In this study, non-destructive technologies that can be applied to evaluate the integrity of valve materials, safety against internal pressure caused by corrosion, and the blocking function of large-diameter water valves during operation without requiring specimen collection or manpower entering the inside of the valve were tested to assess the reliability of the technologies and their suitability for field application. The results showed that the condition of the graphite structure inside the valve body can be evaluated directly through the optical microscope in the field without specimen collection for large-diameter water butterfly valves, and the depth of corrosion inside the valve body can be determined by array ultrasound and the tensile strength can be measured by instrumented indentation test. The reliability of each of these non-destructive techniques is high, and they can be widely used to evaluate the condition of steel or cast iron pipes that are significantly smaller in thickness than valves. Evaluation of blocking function of the valves with mixed gas showed that it can be detected even when a very low flow rate of mixed gas passes through the disk along with the water flow. Finally, as a result of evaluating the field applicability of non-destructive technologies for three old butterfly valves installed in the US industrial water pipeline, it was found that it is possible to check the material and determine the suitability of large-diameter water valves without taking samples, and to determine the corrosion state and mechanical strength. In addition, it was possible to evaluate safety through the measurement results, and it is judged that the evaluation of the blocking function using mixed gas will help strengthen preventive response in the event of an accident.

In this study, the physical properties and fracture characteristics according to the tensile load are evaluated on the materials of the polymeric filler and carbon fiber-based composite sleeve technique. The polymeric filler and the composite sleeve technique are applied to areas where the pipe body thickness is reduced due to corrosion in large-diameter water pipes. First, the tensile strength of the polymeric filler was 161.48~240.43 kgf/cm2, and the tensile strength of the polyurea polymeric filler was relatively higher than that of the epoxy. However, the tensile strength of the polymeric filler is relatively very low compared to ductile cast iron pipes(4,300 kgf/cm2<) or steel pipes(4,100 kgf/cm2). Second, the tensile strength of glass fiber, which is mainly used in composite sleeves, is 3,887.0 kgf/cm2, and that of carbon fiber is up to 5,922.5 kgf/cm2. The tensile strengths of glass and carbon fiber are higher than ductile cast iron pipe or steel pipe. Third, when reinforcing the hemispherical simulated corrosion shape of the ductile cast iron pipe and the steel pipe with a polymeric filler, there was an effect of increasing the ultimate tensile load by 1.04 to 1.06 times, but the ultimate load was 37.7 to 53.7% compared to the ductile cast iron or steel specimen without corrosion damage. It was found that the effect on the reinforcement of the corrosion damaged part was insignificant. Fourth, the composite sleeve using carbon fiber showed an ultimate load of 1.10(0.61T, 1,821.0 kgf) and 1.02(0.60T, 2,290.7 kgf) times higher than the ductile cast iron pipe(1,657.83 kgf) and steel pipe(2,236.8 kgf), respectively. When using a composite sleeve such as fiber, the corrosion damage part of large-diameter water pipes can be reinforced with same level as the original pipe, and the supply stability can be secured through accident prevention.

A total of 100 commercially available olive oil products were analyzed for 179 pesticide residues using gas chromatography-tandem mass spectrometry (GC/MS/MS). The olive oil samples were mixed with organic solvents, centrifuged and frozen to remove fat, and pesticide residues were analyzed using the “quick, easy, cheap, effective, rugged, and safe” (QuEChERS) method. The determination coefficient (R2) of the analysis method used in this study was ≥0.998. The detection limit of the method ranged 0.004–0.006 mg/kg and its quantitative limit ranged 0.012–0.017 mg/kg. The recovery rate (n=5) measured at the level ranging 0.01–0.02, 0.1, and 0.5 mg/kg ranged 66.8– 119.5%. The relative standard deviation (RSD) was determined to be ≤5.7%, confirming that this method was suitable for the "Guidelines for Standard Procedures for Preparing Food Test Methods". The results showed that a total of 151 pesticides (including difenoconazole, deltamethrin, oxyfluorfen, kresoxim-methyl, phosmet, pyrimethanil, tebuconazole, and trifloxystrobin) were detected in 64 of the 100 olive oil products. The detection range of these pesticide residues was 0.01–0.30 mg/kg. The percentage acceptable daily intake (%ADI) of the pesticides calculated using ADI and estimated daily intake (EDI) was 0.0001–0.1346, indicating that the detected pesticides were present at safe levels. This study provides basic data for securing the safety of olive oil products by monitoring pesticide residues in commercially available oilve oil products. Collectively, the analysis method used in this study can be used as a method to analyze residual pesticides in edible oils.

