Development of Spent Fuel Cladding Degradation Model in Integrated Platform

Hong ,  Jong-Dae ,  Yang 외 5명

한국방사성폐기물학회 학술대회

2018 .01

Creep Model for PWR Spent Nuclear Fuel

Kim ,  Ju-Seong ,  Kim 외 7명

한국방사성폐기물학회 학술대회

2015 .01

Peak Cladding Temperature Analysis of a Spent Fuel Assembly According to Heat Transfer Modes

Kim ,  Hyungjin ,  Kim 외 2명

한국방사성폐기물학회 학술대회

2018 .01

Stress-Based Criterion for the Creep Response of Spent Nuclear Fuel Rod

Lee ,  Donghyo ,  Lee 외 3명

한국방사성폐기물학회 학술대회

2018 .01

Thermal creep effects of aluminum alloy cladding on the irradiation-induced mechanical behavior in U – 10Mo/Al monolithic fuel plates

Shu ,  ong Ding

Nuclear Engineering and Technology

2020 .01

Methodology of Delayed Hydride Cracking Assessment of Spent Fuel Cladding

Hong ,  Jong-Dae ,  Kim 외 5명

한국방사성폐기물학회 학술대회

2017 .01

The Effective Thermal Conductivity of Spent Fuel Assemblies for Spent Fuel Storage

Lee ,  Hee-Jae ,  Kim 외 3명

한국방사성폐기물학회 학술대회

2016 .01

Improvement of Spent Fuel Inspection System

Shin ,  Mu-gap ,  Kim 외 1명

한국방사성폐기물학회 학술대회

2017 .01

Development of Spent Fuel Nuclear Characteristic Evaluation System

Kim ,  Jae-Han ,  Kwon 외 7명

한국방사성폐기물학회 학술대회

2019 .01

Confirmatory Procedure of Spent Fuel Information for Spent Fuel Transport to the Interim Storage Facility

Yook ,  Daesik ,  Go 외 6명

한국방사성폐기물학회 학술대회

2017 .01

Circumferential steady-state creep test and analysis of Zircaloy-4 fuel cladding

최경하 ,  신창환 ,  김재용 외 1명

Nuclear Engineering and Technology

2021 .07

Thermal creep behavior of CZ cladding under biaxial stress state

Jin Xin ,  Lin Yuyu ,  Zhang Libin

Nuclear Engineering and Technology

2020 .12

Experimental Investigation of Temperature Profiles in Spent Fuel Model

Oh ,  Dong-seok ,  Shin 외 3명

한국방사성폐기물학회 학술대회

2019 .01

Segmented mandrel tests of as-received and hydrogenated WWER fuel cladding tubes

Ma ,  ton Ki ,  aly 외 8명

Nuclear Engineering and Technology

2021 .09

Estimation Radioactivity of Reference Spent Fuel With Time and Total Radioactivity of All Spent Fuel at 2035

Go ,  A ,  a 외 4명

한국방사성폐기물학회 학술대회

2017 .01

Creep Rupture Characteristics of Cladding Tubes of FC92B and FC92N: Candidate Alloys of SFR Fuel Cladding Tube Materials

Eun Hee Jeong ,  Jun Hwan Kim ,  Sung Ho Kim 외 1명

Metals and Materials International

2022 .06

CHARACTERISTICS OF SPENT COFFEE GROUND AS A HEATING FUEL

Sae Byul KANG ,  Hong Young OH ,  Jong Jin KIM 외 1명

AFORE

2015 .11

Critical Effect According to Number of Spent Fuel Nuclide

KIM ,  Yun-sik ,  Kim 외 1명

한국방사성폐기물학회 학술대회

2018 .01

Fatigue Life Characterization of Simulated Fuel Cladding to Hydride Contents for Normal Transportation Integrity

Lee ,  Kang-Hee ,  Kang 외 7명

한국방사성폐기물학회 학술대회

2019 .01

3D Digital Image Correlation 기법을 활용한 핵연료 피복관 고온 대변형 다차원 측정 실험

김동현 ,  김효찬 ,  이찬 외 2명

대한기계학회 춘추학술대회

2018 .12