• Title/Summary/Keyword: 처분

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Comprehensive Development Plans for the Low- and Intermediate-Level Radioactive Waste Disposal Facility in Korea and Preliminary Safety Assessment (우리나라 중·저준위 방사성폐기물 처분시설 종합개발계획(안)과 예비안전성평가)

  • Jung, Kang Il;Kim, Jin Hyeong;Kwon, Mi Jin;Jeong, Mi Seon;Hong, Sung Wook;Park, Jin Beak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.14 no.4
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    • pp.385-410
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    • 2016
  • The disposal facility in Gyeongju is planning to dispose of 800,000 packages of low- and intermediate- level radioactive waste. This facility will be developed as a complex disposal facility that has various types of disposal facilities and accompanying management. In this study, based on the comprehensive development plan of the disposal facility, a preliminary post-closure safety assessment is performed to predict the phase development of the total capacity for the 800,000 packages to be disposed of at the site. The results for each scenario meet the performance target of the disposal facility. The assessment revealed that there is a significant impact of the inventory of intermediate-level radionuclide waste on the safety evaluation. Due to this finding, we introduce a disposal limit value for intermediate-level radioactive waste. With stepwise development of safety case, this development plan will increase the safety of disposal facilities by reducing uncertainties within the future development of the underground silo disposal facilities.

A Complementary Analysis for the Structural Safety Evaluation of the Spent Nuclear Fuel Disposal Canister for the Pressurized Water Reactor (가압경수로(PWR)용 고준위폐기물 처분용기의 구조적 안전성 평가 보완 해석)

  • Choi, Jong-Won;Kwon, Young-Joo
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.20 no.4
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    • pp.427-433
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    • 2007
  • A structural model of the spent nuclear fuel disposal canister for the pressurized water reactor(PWR) for about 10,000 years long term deposition at a 500m deep granitic bedrock repository has been developed. However this developed structural model of the spent nuclear fuel disposal canister is too heavy to handle without any structural safety problem. Hence a lighter structural model of the spent nuclear fuel disposal canister which is easy to handle has been tried to develop very much. One of the reasons which made the structural model heavy is considered to be due to the severe adaptation of the design conditions like external loads and safety factor etc. to the canister design. Hence a complementary analysis to alleviate such severe design conditions is required for the reduction of the canister weight. In this study, a complementary structural analysis for the spent nuclear fuel disposal canister is carried out changing the design conditions such as external loads and safety factors to recalculate the design parameters like diameter and thickness etc. of the canister. The complementary analysis results shows that the diameter of canister can be shortened from 122cm to 102cm to reduce the weight of the spent nuclear fuel disposal canister.

A Study on Problems and Improvement Measures for Juvenile Protection Cases (소년보호사건의 처리상의 문제점과 개선방안)

  • Kang, Soo-Hwan
    • The Journal of the Korea Contents Association
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    • v.20 no.11
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    • pp.323-332
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    • 2020
  • The current juvenile law has to be improved in the following respects: First, there is no clear and objective basis for the process divided into criminal and protective dispositions. Second, the spirit of legislation to protect the boy is understandable, but when reviewing the application process of the juvenile law to actual juvenile crimes, it is hard to find such spirit. Third, in dealing with juvenile protection cases, the outcome and process of disposal should be reflected in the boy's protection ideology. Finally, efforts should be made to shorten the processing period of the case, curb the transfer of violent criminals to juvenile detention center, and integrate the latter part of the first and sixth disposition.

Basic Design of the Underground Research Tunnel for HLW disposal Research (고준위폐기물 처분연구를 위한 지하연구시설에 대한 기본설계)

  • 권상기;박정화;조원진;한필수
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2004.06a
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    • pp.199-207
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    • 2004
  • In order to develop a safe geological disposal concept for the HLW from the nuclear power plants in Korea, it is necessary to evaluate the safety of the disposal concept in an underground research tunnel in the same geological formation as the host rock mass. The design concept of a research tunnel depends on the actual disposal concept, repository geometry, experiments to be carried at the tunnel, and geological conditions. In this study, geological investigation had been carried out to develop the basic design of the small scale underground disposal research tunnel in KAERI.

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A Study on the Application of Standards for Clearance of Metal Waste Generated During the Decommissioning of NPP by Using the RESRAD-RECYCLE (RESRAD-RECYCLE을 활용한 원전 해체 시 발생하는 금속폐기물의 자체처분 기준 적용 연구)

  • Song, Jong Soon;Kim, Dong Min;Lee, Sang Heon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.14 no.4
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    • pp.305-320
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    • 2016
  • The metal waste generated during nuclear power plant decommissioning constitutes a large proportion of the total radioactive waste. This study investigates the current status of domestic and international regulatory requirements for clearance and the clearance experience of domestic institutions. The RESRAD-RECYCLE code was used for analyzing the clearance of the metal wastes generated during actual nuclear power plant decommissioning, and assessment of the exposure dose of twenty-six scenarios was carried out. The evaluation results will be useful in preliminary analysis of clearance and recycling during nuclear power plant decommissioning. As a next step, the effects of reducing disposal costs by clearance can be studied.