PURPOSES : This study establishes a methodology for evaluating traffic safety in response to the introduction of one-way traffic using surrogate safety measures and analyzes the impact of one-way traffic safety through a case analysis. METHODS : The SSAM(Surrogate Safety Assessment Measure) was used to analyze traffic conflicts (TTC(Time to Collision) and PET(Post Encroachment Time)), which are safety indicators. The SSAM input variable dataset was constructed using a VISSIM(Verkehr In Städten - SIMulationsmodell) simulation. RESULTS : Introducing one-way traffic rather than the pending issue (two-way operation) improved traffic safety as the possibility of TTC or PET was reduced. In addition, the analysis results showed that the average TTC time and average PET time increased with the introduction of the one-way system. It is anticipated that the avoidance action time taken by the driver to avoid dangerous situations will also increase, which will help improve traffic safety. CONCLUSIONS : As an alternative to solving traffic safety and communication problems occurring at the study site, it was determined that a one-way system would be effective. Furthermore, a one-way system that allows two-lane roads on both sides to move one-way and allows parking in pockets on both sides of the road would be appropriate.

APro, developed in KAERI for the process-based total system performance assessment (TSPA) of deep geological disposal systems, performs finite element method (FEM)-based multiphysics analysis. In the FEM-based analysis, the mesh element quality influences the numerical solution accuracy, memory requirement, and computation time. Therefore, an appropriate mesh structure should be constructed before the mesh stability analysis to achieve an accurate and efficient process-based TSPA. A generic reference case of DECOVALEX-2023 Task F, which has been proposed for simulating stationary groundwater flow and time-dependent conservative transport of two tracers, was used in this study for mesh stability analysis. The relative differences in tracer concentration varying mesh structures were determined by comparing with the results for the finest mesh structure. For calculation efficiency, the memory requirements and computation time were compared. Based on the mesh stability analysis, an approach based on adaptive mesh refinement was developed to resolve the error in the early stage of the simulation time-period. It was observed that the relative difference in the tracer concentration significantly decreased with high calculation efficiency.

Compared to operational wastes, nuclear power plant (NPP) decommissioning wastes are generated in larger quantities within a short time and include diverse types with a wider range of radiation characteristics. Currently used 200 L drums and IP-2 type transport containers are inefficient and restrictive in packaging and transporting decommissioning wastes. Therefore, new packaging and transport containers with greater size, loading weight, and shielding performance have been developed. When transporting radioactive materials, radiological safety should be assessed by reflecting parameters such as the type and quantity of the package, transport route, and transport environment. Thus far, safety evaluations of radioactive waste transport have mainly targeted operational wastes, that have less radioactivity and a smaller amount per transport than decommissioning wastes. Therefore, in this study, the possible radiation effects during the transport from NPP to disposal facilities were evaluated to reflect the characteristics of the newly developed containers and decommissioning wastes. According to the evaluation results, the exposure dose to transport workers, handling workers, and the public was lower than the domestic regulatory limit. In addition, all exposure dose results were confirmed, through sensitivity analysis, to satisfy the evaluation criteria even under circumstances when radioactive materials were released 100% from the container.

