• Journal of Radiation Protection and Research
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• 제21권3호
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• pp.155-166
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• 1996

모든 원자력 시설이나 기기들은 설치하기 전과 설치한 후에라도 설비를 개조하여야 할 때에는 ALARA 검토를 받아야 하는데, ALARA 설계측면에서 주요한 목적은 특별한 엔지니어링기법을 통해 작업자 피폭을 감소시킬 수 있는 분야가 무엇인지를 규명하는 것이다. ALARA 설계검토에서 고려하여야 할 기본적인 인자물로는 Crud 통제와 차폐와 격리, 접근성, 유지보수성과 신뢰성, 및 오염통제가 있다. 이처럼 다각적인 측면에서 ALARA 설계검토가 이루어져야 하므로 설계자들이 ALARA 설계검토를 하는 과정에서 검토되어야 할 기본적인 사항들이 누락되지 않도록 하기 위해서는 적절한 ALARA 점검표가 이용되어야 한다. 따라서 본 연구에서는 실제적인 ALARA 점검표를 개발하기 위하여 각각의 기본적인 ALARA 인자들 별로 검토하여야 할 항목들을 살펴보았다. 또 각각의 검토항목별로 어떤 사항들이 고려되어야 할 것인지에 대해 논하였으며, 설정된 기본인자들과 검토항목들을 토대로 ALARA 점검표가 개발되었다.

• Journal of Radiation Protection and Research
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• 제4권1호
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• pp.29-35
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• 1979

Comparison of the risk of death due to radiation exposure with the same risk due to occupational hazards in other safe industries underlines the importance of the ALARA principle. The outlined responsibilities and listed examples presented here can serve as a basis for expanding and developing the concepts necessary for its successful application.

• Nuclear Engineering and Technology
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• 제54권3호
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• pp.1136-1144
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• 2022

The effects of nearby residents and the public by the residual contamination from the decommissioning of nuclear facilities should comply with the dose criteria, and whether additional remediation action is necessary from the ALARA perspective must be determined. Therefore, we analyzed the requirements of ALARA action levels and performed preliminary ALARA evaluation. The ratio of residual contamination concentration to DCGL was calculated for the basement fill and the building occupancy mode. The results showed that the additional remediation actions below DCGL are not justified. In addition, we analyzed the effect of remediation area. It was noted that the increase of the remediation area showed a positive correlation with the Conc/DCGL value in the basement fill mode. On the other hand, in the building occupancy mode, since the floor area of the building is the target of remediation and has the effect of increasing the same as the evaluation area of the building occupants, but due to the difference in the amount of increase, the Conc/DCGL showed a negative correlation. We expect the approach and method of ALARA evaluation can be utilized for concrete cost-benefit calculation during the decommissioning or at the time of remediation.

• Journal of Radiation Protection and Research
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• 제13권2호
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• pp.95-98
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• 1988

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 추계학술발표회요약집
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• pp.357-357
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• 2002

• 동위원소회보
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• 제10권2호
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• pp.33-37
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• 1995

• Nuclear Engineering and Technology
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• 제53권1호
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• pp.351-356
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• 2021

Korean nuclear power plants (NPPs) have various radiation protection programs to attain radiation exposure as low as reasonably achievable (ALARA). In terms of ALARA, this paper provides a comprehensive overview of administrative dose control for occupationally-exposed workers in Korean NPPs. In addition to dose limits, administrative dose constraints are implemented to resolve an inequity of radiation exposure in which some individuals in NPPs receive relatively higher doses than others. Occupational dose constraints in Korean NPPs are presented in this paper with the background of how those values were determined. For pressurized water reactors, 80% and 90% of the annual average limit for an effective dose, 20 mSv/y, are set as the primary and secondary dose constraints, respectively. Pressurized heavy water reactors (PHWRs) have also established the primary and secondary dose constraints corresponding to 70% and 80% of the effective dose limit, and additional constraints for tritium concentration are provided to control internal exposure in PHWRs. Follow-up measures for exceeding these administrative dose constraints are also introduced compared to exceeding the dose limits. Finally, analysis results of dose distributions show how the implementation of administrative dose constraints impacted the occupational dose distributions in Korean NPPs during the years 2009-2018.

• 동위원소회보
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• 제10권2호
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• pp.26-32
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• 1995

• Imaging Science in Dentistry
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• 제45권4호
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• pp.263-265
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• 2015

Cone-beam computed tomography (CBCT) is routinely recommended for dental diagnosis and treatment planning. CBCT exposes patients to less radiation than does conventional CT. Still, lack of proper education among dentists and specialists is resulting in improper referral for CBCT. In addition, aiming to generate high-quality images, operators may increase the radiation dose, which can expose the patient to unnecessary risk. This letter advocates appropriate radiation dosing during CBCT to the benefit of both patients and dentists, and supports moving from the concept of "as low as reasonably achievable" (ALARA) to "as low as diagnostically acceptable" (ALADA).

• Nuclear Engineering and Technology
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• 제30권5호
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• pp.444-451
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• 1998

The cost-effective reduction of occupational radiation exposure (ORE) dose at a nuclear power plant could not be achieved without going through an extensive analysis of accumulated ORE dose data of existing plants. It is necessary to identify what are high ORE jobs for ALARA implementation. In this study, the Rank Sum Method (RSM) is used in identifying high ORE jobs. As a case study, the database of ORE-related maintenance and repair jobs for Kori Units 3 and 4 is used for assessment, and top twenty high ORE jobs are identified. The results are also verified and validated using the Friedman test, and RSM is found to be a very efficient way of analyzing the data.