225

The Applicability of SiC-SiC Fuel Cladding to Conventional PWR Power Plant

Kenichiro FURUMOTO (Mitsubishi Nuclear Fuel, Co., Ltd., Japan) Seiichi WATANABE, Teruhisa YAMAMOTO, Hideyuki TESHIMA, Shinichiro YAMASHITA, Hiroaki SAITO, Noriko SHIRASU
T5-03
LOCA Modeling
  • Time: 11:00-12:00
  • Venue: Ramada Ballroom 2 (2F)
  • Chair(s):  Kwangheon PARK (Kyung Hee University, Korea, Republic of)
    Kazuyuki KUSAGAYA (Global Nuclear Fuel-Japan, Japan)
11:00-11:20
A-042

Assessment of Fraptran Modeling of Large Strains under Loss of Coolant Accidents

Santiago BERMEJO (CIEMAT, Spain) Luis Enrique HERRANZ
11:20-11:40
A-053

Fuel Performance Modeling of FeCrAl Cladding Failure during Loss of Coolant Conditions

Kyle GAMBLE (Idaho National Laboratory, United States) Jason HALES, Giovanni PASTORE, Tommaso BARANI, Davide PIZZOCRI, Kurt TERRANI
11:40-12:00
A-181

Mechanical Robustness of AREVA's GAIA Fuel Design under Seismic and LOCA Excitations

Brian PAINTER (AREVA NP, United States) Brett MATTHEWS, Pierre-henri LOUF, Herve LEBAIL, Veit MARX
T3-03
Reactor Testing
  • Time: 11:00-12:00
  • Venue: Ramada Ballroom 3 (2F)
  • Chair(s):  Sang Jong LEE (KEPCO Nuclear Fuel Company, Korea, Republic of)
    Viktors GRISMANOVS (Institute for Energy Technology, Norway)
11:00-11:20
A-180

Summary of Test Reactor Experiments to Simulate Secondary Fuel Degradation and Its Mitigation

David SCHRIRE (VATTENFALL, Sweden) Jonathan WRIGHT, Terje TVERBERG, Suresh YAGNIK, Magnus LIMBACK
11:20-11:40
A-078

Behavior of High-burnup Advanced LWR Fuels under Design-basis Accident Conditions

Masaki AMAYA (Japan Atomic Energy Agency, Japan) Yutaka UDAGAWA, Takafumi NARUKAWA, Takeshi MIHARA, Yoshinori TANIGUCHI
11:40-12:00
A-274

Development of the Treat Transient Testing Program

Daniel WACHS (Idaho National Laboratory, United States) Nicolas WOOLSTENHULME, Colby JENSEN
T4-02
Transportation and Storage of Spent Nuclear Fuel
  • Time: 11:00-11:40
  • Venue: Mara (2F)
  • Chair(s):  Yongdeog KIM (Korea Hydro & Nuclear Power Co., Ltd., Korea, Republic of)
    Holger VOELZKE (Bundesanstalt fur Materialforschung und -pruefung, Germany)
11:00-11:20
A-034

Dry Storage of Spent Nuclear Fuel and High Active Waste in Germany

Gerold SPYKMAN (TÜV NORD EnSys GmbH & Co. KG, Germany)
11:20-11:40
A-290

The New Castor® Geo - Comprehensive Solutions for Transport and Storage of Spent Nuclear Fuel, MOX and Damaged Fuel

Linus BETTERMANN (GNS Gesellschaft Für Nuklear-Service mbH, Germany) Jürgen SKRZYPPEK, Roland HUEGGENBERG, Ralf SCHNEIDER-EICKHOFF
Luncheon
  • Time: 12:00-13:30
  • Venue: Restaurants (1F)
T2-06
SiC Cladding II
  • Time: 13:30-15:30
  • Venue: Ramada Ballroom 1 (2F)
  • Chair(s):  Weon-Ju KIM (Korea Atomic Energy Research Institute, Korea, Republic of)
    Peng XU (Westinghouse Electric Company, United States)
13:30-13:50
A-238