At present, the assessment for the crew training using the ship handling simulator is completed by the assessor, which is subjective and difficult to unify the assessment criteria. Under this assessment mode, the assessor will have a great work intensity. So it is necessary to design and develop the automatic assessment system for the ship handling simulator. This paper introduces the automatic assessment system developed by Dalian Maritime University (shorted for DMU), which includes the assessment method, system architecture and implementation. A selected example of applications is described.

국제유가가 배럴당 85달러에서 하반기에는 최대 100달러까지 오를 것으로 예상하여 세계 시장에서 해양플랜트 발주가 늘어 날 가능성이 크다. 해양플랜트의 주요 특징 중 한 가지는 탑사이드에 대형 헬리데크가 위치하며 경량화 및 내부식성을 위하여 알루미 늄 합금을 구조의 기본 재료로 사용하고 있다. 선주사는 긴급 상황 발생 시 신속한 인명 대피를 위하여 헬리콥터 크기를 대형화하는 추세이고, 헬리콥터를 데크에 안정적으로 고박할 수 있는 장치의 안전사용하중도 증가가 필요하다. 알루미늄 재질의 특성상 용접에 의 한 구조 강도 저하가 크기 때문에, 고정 장치는 데크에 매립하여 볼트로 고정하는 방식으로 설계가 필요하다. 본 연구에서는 대형 헬 리데크(직경=28m)에 사용이 가능한 헬리콥터 고정 장치를 개발하기 위하여 알루미늄 합금 6082-T6를 적용한 모델을 개발하였다. 개발 된 고정 장치는 실제 고박에 사용하는 하중 조건을 만족하도록 비선형구조 강도 계산을 통하여 검증하였다. 45도 경사각을 갖는 하중 조건은 국부적인 소성 붕괴로 인하여 90도 조건에 비해 낮은 최종강도를 나타냈다. 최종 모델에 대한 비선형 구조 붕괴 거동은 강도 실험과 경향이 유사하게 나타났다. 본 연구에서 도출한 주요 내용은 유사 알루미늄 기자재의 구조 강도 검토 시 참고 문헌이 될 것으 로 판단된다.

본 연구는 국내 희귀 및 멸종위기야생식물 Ⅱ급인 초령목의 자생지에서의 분포와 생육 특성을 파악하고 보전지위를 평가하 고자 실시하였다. 초령목은 흑산도와 제주도에서 자생지가 확인되었는데, 4개의 개체군으로 구분되었다. 자생지에서 314개체 가 확인되었으며, 이중 약 45.9%(144개체)가 해발고도 401m~500m 범위에 분포하였다. 수고는 평균 2.7(±4.8)m였으며, 흉고직경은 12.6(±13.9)㎝였고 분지는 평균 1.0(±0.5)개로 나타났다. 초령목의 어린나무 개체들은 어미목에서 반경 30m 이내에 54.3%가 분포하였고, 31m~40m 사이에서 25.8%가 분포하였으며, 반경 60m 이내에 대부분(90.1%)이 확인되었다. 초령목의 어린나무 개체들이 일부 성숙목 주변에서도 확인되지 않고, 극히 한정된 지역에서만 출현하는 것은 자생지 환경뿐만 아니라 생육조건과 관계가 있는 것으로 판단된다. 초령목의 종자 산포는 천연하종과 더불어 조류가 관여하는 것으로 추정되는 데, 이는 천연하종의 범위 이상에서 발견되는 자생지는 조류가 쉴 수 있는 물웅덩이가 근처에 존재하는 공통적인 특징을 지녔기 때문이다. 초령목의 지역 및 국가수준의 IUCN 적색목록 평가기준의 범주는 위급(Critically Endangered) 범주에 해당하며 국내 개체군은 “CR B2ab(ⅴ); C2a(ⅰ); D” 범주로 평가되는 것으로 나타났다.

