지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
이용수
등록된 정보가 없습니다.
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Derivation and Comparison of Preliminary Derivation Concentration Guideline Level (DCGL) According to Scenarios of Kori Unit 1 Using RESRAD-BUILD
한국방사성폐기물학회 학술대회
2019 .01
Derivation of preliminary derived concentration guideline level (DCGL) by reuse scenario for Kori Unit 1 using RESRAD-BUILD
Nuclear Engineering and Technology
2020 .01
Derivation of DCGLs for the Surface Soil of Kori-1 NPP by Using RESRAD Probabilistic Analysis
한국방사성폐기물학회 학술대회
2017 .01
Derivation of Surface Soil DCGL for Kori-1 NPP Reuse Scenario
한국방사성폐기물학회 학술대회
2017 .01
Derivation of preliminary derived concentration guideline levels for surface soil at Kori Unit 1 by RESRAD probabilistic analysis
Nuclear Engineering and Technology
2018 .01
A study on the dose evaluation of critical groups for unrestricted reuse of the site after the decommissioning of Kori Unit 1
Nuclear Engineering and Technology
2024 .08
External exposure specific analysis for radiation worker in reuse of containment building for Kori Unit 1
Nuclear Engineering and Technology
2022 .05
A Methodology of Selecting Potential Radionuclides for the Kori Unit 1 DCGL Calculation
한국방사성폐기물학회 학술대회
2018 .01
Derivation of Surface Soil Area Factor for Kori-1 NPP by Using RESRAD-ONSITE
한국방사성폐기물학회 학술대회
2018 .01
Study on Dismantling Scenario for Large Components of Kori Unit 1
한국방사성폐기물학회 학술대회
2018 .01
Analysis of Exposure Dose by RESRAD Sensitivity Analysis
한국방사성폐기물학회 학술대회
2018 .01
Preliminary Evaluation of DCGLs for Site Release After Decommissioning of Korean Research Reactor 1 & 2
한국방사성폐기물학회 학술대회
2017 .01
Simulation-Based Evaluation for the Dismantling Scenario of the Reactor Vessel at Kori Unit 1
한국방사성폐기물학회 학술대회
2017 .01
Calculation of Preliminary Site-Specific DCGLs for Nuclear Power Plant Decommissioning Using Hybrid Scenarios
Nuclear Engineering and Technology
2019 .01
A study on DCGL determination and the classification of contaminated areas for preliminary decommission planning of KEPCO-NF nuclear fuel fabrication facility
Nuclear Engineering and Technology
2019 .01
Status of Development of Final Decommissioning Plan for Kori Unit 1
한국방사성폐기물학회 학술대회
2019 .01
Process Development for Kori Unit 1 Reactor Vessel Segmentation
한국방사성폐기물학회 학술대회
2018 .01
Some Derivations on d-Algebras
INTERNATIONAL JOURNAL of FUZZY LOGIC and INTELLIGENT SYSTEMS
2018 .12
A Study on the Development of Interview Procedure for HSA at Kori Unit 1
한국방사성폐기물학회 학술대회
2018 .01
Study on Segmentation Plan for Kori Unit 1 Reactor Vessel Internal
한국방사성폐기물학회 학술대회
2018 .01
0