[논문]해체사업의 최종현황조사를 위한 MARSSIM 적용

홍상범; 이기원; 박진호; 정운수

doi:10.7733/jkrws.2011.9.2.107

초록
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해체의 최종단계는 대상 부지 및 건물을 규제로부터 제외하는 것이다. MARSSIM은 부지를 개방하기 위한 최종현황조사를 수행함에 있어 요구되는 자료의 수집 등의 다양한 요건을 만족키기 위한 총괄적인 지침을 제공한다. 연구로 해체 후 부지 및 건물의 최종현황조사를 위해 MARSSIM에서 제시하고 있는 방법을 적용하였다. 연구로 부지의 특성을 반영한 개방기준을 도출하기 위해 RESRAD 및 RESRAD-Build 전산코드를 이용하여 부지 및 건물에 대해서 계산하였다. 부지 및 건물의 조사설계(Survey Design)를 위해서 잠재적 오염도 및 측정 결과를 활용하여 조사구역을 구분하였고, 개략조사 및 특성조사를 통해 수집된 다양한 결과에 기초하여 통계학적 검사를 통해 조사구역 별로 요구되는 시료의 수를 산정하게 된다. 측정된 결과에 기초하여 연구로 최종 개방기준에 만족하는 것으로 평가되었다.

Abstract ▼ AI-Helper

The release of a site and building from regulatory control is the final stage of the decommissioning process. The MARSSIM (Multi-Agency Radiation Survey and Site Investigation Manual) provides overall framework for conducting data collection for a final status survey to demonstrate compliance with s...

The release of a site and building from regulatory control is the final stage of the decommissioning process. The MARSSIM (Multi-Agency Radiation Survey and Site Investigation Manual) provides overall framework for conducting data collection for a final status survey to demonstrate compliance with site closure requirements. The KAERI carried out establishing a final status survey by using the guidance provided in the MARSSIM for of a site and building of the Korea Research Reactor. The release criteria for a site and building were set up based on these results of the site specific release levels which were calculated by using RESRAD and RESRAD-Build codes. The survey design for a site and building was classified by using the survey dataset and potential contamination. The number of samples in each survey unit was calculated by through a statistical test using the collected data from a scoping and characterization survey. The results of the final status survey were satisfied the release criteria based on an evaluation of the measured data.

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문제 정의

The objective of the assessment of the residual radioactivities is to demonstrate a satisfactory residual contamination level in accordance with the established release criteria. Therefore, one of the most important aspects of the final status survey planning was a clear understanding of the criteria will be applied to a particular decommissioning project.
The purpose of the final status survey was to demonstrate that the residual radioactivity in each survey unit would satisfy the release criteria. The final radiological conditions of a site and building must satisfy the DCGL.

가설 설정

and offices wer얀 classified as Class 3. Most of the rooms smaller than limitation size (100 to 1,000 m2) of the Class 2 strictures could be dMded one survey unit. Survey design of the laboratory 아in the Figure 4.
. Class 3 : Contamination levels of the outside area and building exteriors are expected to be quite similar to the background. While contaminations are identified, their levels are a small fraction of the DCGLw.

제안 방법

Therefore, one of the most important aspects of the final status survey planning was a clear understanding of the criteria will be applied to a particular decommissioning project. A dose modeling and setting of the release criteria was performed to evaluate the future radiological impacts on the individuals at the site or surrounding area, and to assure a compliance with regulatory cleanup requirements. The release dose criteria recommended by the IAEA are between the dose constraint (300 μSv/y; a portion of dose limit) and a trivial dose range (~10 μSv/y)[2, 3].
185 [9]. Because the actual scan MDC was larger than required scan MDC for the Class 1 area of the KRR site, it was necessary to calculate a new area factor that corree>onds to the actual scan MDC by ming a RESRAD code (1.43 = 50 m2). The new sample size was determined by dividing the area into the survey unit.
The main contaminants at a site and buildings were 60Co and 137CS but all the detected radionuclides in decommissioning waste were considered during the final status survey[l]. For the surface soil and buildings, dose rate s were measured with survey meters connected with a GPS(Global Positioning System) during the scoping and characterization survey, and the measured data were used for detecting the existence of hot spots and predicting the soil and building contamination levels. The results of the dose rates in the site are given in Figure 1.
procedure. The survey design for the final status survey of the KRR site and buildings was carried out. A site and buildings were classified into Class 1, Class 2, and Class 3 based on the potential contamination by using the measured and calculated results.

이론/모형

In this study, plan for the final status survey and release criteria for a site release were established by applying the MARSSIM procedure. The survey design for the final status survey of the KRR site and buildings was carried out.

성능/효과

The final status of the contamination level of the site was less than 0.02 Bq/g and 0.03 Bq/g of 60Co and 137CS, respectively. The total amount of the removed waste during remedial action was about 16m3, which was temporally stored in the reactor building.

참고문헌 (9)

S. B. Hong and J. H. Park, Waste Management in Decommissioning Projects at KAERI, Proceeding of the 6th Korea-China Joint Workshop on Nuclear Waste Management, Korean Radioactive Waste Society, ISSN 1738-1924, pp.290-299 (2005).
OECD/NEA, Radioactive Waste Management Committee The release of site of nuclear instillations, a status report, NEA/RWM/WPDD (2006).
International Atomic Energy Agency, Release of Sites from Regulatory Control on Termination of Practices, IAEA Safety Guide No. WS-G-5.1, IAEA, Vienna (2006).
Argonne National Laboratory; User's Manual for RESRAD version 6.0, Environmental Assessment Division (2001).
Argonne National Laboratory; User's manual for RESRAD-BUILD version 3, Environmental Assessment Division (2003).
J. H. Cheong, A Mathematical Model to evaluate the Radiological Risks for the Reuse of Decommissioning Site, J. of the Korean Radioactive Waste Society, Vol. 4(4), pp.353-365 (2006).
U.S. NRC, EPA, DOE; MARSSIM, Multiagency Radiation Survey and Site Investigation Manual, NUREG-1575, Rev1, EPA 402-R-97-016, Rev.1, DOE/EH-0624, Rev.1 (2000).
E. W. Abelquist: Decommissioning Health Physics: A Handbook for MARSSIM Users", Taylor & Francis Group, New York (2001).
E. W. Abelquist, W.S. Brown, G.E Powers and A.M. Huffert, Minimum detectable concentrations with typical radiation survey instruments for various contaminants and field conditions, NUREG-1507, US Nuclear Regulatory Commission, Washington, DC (1998).

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해체사업의 최종현황조사를 위한 MARSSIM 적용
Application of MARSSIM for Final Status Survey of the Decommissioning Project 원문보기

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해체사업의 최종현황조사를 위한 MARSSIM 적용 Application of MARSSIM for Final Status Survey of the Decommissioning Project 원문보기

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해체사업의 최종현황조사를 위한 MARSSIM 적용
Application of MARSSIM for Final Status Survey of the Decommissioning Project 원문보기

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