본 연구에서는 울산지역에서 유통되는 로컬푸드 농산물 367건에 대해 다성분 분석법을 이용하여 잔류농약 350종 을 분석한 결과 다음과 같다. 로컬푸드 농산물에 대한 잔류농약 분석 결과 21.5%(79 건)의 검출률을 보였으며 부적합률은 1.1%(4건)으로 나타 났다. 품목별로 과일류는 65건 중 27건(41.5%), 채소류는 242건 중 50건(20.7%), 두류는 7건 중 1건(14.3%), 곡류 11건 중 1건(9.1%) 검출률을 보였고, 취나물, 곤달비, 파, 살구에서 기준치 이상의 잔류농약이 검출되었다. 검출된 잔류농약은 총 58종 163회로 살충제 성분이 가 장 많이 검출되었고 고독성 농약 1회, 보통 독성 농약 9 회, 저독성 농약이 48종이었다. 부적합 처리된 품목을 포함한 검출된 잔류농약 항목에 대한 위해도 평가 결과 위해지수(%ADI) 가 0.0000- 63.1043% 으로 모두 100% 미만으로 위해하지 않은 수준 으로 판단되었다. 지속적으로 로컬푸드 농산물의 운동 추진 방향인 지역 활성화와 안전한 먹거리 공급체계구축의 목적을 위해 엄 격히 관리되는 기준으로 안전성 검사를 실시하고, 신뢰성 확보를 위한 생산자 교육 및 홍보, 출하 전 안전성 검사 관리시스템이 정착된다면 울산지역 로컬푸드 농산물 사업 이 더욱 활성화되고 지속적으로 추진 될 수 있을 것으로 판단된다.

미세플라스틱 입자는 환경 내 어디에나 존재하며 크기, 모양 또는 유형의 표준화된 입자가 아 니다. 따라서 독성자료를 바탕으로 해수, 퇴적물 등 해양환경의 다차원을 정확하게 평가하고 관리하는 위험평가 프레임워크를 구축하는 것은 매우 어렵다. 본 연구에서는 해양환경 미세플 라스틱의 특징과 영향을 조사하였고, 해양환경 미세플라스틱의 분포와 생물영향에 따른 위해 도 평가 프레임워크(초안)를 제안하고 있다. 환경 미세플라스틱의 특성은 매우 다양하지만 대 부분의 독성 데이터는 독특한 형태와 유형에 집중되어 있으며, 실험실 노출 생물과 관리해야 하는 생물 종도 다르다. 실제적으로, 지금까지의 수집된 연구결과는 위해성평가에 활용하기에 독성 데이터 품질에 있어 불확실성이 높기도 하며, 전통적인 위해성평가 프레임워크를 적용 하는 데 있어 고려할 부분이 많이 존재한다. 그러나, 현재 미세플라스틱 관리에 대한 국제사회 의 움직임이 점차 강화되고 있고, 해양환경의 미세플라스틱 오염도가 높아지고 있는 점을 고 려하면, 해양환경의 미세 플라스틱 특성에 기초한 위해성평가 기법 구축에 대한 추가 연구가 제안되어야 할 것이다.

도시 내 기후변화로 인한 이상 기상 현상과 함께 다양한 환경문제의 발생 빈도가 높아지고 있다. 도시의 회복력 향상을 위해서 자연기반해법이 대두되며, 이는 식물의 생육과 밀접한 관련이 있으므로 환경 스 트레스에 회복력이 강한 식물 소재가 요구되고 있다. 본 연구는 식물 소재 중 지피식물 47종을 대상으로 침수 내성을 평가하여 식재 및 관리를 위한 기초자료로 활용하고자 수행되었다. 시험 식물을 3일 및 7일 간 지제부까지 완전히 침수시킨 후 관행의 방법으로 관리하여 생육 변화를 4주간 관찰하였다. 식물의 외관 변화와 대조구와 처리구간의 S/R율(Shoot / Root ratio)차이에 따라 내침수성을 5개 집단으로 구분 하였다. Group A는 ‘곰취’등 28종의 식물로 외관 변화가 없으며, 침수에 의한 영향을 받지 않는다. Group B, C, D 및 E의 17종은 침수에 의한 외관 변화나 S/R율의 차이가 뚜렷이 확인되었다. 특히 ‘구절초’등 4종은 외관의 변화가 뚜렷하고 대조구와 처리구간 S/R율이 4배 수준이며(Group C), ‘눈개승마’는 지상 부가 완전히 고사하였다(Group E). 따라서 침수에 대응한 식재 계획에서는 Group A의 식물을 이용하는 것이 적합할 것으로 판단된다.