Safety Evaluation of Accident Tolerant Fuel with SiC/SiC Cladding

Hisaki SATO (TOSHIBA, Japan) Yutaka TAKEUCHI, Kazuo KAKIUCHI, Shinichiro YAMASHITA, Fumihisa NAGASE
13:50-14:10
A-184

Status of Westinghouse SiC Composite Cladding Fuel Development

Peng XU (Westinghouse Electric Company, United States) Edward LAHODA, Richard JACKO, Frank BOYLAN, Robert OELRICH
14:10-14:30
A-177

Improving the Corrosion Resistance of Silicon Carbide for Fuel in BWR Environments by Using a Metal Coating

Ryo ISHIBASHI (Hitachi-GE Nuclear Energy, Ltd., Japan) Shigetada TANABE, Takao KONDO, Shinichiro YAMASHITA, Fumihisa NAGASE
14:30-14:50
A-213

Influence of Water Chemistry and Microstructure on the Hydrothermal Corrosion of SiC Ceramics

Weon-Ju KIM (Korea Atomic Energy Research Institute, Korea, Republic of) Jungho SHIN, Daejong KIM, Hyeon-Geun LEE, Ji Yeon PARK, Jung-Hwan PARK
14:50-15:10
A-260

SiC Composite for BWR Channel Application

Ken YUEH (Electric Research Institute, United States) Gordon KOHSE, Ronghua WEI, Yutai KATOH, Thiago SEUACIUC-OSORIO
15:10-15:30
A-108

Silicon Carbide Cladding Behaviour: Experiments and Modeling at Paul Scherrer Institute

Cedric COZZO (Paul Scherrer Institute, Switzerland) Johannes BERTSCH, Loic FAVE, Saidur RAHMAN, Abdelhamid DOKHANE, Matthias KRACK, Manuel A. POUCHON, Yong DAI, Jia-Chao CHEN, Martin PYTEL
T2-07
FeCrAl Claddings
  • Time: 13:30-15:30
  • Venue: Ramada Ballroom 2 (2F)
  • Chair(s):  Jae Ho YANG (Korea Atomic Energy Research Institute, Korea, Republic of)
    Masaki KURATA (Japan Atomic Energy Agency, Japan)
13:30-13:50
A-033

Overview of Japanese Development of Accident Tolerant FeCrAl-ODS Fuel Claddings for BWRs

Kan SAKAMOTO (Nippon Nuclear Fuel Development Co. Ltd, Japan) Mutsumi HIRAI, Shigeharu UKAI, Akihiko KIMURA, Akifumi YAMAJI, Kazuyuki KUSAGAYA, Takao KONDO, Shinichiro YAMASHITA
13:50-14:10
A-287

Progress of GE Development of Accident Tolerant Fuel FeCrAl Cladding

Russell E. STACHOWSKI (Global Nuclear Fuel-Americas, LLC, United States) Russ FAWCETT, Raul REBAK, William P. GASSMANN, John WILLIAMS, Kurt TERRANI
14:10-14:30
A-032

Analytical Study of the Applicability of FeCrAl-ODS Cladding for BWR

Sho TAKANO (Global Nuclear Fuel - Japan Co., Ltd., Japan) Kazuyuki KUSAGAYA, Daisuke GOTO, Kan SAKAMOTO, Shinichiro YAMASHITA
14:30-14:50
A-068

Irradiation Testing of Accident Tolerant Fuel FeCrAl Cladding

Kevin FIELD (Oak Ridge National Laboratory, United States) Richard HOWARD, Christian PETRIE, Kurt TERRANI
14:50-15:10
A-059

Welding Technology R&D of Japanese Accident Tolerant FeCrAl-ODS Fuel Claddings for BWRs

Akihiko KIMURA (Kyoto University, Japan) Sho YUZAWA, Kan SAKAMOTO, Mutsumi HIRAI, Kazuyuki KUSAGAYA, Shinichiro YAMASHITA
15:10-15:30
A-027

