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Copper Alloy Design for Preventing Sulfur-Induced Embrittlement in Copper

Materials, 2024-01, Vol.17 (2), p.350

2024

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Optimization of spent nuclear fuels per canister to improve the disposal efficiency of a deep geological repository in Korea

Nuclear Engineering and Technology, 2022, 54(8), , pp.2819-2827

2022

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Benefit and Cost Ratio Analysis of Direct Disposal and Pyro-SFR Fuel Cycle Alternatives Using the Results of Multi-Criteria Decision-Making in Korea

Energies (Basel), 2021-06, Vol.14 (12), p.3509

2021

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Thermal conductivity evaluation for bentonite buffer materials under elevated temperature conditions

Case studies in thermal engineering, 2022-02, Vol.30, p.101792, Article 101792

2022

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Ensemble Learning Approach for the Prediction of Quantitative Rock Damage Using Various Acoustic Emission Parameters

Applied sciences, 2021, Vol.11 (9), p.4008

2021

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Comparative Evaluation of Direct Disposal and Pyro-SFR Nuclear Fuel Cycle Alternatives Using Multi Criteria Decision Making in Korea

Energies (Basel), 2021-06, Vol.14 (12), p.3590

2021

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A Bayesian approach for probabilistic safety assessment of HLW repository

Annals of nuclear energy, 2020-04, Vol.138, p.107203, Article 107203

2020

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Numerical analysis of the effect of gap-filling options on the maximum peak temperature of a buffer in an HLW repository

Progress in nuclear energy (New series), 2019-03, Vol.111, p.138-149

2019

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ESTIMATION OF EXPOSURE DOSES FOR THE SAFE MANAGEMENT OF NORM WASTE DISPOSAL

Radiation protection dosimetry, 2018-11, Vol.181 (4), p.394-402

2018

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Effectiveness of source term optimization for higher disposal density of spent fuels in a deep geological repository

Annals of nuclear energy, 2014-09, Vol.71, p.125-129

2014

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Model Development for Risk-Based Safety Assessment of a Geological Disposal System of Radioactive Wastes Generated by Pyroprocessing of Pressurized Water Reactor Spent Fuel in Korea

Nuclear technology, 2018-07, Vol.203 (1), p.1-16

2018

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A methodology for a risk-based approach to complex scenarios in a long-term safety assessment of a radioactive waste repository

Nuclear engineering and design, 2014-03, Vol.268, p.58-63

2014

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Verification of Source Term Estimation Method against Measured Data for Decommissioning Waste from a CANDU Reactor

Journal of nuclear science and technology, 2011-07, Vol.48 (7), p.1087-1093

2011

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Progress of the long-term safety assessment of a reference disposal system for high level wastes in Korea

Progress in nuclear energy (New series), 2016-07, Vol.90, p.37-45

2016

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Comparison of calculated results with NTD measured data for establishment of burned core model for Monte Carlo simulation of HANARO reactor

Journal of radioanalytical and nuclear chemistry, 2015-02, Vol.303 (2), p.1629-1633

2015

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Sensitivity of Physics Parameters for Establishment of a Burned CANDU Full-Core Model for Decommissioning Waste Characterization

Journal of nuclear science and technology, 2011-02, Vol.48 (2), p.215-226

2011

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Advanced hybrid analysis system for nuclear facility design with best estimate source terms

Nuclear engineering and design, 2013-03, Vol.256, p.274-284

2013

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Verification of source term estimation method against measured data for spent fuel hardware characterization

Annals of nuclear energy, 2013-08, Vol.58, p.36-42

2013

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Characteristics of a Geological Disposal System for the Increasing Burn-up of Spent Nuclear Fuel in Korea

Journal of nuclear science and technology, 2007-10, Vol.44 (10), p.1306-1316

2007

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Radiation safety evaluation of the HANARO research reactor spent fuel disposal system

Nuclear technology & radiation protection, 2011-04, Vol.26 (1), p.50-57

2011

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Optimization of spent nuclear fuels per canister to improve the disposal efficiency of a deep geological repository in Korea

Nuclear engineering and technology, 2022, Vol.54 (8), p.2819-2827

2022

Volltextzugriff (PDF)

Verification of Source Term Estimation Method against Measured Data for Decommissioning Waste from a CANDU Reactor

Journal of nuclear science and technology, 2011-07, Vol.48 (7), p.1087

2011

Volltextzugriff (PDF)

Sensitivity of Physics Parameters for Establishment of a Burned CANDU Full-Core Model for Decommissioning Waste Characterization

Journal of nuclear science and technology, 2011-02, Vol.48 (2), p.215

2011

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Characteristics of a Geological Disposal System for the Increasing Burn-up of Spent Nuclear Fuel in Korea

Journal of nuclear science and technology, 2007, Vol.44 (10), p.1306

2007

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Source term characterization program for the decommissioning waste from a CANDU reactor

Progress in nuclear energy (New series), 2012-03, Vol.55, p.1-11

2012

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Copper Alloy Design for Preventing Sulfur-Induced Embrittlement in Copper

Optimization of spent nuclear fuels per canister to improve the disposal efficiency of a deep geological repository in Korea

Benefit and Cost Ratio Analysis of Direct Disposal and Pyro-SFR Fuel Cycle Alternatives Using the Results of Multi-Criteria Decision-Making in Korea

Thermal conductivity evaluation for bentonite buffer materials under elevated temperature conditions

Ensemble Learning Approach for the Prediction of Quantitative Rock Damage Using Various Acoustic Emission Parameters

Comparative Evaluation of Direct Disposal and Pyro-SFR Nuclear Fuel Cycle Alternatives Using Multi Criteria Decision Making in Korea

A Bayesian approach for probabilistic safety assessment of HLW repository

Numerical analysis of the effect of gap-filling options on the maximum peak temperature of a buffer in an HLW repository

ESTIMATION OF EXPOSURE DOSES FOR THE SAFE MANAGEMENT OF NORM WASTE DISPOSAL

Effectiveness of source term optimization for higher disposal density of spent fuels in a deep geological repository

Model Development for Risk-Based Safety Assessment of a Geological Disposal System of Radioactive Wastes Generated by Pyroprocessing of Pressurized Water Reactor Spent Fuel in Korea

A methodology for a risk-based approach to complex scenarios in a long-term safety assessment of a radioactive waste repository

Verification of Source Term Estimation Method against Measured Data for Decommissioning Waste from a CANDU Reactor

Progress of the long-term safety assessment of a reference disposal system for high level wastes in Korea

Comparison of calculated results with NTD measured data for establishment of burned core model for Monte Carlo simulation of HANARO reactor

Sensitivity of Physics Parameters for Establishment of a Burned CANDU Full-Core Model for Decommissioning Waste Characterization

Advanced hybrid analysis system for nuclear facility design with best estimate source terms

Verification of source term estimation method against measured data for spent fuel hardware characterization

Characteristics of a Geological Disposal System for the Increasing Burn-up of Spent Nuclear Fuel in Korea

Radiation safety evaluation of the HANARO research reactor spent fuel disposal system

Optimization of spent nuclear fuels per canister to improve the disposal efficiency of a deep geological repository in Korea

Verification of Source Term Estimation Method against Measured Data for Decommissioning Waste from a CANDU Reactor

Sensitivity of Physics Parameters for Establishment of a Burned CANDU Full-Core Model for Decommissioning Waste Characterization

Characteristics of a Geological Disposal System for the Increasing Burn-up of Spent Nuclear Fuel in Korea

Source term characterization program for the decommissioning waste from a CANDU reactor

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