프로바이오틱스는 다양한 환경에서 분리되어 왔으며, Bacillus 균주는 유산균과 같은 일반적인 프로바이오틱스의 한계를 보완할 수 있는 내생포자 형성 능력으로 인해 프로바이오틱스 균주 중에서 유리하다. 본 연구의 목적은 한국에서 오염되지 않은 환경으로 알려진 울릉도 토양에서 분리된 Bacillus 균주의 프로바이오틱스 잠재성을 조사하는 것이다. 토양 시료는 울릉도 각지에 서 채취하였으며, 항생제 내성과 효소 활성을 평가하였다. 항생제에 내성을 나타내지 않는 6개 의 Bacillus 균주를 확보하였고 이후에 효소 활성을 검사하였다. 인체에 악영향을 미칠 수 있 는 β-glucuronidase 효소는 활성이 나타나지 않았으며, 시중에서 판매되고 있는 Bacillus 프로바 이오틱스와 유사한 효소의 활성과, 추가적으로 펩타이드 가수분해효소인 Leucine arylamidase 의 활성이 나타난 NB-1 균주가 확인되었다. 이에, 추가적인 효능 연구 및 안정성 실험을 통해 프로바이오틱스 균주로서의 가능성을 모색해야 할 필요가 있다고 판단된다.

목적 : 본 연구의 목적은 지역사회 거주 노인의 건강과 관련된 사회적 지지 연구에서 적용한 평가도구의 특성과 사회적 지지의 측면 및 하위요인의 분류 및 고찰을 통해 사회적 지지 평가도구들을 체계적으로 분석하여 제시하고자 한다. 연구방법 : 자료수집은 PubMed, Cumulative Index of Nursing and Allied Health Literature(CINAHL), 학술연구정보서비스(Research Information Sharing Service; RISS), 한국학술정보(Korean Studies Information Service System; KISS) 국내외 데이터베이스를 사용하여 2012년 1월부터 2022년 12월까지 게재된 논문을 대상으로 문헌을 검색하였다. 검색어는 “social support assessment”, OR “social support questionnaire”, OR “social support scale” AND “older adults” AND “community dwelling” AND “health”를 사용하였다. 결과 : 총 3,897편의 연구 중 최종적으로 24편의 문헌이 선정되었고, 선정된 문헌에서 14개의 사회적 지 지 평가도구가 포함되었다. 사회적 지지 개념적 측면에서 지각된 사회적 지지를 측정하는 도구는 총 14 개 중 8개(57%)가 포함되었다. 평가도구의 하위요인은 사회적 지지의 개념적 측면의 기능과 제공 및 수혜 형태의 복합적인 요인을 포함하는 것으로 나타났다. 결론 : 본 연구는 지역사회 거주 노인의 건강과 관련된 사회적 지지 평가도구의 특성, 측면 및 하위요인을 분류하 여 제시하였으며, 표준화된 사회적 지지 평가도구를 개발하는데 기초자료로 활용될 것으로 기대한다.

