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PYROPROCESS WASTE DISPOSAL SYSTEM DESIGN AND DOSE CALCULATION
Kook, Dong-Hak,Cho, Dong-Keun,Lee, Min-Soo,Lee, Jong-Youl,Choi, Heui-Joo,Kim, Yong-Soo Korean Nuclear Society 2012 Nuclear Engineering and Technology Vol.44 No.5
PWR spent fuels produced in the Republic of Korea are expected to be recycled by pyroprocess in the long term future. Even though pyroprocess waste amounts can be smaller than that of PWR spent fuel assembly in case of direct disposal, this process essentially will produce various and unique radioactive wastes. The goals of this article are to characterize these wastes, calculate the amount of wastes, design disposal systems for each waste and evaluate the radiation safety of each system by dose assessment. The absorbed dose results of the metal and ceramic waste for the engineering barrier system (EBS) showed $2.21{\times}10^{-2}$ Gy/h and $1.15{\times}10^{-2}$ Gy/h, which are lower than the recommended value of 1 Gy/h. These results confirmed that the newly proposed disposal systems have a safety margin for the radiation produced from each waste.
Dong-Hak Kook,Won-Myung Choung,Jeong-Hoe Ku,Il-Je Cho,Eun-Pyo Lee,Gil-Sung You 한국방사성폐기물학회 2004 방사성폐기물학회지 Vol.2 No.3
사용후핵연료의 효율적인 관리를 위하여 원자력연구소에서 개발중인 사용후핵연료 차세대관리 종합공정(ACP)은 공정타당성연구 단계를 마치고 이의 실증을 위한 - type핫셀 건설 단계에 이르렀다. 핫셀의 설계에 앞서 사용후핵 연료를 취급하게 되는 과정에서 발생할 수 있는 방사능에 대한 환경영향평가를 정상운전 시와 사고발생 시로 나누어 수행하였다. 평가에 필요한 자료들은 공정의 개념설계 보고서와 최근 연구소부지 기상 테이터 및 부지특성 자료를 바탕으로 하였으며 기존의 유사한 시설에 대한 평가방법을 참조하였다. 각 핵종별 발생량과 방출량을 계산하여 피폭선량을 계산하였으며 평가결과 원자력법관련 규제기준과 핫셀이 위치하게 되는 IMEF 건물의 안전성분석 기준보다 매우 안전한 결과를 얻어 시설 운영에 대한 안전성을 확보하였다. Advanced spent fuel Conditioning Process(ACP) project which is under development for efficient spent fuel management has finished process feasibility study and is preparing - type hot cell construction for process experimentation. Radiation dose evaluation for the radioactive nuclides were preliminarily performed for normal operation and accident case with the basic concept design report, the meteorological data and the recent site specific data. According to the production and release rate of nuclides, dose evaluations for residents around facility were performed. The evaluation result shows a safe margin for regulation limits and SAR(Safety Analysis Report) limit of IMEF(Irradiated Material Examination Facility) where this facility will be constructed.
Campylobacter rectus ATCC 33238에 대한 종 : 특이 DNA 프로브의 클로닝
국중기,정학균,성진효,손재범,김병옥,김동기 대한구강보건학회 2002 大韓口腔保健學會誌 Vol.26 No.4
The purpose of this study is to develope strain-specific DNA probes and polymerase chain reaction (PCR) primers for detection and identification of Camphyrobactor rectus (C, rectus) ATCC 33238. This study procedure included (1) whole-genomic DNA extraction of C. rectus ATCC 33238, (2) construction of the genomic DNA library, (3) screening of restriction fragment of genomic DNA by reverse dot hybridization, (4) isolation of strain-specific DNA probes by Southern blot hybridization. Thirty-five restriction fragments of C, rectus ATCC 33238 genomic DNA digested with the HindⅢ were obtained. Southern blot analysis data showed that two of them, Cr44-3 (832 bp) and Cr44-4 (669 bp) were C. rectus ATCC 33238 specific DNA probes. Our data indicate that these DNA probes may be useful in detection and identification of the C rectus ATCC 33238.
A Standardized Pathology Report for Gastric Cancer: 2nd Edition
Sung Hak Lee,Mee-Yon Cho,Young Soo Park,Myeong-Cherl Kook,Baek-Hui Kim,Hye Seung Lee,Dong-Wook Kang,Mi-Jin Gu,Ok Ran Shin,Younghee Choi,Wonae Lee,Hyunki Kim,In Hye Song,Kyoung-Mee Kim,Hee Sung Kim,Guh 대한위암학회 2023 Journal of gastric cancer Vol.23 No.1
The first edition of ‘A Standardized Pathology Report for Gastric Cancer’ was initiated by the Gastrointestinal Pathology Study Group of the Korean Society of Pathologists and published 17 years ago. Since then, significant advances have been made in the pathologic diagnosis, molecular genetics, and management of gastric cancer (GC). To reflect those changes, a committee for publishing a second edition of the report was formed within the Gastrointestinal Pathology Study Group of the Korean Society of Pathologists. This second edition consists of two parts: standard data elements and conditional data elements. The standard data elements contain the basic pathologic findings and items necessary to predict the prognosis of GC patients, and they are adequate for routine surgical pathology service. Other diagnostic and prognostic factors relevant to adjuvant therapy, including molecular biomarkers, are classified as conditional data elements to allow each pathologist to selectively choose items appropriate to the environment in their institution. We trust that the standardized pathology report will be helpful for GC diagnosis and facilitate large-scale multidisciplinary collaborative studies.
WASTE CLASSIFICATION OF 17×17 KOFA SPENT FUEL ASSEMBLY HARDWARE
Cho, Dong-Keun,Kook, Dong-Hak,Choi, Jong-Won,Choi, Heui-Joo Korean Nuclear Society 2011 Nuclear Engineering and Technology Vol.43 No.2
Metal waste generated from the pyroprocessing of 10 MtU of spent fuel was classified by comparing the specific activity of a relevant radionuclide with the limit value of the specific activity specified in the Korean acceptance criteria for a lowand intermediate-level waste repository. A Korean Optimized Fuel Assembly design with a 17${\times}$17 array, an initial enrichment of 4.5 weight-percent, discharge burn-up of 55 GWD/MtU, and a 10-year cooling time was considered. Initially, the mass and volume of each structural component of the assembly were calculated in detail, and a source term analysis was subsequently performed using ORIGEN-S for these components. An activation cross-section library generated by the KENO-VI/ORIGEN-S module was utilized for top-end and bottom-end pieces. As a result, an Inconel grid plate, a SUS plenum spring, a SUS guide tube subpart, SUS top-end and bottom-end pieces, and an Inconel top-end leaf spring were determined to be unacceptable for the Gyeongju low- and intermediate-level waste repository, as these waste products exceeded the acceptance criteria. In contrast, a Zircaloy grid plate and guide tube can be placed in the Gyeongju repository. Non-contaminated Zircaloy cladding occupying 76% of the metal waste was found to have a lower level of specific activity than the limit value. However, Zircaloy cladding contaminated by fission products and actinides during the decladding process of pyroprocessing was revealed to have 52 and 2 times higher specific activity levels than the limit values for alpha and $^{90}Sr$, respectively. Finally, it was found that 88.7% of the metal waste from the 17${\times}$17 Korean Optimized Fuel Assembly design should be disposed of in a deep geological repository. Therefore, it can be summarized that separation technology with a higher decontamination factor for transuranics and strontium should be developed for the efficient management of metal waste resulting from pyroprocessing.