Weld Development of FeCrAl Thin-Wall Cladding for LWR Accident Tolerant Fuel

Jian GAN (Idaho National Laboratory, United States) Nathan JERRED, Emmanuel PEREZ, Haiming WEN, Dc HAGGARD
T3-04
Loss of Coolant Accidents
  • Time: 13:30-15:10
  • Venue: Ramada Ballroom 3 (2F)
  • Chair(s):  Sang Jong LEE (KEPCO Nuclear Fuel Company, Korea, Republic of)
    Jinzhao ZHANG (Tractebel - ENGIE, Belgium)
13:30-13:50
A-162

Providing Durability in a LOCA Design Basis Accident of Fuel Rod Claddings Made of Electrolytic Zirconium E110 Alloy

Vladimir MARKELOV (JSC VNIINM, Russian Federation) Andrey MALGIN, Vladimir NOVIKOV
13:50-14:10
A-266

Results from In-cell Integral LOCA Testing at ORNL

Yong YAN (Oak Ridge National Laboratory, United States) Zachary BURNS, Kory LINTON, Kurt TERRANI
14:10-14:30
A-146

Experimental Study to Predict Effect of Azimuthal Temperature Difference on Thermo-Mechanical Behaviour of Clad Tube

Ashwini Kumar YADAV (Korea Atomic Energy Research Institute, Korea, Republic of) Chan LEE, Sung-Uk LEE, Chang Hwan SHIN, Hyo Chan KIM
14:30-14:50
A-178

The PERFROI Project Investigating the Thermal Mechanicals Behaviour of a Fuel Rod Assembly during a Loss of Coolant Accident

Georges REPETTO (Institut De Radioprotection Et De Sret Nuclaire, France) Cristina DOMINGUEZ, Tatiana TAURINES
14:50-15:10
A-188

A New Method to Enhance the Oxidation Resistance of a Zirconium Alloy Cladding: High-Temperature Pre-Oxidation 

Cheol Min LEE (Ulsan National Institue of Science and Technology, Korea, Republic of) Tae Won CHO, Gwan Yoon JEONG, Mi Jin KIM, Hee-Jae LEE, Jihyun KIM, Dong Seong SOHN
T1-03
Fuel Operating Experience and Performance II (Operating Experience and Fuel Failures)
  • Time: 13:30-15:30
  • Venue: Mara (2F)
  • Chair(s):  Hyeong Koo KIM (KEPCO Nuclear Fuel Company, Korea, Republic of)
    Hideyuki TESHIMA (Mitsubishi Nuclear Fuel, Japan)
13:30-13:50
A-009

The Application of Automatic Feeding Device in Recycling Treatment of UO2 with High Content of Fluorine in Dry Process

Lin XIA (CNNC Jianzhong Nuclear Fuel Co., Ltd, China) Lu BOXIANG
13:50-14:10
A-070

New Insights in the Fuel Grain Subdivision during In-plant Irradiation up to High Burn-Up

Mélanie CHOLLET (Paul Scherrer Institute, Switzerland) Cedric COZZO, Daniel GROLIMUND, Matthias MARTIN, Johannes BERTSCH
14:10-14:30
A-073

Operating Experience and Fretting Wear Performance of Plus7 Fuel

Yong Hwan KIM (KEPCO NF, Korea, Republic of)
14:30-14:50
A-199

Uranium Contamination of Repaired Fuel Assemblies

Mattias OLSSON (Forsmarks Kraftgrupp AB, Sweden)
14:50-15:10
A-201

Experiences from Concurrent Xenon and Helium Measurements for the Detection of Fuel Failures

Mattias OLSSON (Forsmarks Kraftgrupp AB, Sweden) Jan Ola HELMERSSON, Irina LARSSON
15:10-15:30
A-240

Feasibility Study of Using Gamma Emission Tomography for Identification of Leaking Fuel Rods in Commercial Fuel Assemblies

Scott HOLCOMBE (OECD Halden Reactor Project, Norway) Peter ANDERSSON
Coffee Break & Poster Viewing
  • Time: 15:30-16:00
  • Venue: Ramada Ballroom Foyer (2F)
Banquet
  • Time: 18:30 ~
  • Venue: Ramada Ballroom 1~3 (2F)
  • Close

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WRFPM 2017 Secretariat (c/o The Plan)
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