In this research, the dose rate was measured using a backpack-type scan survey device at 4 sites in sites around Nuclear Power Plants (Kori, Wolsong, Hanbit, Hanul), and the radioactivity ratio for each nuclide was evaluated using an high-purity germanium (HPGe) detector. Kori, Wolsong and Hanul power plants were measured within 2 km of the power plant, and Hanbit power plants were measured about 6.7 km from the power plant. As a result of measuring the dose rate with a backpacktype scan survey device, the average dose rate was the lowest in the measurement site 1 at 0.090 μSv/h, and the highest in the measurement site 4 at 0.145 μSv/h. All measurement points showed the domestic environmental dose rate level. The data obtained by the scan survey was visualized using the classed post and gridding functions of the surfer program. As a result of measurement with the HPGe detector, 137Cs was not detected, and only natural nuclides were detected. Among the detected natural nuclides, the radioactivity ratio was the highest for 40K with an average of 94.56%, and the lowest for 214Pb with an average of 0.26%. The results of this research can be used as basic data for radiation environment surveys around nuclear power plants. Further studies are needed to evaluate the radiation impacts by region and environment through periodic measurements.

The US NRC developed a program called NRCDose3 to evaluates the environmental impact of radiation around nuclear facilities. The NRCDose3 code is a software suite that integrates the functionality of three individual LADTAP II, GASPAR II, and XOQDOQ Fortran codes that were developed by the NRC in the 1980’s and have been in use by the nuclear industry and the NRC staff for assessments of liquid effluent and gaseous effluent, and meteorological transport and dispersion, respectively. Through the integrated program, it is possible to conduct safety assessment and environmental impact assessment from liquid and gaseous effluent when operating permits are granted. In addition to a more user-friendly graphic user interface (GUI) for inputting data, significant changes have been made to the data management and operation to support expanded capabilities. The basic calculation methods of the LADTAP II, GASPAR II, and XOQDOQ have not been changed with this update to the NRCDose3 code. Several features have been added. The previous program used only ICRP-2 dose conversion factor, but the new program can additionally use dose conversion factor of ICRP-30 and ICRP-72. In the previous program, 4 age groups (infant, child, teen, and adult) were evaluated during dose evaluation, but when ICRP-72 was selected, 6 age groups (infant, 1-year, 5-year, 10-year, 15-year, and adult) could be evaluated. In addition, when selecting ICRP-72, many user-modifiable parameters such as food intake and exposure time were added. It will be referred to E-DOSE60, a program currently under development.

After the Fukushima nuclear power plant accident in 2011, interest in technology for evaluating residents’ exposure to effluents generated from nuclear power plants at the time of the accident has increased. KHNP has developed the S-REDAP program and is using it to evaluate radiation dose and recommend resident protection measures in the event of a nuclear power plant emergency. Its main functions are source term evaluation, atmospheric diffusion evaluation, radiation dose evaluation, etc. Based on these evaluations, resident protection measures are evaluated. In Japan, evaluation is conducted through a program called SPEEDI-MP (System for Prediction of Environmental Emergency Dose Information Multi-model Package) created by JAEA (Japan Atomic Energy Agency). Similar to S-REDAP, the program also evaluates effluents emitted from nuclear facilities through source term evaluation and atmospheric diffusion factor evaluation. In JAEA, through a program using SPEEDI-MP, the source term evaluation was performed in collaboration with NSC (Nuclear Safety Commission) in the event of the Fukushima nuclear plant accident, and dose evaluation in Japan was performed 2 months as an atmospheric diffusion factor using meteorological data for 2 days. Through comparative analysis of evaluation data from Japan, improvements to the current program be derived.