Thermohydromechanical Stability Study on the Joint Characteristics and Depth Variations in the Region of an Underground Radwaste Repository (절리 발달 특성 및 심도 변화에 의한 방사성폐기물 처분장 주변영역에서의 열수리역학적 안정성 연구)

  • Kim, Jhinwung;Daeseok Bae;Park, Chongwon
    • Tunnel and Underground Space
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    • v.13 no.2
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    • pp.153-168
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    • 2003
  • The objective of this present study is to understand long term(500 years) thermohydromechanical interaction behavior in the vicinity of a repository cavern on the joint location and repository depth variations. The model includes a saturated discontinuous granitic rock mass, PWR spent nuclear fuel in a disposal canister surrounded with compacted bentonite inside a deposition hole, and mixed bentonite backfilled in the rest of the space within a repository cavern. It is assumed that two joint sets exist within the model. Joint set 1 includes joints of 56$^{\circ}$ dip angle, spaced at 20 m, and joint set 2 is in the perpendicular direction to joint set 1 and includes joints of 34$^{\circ}$ dip angle, spaced at 20 m. In order to understand the behavior change on the joint location variations, 5 different models of 500m in depth are analyzed, and additional 3 different models of 1000 m in depth are analyzed to understand the effect of depth variation.

Basic Design of the Underground Tunnel for the Research on High-level Waste Disposal (고준위폐기물 처분연구용 지하터널의 기본설계)

  • Cho Won-Jin;Kwon Sang-Ki;Park Jung-Hwa;Hahn Pil-Soo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.2 no.4
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    • pp.279-292
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    • 2004
  • The underground research tunnel is essential to validate the integrity of a reference high-level waste disposal system, and the safety of geological disposal. In this study, a basic design of an underground research tunnel (URT) was tried to be developed. The candidate site for URT was described briefly, and it was intended to suggest the basic concept of the underground research tunnel. In order to develop the design of URT based on the basic concept, design requirements were established. Based on the basic concept and the design requirements, the basic design of URT was performed. Research items to be studied in the URT were also derived in this study.

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The Announcement Effects of Stock Repurchase and Stock Dispositions on Shareholder Wealth (자기주식 취득 및 처분 공시가 주주의 부에 미치는 영향 - 취득 및 처분목적을 중심으로 -)

  • Sul, Won-Sik;Kim, Soo-Jung
    • The Korean Journal of Financial Management
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    • v.22 no.1
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    • pp.37-69
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    • 2005
  • This study intends to verify whether stock repurchase, as well as stock dispositions, affects shareholder's wealth and also whether repurchase/dispositions has varying impact de-pending on its purpose. According to empirical analysis, announcement of stock repurchase results in positive abnormal returns when the objective of stock repurchase is stock price stabilization or cancellation of shares. However, when the purpose of stock repurchase is granting incentives to executives/employees, we get the negative abnormal returns. Also, the termination of stock trust for reason of expiration or stock dispositions of which goal is to give incentives to executive/employees has a negative impact on stock price, whereas direct dispositions of stock to raise cash or to improve financial structrue are shown to significantly increase the wealth of shareholders. Cross-section analysis also confirms that stock repurchase and dispositions has different impact on excess returns depending on its purpose. The results of this study imply that the dispositions of stock should be regarded as an important financial strategic tool to be used by companies and what's more, such studies dealing with stock repurchase or dispositions should take firm's purpose into consideration in their approach.

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Some notes on the Timing of Geological Disposal of CANDU Spent Fuels (CANDU 사용후핵연료 처분 착수 시점에 관한 소고)

  • Choi, Heui-Joo;Kook, Dong-Hak;Choi, Jong-Won
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.8 no.2
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    • pp.167-172
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    • 2010
  • CANDU spent fuel is to be disposed of at repository finally rather than recycled because of its low fissile nuclide concentration. But the difficult situation of finding a repository site can not help introducing a interim storage in the short term. It is required to find an optimum timing of geological disposal of CANDU spent fuels related to the interim storage operation period. The major factors for determining the disposal starting time are considered as safety, economics, and public acceptance. Safety factor is compared in terms of the decay heat and non-proliferation. Economics factor is compared from the point of the operation cost, and public acceptance factor is reviewed from the point of retrievability and inter-generation ethics. This paper recommended the best solution for the disposal starting time by analyzing the above factors. It is concluded that the optimum timing for the CANDU spent fuel disposal is around 2041 and that the sooner disposal time, the better from the point of technical and safety aspects.

Study on Basic Requirements of Geoscientific Area for the Deep Geological Repository of Spent Nuclear Fuel in Korea (사용후핵연료 심지층처분장부지 지질환경 기본요건 검토)

  • Bae, Dae-Seok;Koh, Yong-Kwon;Park, Ju-Wan;Park, Jin-Baek;Song, Jong-Soon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.10 no.1
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    • pp.63-75
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    • 2012
  • This paper gives some basic requirements and preferences of various geological environmental conditions for the final deep geological repository of spent nuclear fuel (SNF). This study also indicates how the requirements and preferences are to be considered prior to the selection of sites for a site investigation as well as the final disposal in Korea. The results of the study are based on the knowledge and experience from the IAEA and NEA/OECD as well as the advanced countries in SNF disposal project. This study discusses and suggests preliminary guideline of the disposal requirements including geological, mechanical, thermal, hydrogeological, chemical and transport properties of host rock with long term geological stabilities which influence the functions of a multi-barrier disposal system. To apply and determine whether requirements and preferences for a given parameter are satisfied at different stages during a site selection and suitability assessment of a final disposal site, the quantitative criteria in each area should be formulated with credibility through relevant research and development efforts for the deep geological environment during the site screening and selection processes as well as specific studies such as productions of safety cases and validation studies using a generic underground research laboratory (URL) in Korea.