Derivation of Surface Soil DCGL for Kori-1 NPP Reuse Scenario

Byon ,  Ji Hyang ,  Pa 외 4명

한국방사성폐기물학회 학술대회

2017 .01

Derivation of DCGLs for the Surface Soil of Kori-1 NPP by Using RESRAD Probabilistic Analysis

Byon ,  Ji Hyang ,  Pa 외 4명

한국방사성폐기물학회 학술대회

2017 .01

Derivation of Preliminary Derived Concentration Guideline Level (DCGL) by Containment Building Reuse Scenario for Kori Unit 1 Using RESRAD-BUILD

Pa ,  k ,  SangJune 외 4명

한국방사성폐기물학회 학술대회

2018 .01

Derivation and Comparison of Preliminary Derivation Concentration Guideline Level (DCGL) According to Scenarios of Kori Unit 1 Using RESRAD-BUILD

Pa ,  k ,  SangJune 외 4명

한국방사성폐기물학회 학술대회

2019 .01

Proposal for the list of potential radionuclides of interest during NPP site characterization or fi nal status surveys

서형우 ,  오재용 ,  신원규

Nuclear Engineering and Technology

2021 .01

A study on the dose evaluation of critical groups for unrestricted reuse of the site after the decommissioning of Kori Unit 1

서형우 ,  류강우 ,  나영일 외 3명

Nuclear Engineering and Technology

2024 .08

Status of Development of Final Decommissioning Plan for Kori Unit 1

Yoon ,  Suk Bon ,  Lee 외 3명

한국방사성폐기물학회 학술대회

2019 .01

Process Development for Kori Unit 1 Reactor Vessel Segmentation

Hwang ,  Young Hwan ,  Hwang 외 5명

한국방사성폐기물학회 학술대회

2018 .01

Study on Dismantling Scenario for Large Components of Kori Unit 1

Hwang ,  Young Hwan ,  Hwang 외 3명

한국방사성폐기물학회 학술대회

2018 .01

Preliminary Evaluation of DCGLs for Site Release After Decommissioning of Korean Research Reactor 1 & 2

Do ,  Tae Gwan ,  Pa 외 6명

한국방사성폐기물학회 학술대회

2017 .01

A Study on the Development of Interview Procedure for HSA at Kori Unit 1

Lee ,  Donghee ,  Sohn 외 5명

한국방사성폐기물학회 학술대회

2018 .01

Study on Segmentation Plan for Kori Unit 1 Reactor Vessel Internal

Hwang ,  Young Hwan ,  Hwang 외 5명

한국방사성폐기물학회 학술대회

2018 .01

Derivation of preliminary derived concentration guideline levels for surface soil at Kori Unit 1 by RESRAD probabilistic analysis

변지양 ,  박상준 ,  안석영

Nuclear Engineering and Technology

2018 .01

Derivation of preliminary derived concentration guideline level (DCGL) by reuse scenario for Kori Unit 1 using RESRAD-BUILD

박상준 ,  변지향 ,  반두현 외 3명

Nuclear Engineering and Technology

2020 .01

Conceptual Design for Kori Unit 1 Reactor Vessel and Internal Segmentation Process

Hwang ,  Young Hwan ,  Hwang 외 5명

한국방사성폐기물학회 학술대회

2017 .01

Calculation of Preliminary Site-Specific DCGLs for Nuclear Power Plant Decommissioning Using Hybrid Scenarios

서형우 ,  손욱

Nuclear Engineering and Technology

2019 .01

Simulation-Based Evaluation for the Dismantling Scenario of the Reactor Vessel at Kori Unit 1

Hyun ,  Dongjun ,  Kim 외 9명

한국방사성폐기물학회 학술대회

2017 .01

Assessment of soil density and distribution coefficient of Cs-137 for deriving DCGLs in korea research reactor unit 1 and 2

김근호 ,  김일국 ,  김광표

Nuclear Engineering and Technology

2024 .07

Effective Cross Section Estimation of Cl and Ca in Concrete of Kori Unit 1

Jang ,  Mee ,  Kim 외 5명

한국방사성폐기물학회 학술대회

2018 .01

A Study for Dismantling Method of Bio-shield in Kori Unit 1 Nuclear Power Plant

Pa ,  k ,  Kwang-Soo 외 6명

한국방사성폐기물학회 학술대회

2019 .01