K-DOSE60, a off-site dose calculation program currently used by khnp, is performing evaluation based on the gaseous effluent evaluation methodology of NRC Reg. Guide 1.109. In particular, H-3 and C-14, which are the major nuclides of gaseous effluent, are evaluated using a ratio activity model. Among them, H-3 is additionally evaluating the dose to OBT (Organically Bound Tritium) and HT as well as HTO (Triated water). However, NRC Reg. Guide 1.109 is a methodology developed in the 1970s, and verification was performed by applying the evaluation methodology of H-3 and C-13 presented by IAEA TRS-472 in 2010 to the current K-DOSE60. The IAEA TRS-472 methodology also includes OBT and HT for H-3. In order to apply the ratio radioactivity model presented in IAEA TRS-472, the absolute and relative humidity were calculated using the weather tower of the nuclear site and used for H-3 evaluation. For the dose evaluation of HT, the previously used Canada Chalk River Lab. (CNL) conversion factor was used. For atmospheric carbon concentration, the carbon concentration presented in IAEA TRS-472 was used, not the carbon concentration in the 1970s of NRC Reg. Guide 1.109. It was confirmed that the K-DOSE60, which applied the changed input data and methodology, was satisfied by performing comparative verification with the numerical calculation value.

In 2022 and 2023, the Korea Institute of Nuclear Safety (KINS), a regulatory body, revised the regulatory guidelines for off-site dose evaluation to residents, marine characteristics surveys around nuclear facilities, and environmental radiation surveys and evaluation around nuclear facilities. In addition, the NRC, a US regulatory body, has revised regulatory guide 1.21 (MEASURING, EVALUATING, AND REPORTING RADIOACTIVE MATERIAL IN LIQUID AND GASEOUS EFFLUENTS AND SOLID WASTE) to change environmental programs for nuclear facilities. The domestic regulatory guidelines were revised and added to reflect the experience of site dose evaluation for multiple units during the operation license review of nuclear facilities, the resident exposure dose age group was modified to conform to ICRP-72, and the environmental monitoring plan was clarified. In the case of the US, the recommended guidelines for updating the long-term average atmospheric diffusion factor and deposition factor, the clarification of the I-131 environmental monitoring guidelines for drinking water, and the clarification of the procedures described in the technical guidelines when changing environmental programs have been revised and added. Through such regulatory trend review, it is necessary to preemptively respond to changes in the regulatory environment in the future.

Radioactive materials depositied after nuclear accident or radiological emergency result in radiation exposure to individuals living in long-term contaminated territories. Therefore, the remedial actions should be taken on affected areas for the evacuated residents to return to their homes and normal lifestyle. Meanwhile, radiation exposure occurs through various pathways by work types during the site clean-up. Therefore, dose assessment is crucial to protect emergency workers and helpers from the potential radiological risk. This study estimated the exposure dose to individuals decontaminating the areas contaminated with 60Co, 63Ni, 90Sr, 134Cs, 137Cs, and then calculated the maximum workable soil concentration to comply with the reference level of 20 mSv/y for transition to existing exposure situations. For the realistic assessment, the detailed exposure scenarios depending on the types of work (excavation, collection, transportation, disposal, landfill), and the relevant exposure pathways were used. In addition, with the LHS (Latin Hypercube Sampling) - PRCC (Partial Rank Correlation Coefficient) method, sensitivity analysis was performed to identify the influence of the input parameters and their variation on the model outcomes. As a result, the most severe exposure-induced type was identified as the excavator operation with an annual individual dose of 4.75E-01 mSv at the unit soil concentration (1 Bq/g), from which the derived maximum workable soil concentration was 4.21E+01 Bq/g. Dose contribution by isotopes were found to be 60Co (55.63%), 134Cs (32.01%), and 137Cs (12.28%), and the impact of 63Ni and 90Sr were found to be negligible. Dose contribution by exposure pathways decreased in the following order: ground-shine, soil ingestion, dust inhalation, and skin contamination. Furthermore, the most high sensitive input parameters and their PRCC were found to be as the dilution factor (0.75) and as the exposure time (0.63). In conclusion, the results are expected to contribute to optimize radiation protection strategeis for recovery workers and to establish appropriate response procedures to be applicable in areas with high deposition density after a radiological or nuclear emergency.