Radiological Dose Analysis to the Public Resulting from the Operation of Daedeok Nuclear Facilities

2014 ◽  
Vol 39 (1) ◽  
pp. 38-45
Author(s):  
Hae Sun Jeong ◽  
Eun Han Kim ◽  
Hyo Joon Jeong ◽  
Moon Hee Han ◽  
Mi Sun Park ◽  
...  
Keyword(s):  
Nuclear Facilities ◽  
The Public ◽  
Radiological Dose

Decontamination and Provenance Tracking

2003 ◽  
Author(s):  
David Bradbury ◽  
George R. Elder ◽  
John C. Ritchie ◽  
Robert G. Ward
Keyword(s):  
Electricity Generation ◽  
Nuclear Power ◽  
Nuclear Industry ◽  
Public Confidence ◽  
Nuclear Facilities ◽  
The Public ◽  
Nuclear Plants ◽  
Potential Benefits ◽  
Continued Use ◽  
Contamination Levels

Decommissioning of retired nuclear plants and facilities demands the proper management of the process, both for economic reasons and for retaining public confidence in the continued use of nuclear power for electricity generation. There are significant potential benefits, both economic and environmental, in recycling materials from retired nuclear facilities for new uses rather than disposing of them as radioactive waste. Although it is technically possible to decontaminate many retired nuclear components to reduce contamination levels to below those appropriate for free release into the public domain, there is some public unease at the prospect of formerly contaminated materials passing into unrestricted public use. Greater support for recycle can be achieved by converting decontaminated materials into products for new controlled uses, particularly within the nuclear industry. Irrespective of the future of nuclear power, the industry has a need for many new items such as waste containers, replacement components etc. Good economics can be achieved by decontaminating the materials and then using existing non-radioactive manufacturing facilities for fabrication of new components. Provided that materials have first been decontaminated to below unrestricted release levels, there is no objection in principle to using non-radioactive facilities for recycling and manufacturing activities, so long as the materials are properly tracked to prevent their uncontrolled release. Surface decontamination has an important role to play in these activities. Efficient and economic decontamination processes are needed to prepare materials for recycle. The EPRI DFDX Process is a process for achieving these objectives. Recent progress with this process is described.

Development of Safety Assessment Code for Decommissioning of Nuclear Facilities (DecDose)

2009 ◽  
Author(s):  
Taro Shimada ◽  
Soichiro Ohshima ◽  
Takenori Sukegawa
Keyword(s):  
Dose Rate ◽  
Safety Assessment ◽  
Ventilation System ◽  
Cutting Speed ◽  
Liquid Waste ◽  
Atomic Energy ◽  
Internal Dose ◽  
Nuclear Facilities ◽  
The Public ◽  
External Dose

A safety assessment code, DecDose, for decommissioning of nuclear facilities has been developed, based on the experiences of the decommissioning project of Japan Power Demonstration Reactor (JPDR) at Japan Atomic Energy Research Institute (now Japan Atomic Energy Agency). DecDose evaluates the annual exposure dose of the public and workers according to the progress of decommissioning of the plant, and also evaluates the public dose at accidental situations including fire and explosion. The public dose at normal situations during decommissioning is evaluated from the amount of radionuclides discharged from the plant to the atmosphere and the ocean. The amounts of radionuclides discharged depend on which and how activated and/or contaminated components and structures are dismantled. The amount is predicted by using the radioactive inventory given by the plant. The filtration efficiency of the ventilation system and decontamination factors of the liquid waste treatment system of the plant are also considered. Both of the internal dose caused by inhalation and ingestion of agricultural crops and seafood, and the external dose by radioactive aerosols airborne and radioactive deposition at soil surfaces are calculated for all of possible pathways. Also included in the external dose are direct radiation and skyshine radiation from waste containers which are packed and temporarily stored in the in-site building. For external dose of workers, the radiation dose rate from dismantling contaminated components and structures is calculated using the dose rate library which was previously evaluated by a point kernel shielding code. In this condition, radiation sources are regarded to be consisted of two parts; one is a dismantling object of interest, and the other is the sum of surrounding objects. Difference in job type or position is taken into account; workers for cutting are situated closer to a dismantling component, other workers help them at some distance, and the supervisor watches their activities from away. For worker’s internal dose, the radionuclide concentrations in air for individual radionuclides are calculated from a dismantling condition, e.g. cutting speed, cutting length of the dismantling component and exhaust velocity. A calculation model for working time on dismantling was developed using more segmented WBS (work breakdown structure). DecDose was partially verified by comparison with measured the external dose of workers during JPDR Decommissioning Project. The DecDose is expected to contribute to utilities in formulating rational dismantling plans and to the safety authority in estimating conservativeness in safety assessment of licensing application or risk-based regulatory criteria.

scholarly journals Historic Perspective on the Conversations to Restart the Kashiwazaki-Kariwa Nuclear Power Plant

2021 ◽  
Vol 10 (29) ◽  
pp. 147-172
Author(s):  
Andrea Carolina Ávalos Salgado ◽  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Energy ◽  
Local Community ◽  
Nuclear Facilities ◽  
The Public ◽  
Before And After ◽  
The Government

Following the accident of Fukushima in 2011, nuclear facilities in Japan were shut down, and a new evaluation and restart process was developed. Despite the public safety concerns, the current administration expects nuclear energy to become a pillar for economic recovery in the coming years. This paper compares the historic context of restarting Kashiwazaki-Kariwa Nuclear Power Plant before and after Fukushima. The evolution is analyzed through a series of interviews in 2012 and 2013 in the community and with government officers, as well as a close follow-up of the official statements by TEPCO and the government agencies up until the end of 2020. It tackles the development in the relation between TEPCO, local authorities, and local community of this nuclear plant, before and after Fukushima. This historic relation has shown to be the key element in the restart process, even above the legal process.

Realistic retrospective dose assessments to members of the public around Spanish nuclear facilities

2011 ◽  
Vol 102 (11) ◽  
pp. 995-1007 ◽  
Author(s):  
M.A. Jiménez ◽  
J.M. Martín-Valdepeñas ◽  
M. García-Talavera ◽  
J.L. Martín-Matarranz ◽  
M.R. Salas ◽  
...  
Keyword(s):  
Nuclear Facilities ◽  
The Public ◽  
Dose Assessments

scholarly journals Deposition velocities of some natural radionuclides from the atmosphere at Ninh Thuan and Dong Nai of Vietnam

2021 ◽  
Vol 10 (1) ◽  
pp. 31-39
Author(s):  
Phu Nguyen Van ◽  
Sieu Le Nhu ◽  
Khoa Tran Dinh ◽  
Tung Nguyen Dinh ◽  
Nga Nguyen Thi Thanh ◽  
...  
Keyword(s):  
Natural Radionuclides ◽  
Deposition Velocity ◽  
Specific Radioactivity ◽  
Gamma Spectrometer ◽  
Transport Parameters ◽  
Nuclear Facilities ◽  
The Public ◽  
Deposition Velocities ◽  
Deposition Density ◽  
The World

The deposition velocities of Be-7, K-40, Th-232, U-238 and Pb-210 radionuclides from the atmosphere at Ninh Thuan and Dong Nai monitoring stations of Vietnam were investigated. The deposition velocity was calculated based on it’s specific radioactivity in aerosols and deposition density in fallout samples. The data of the deposition velocities of radionuclides from the atmosphere are needed as input data for the models to simulate atmospheric radioactive dispersion and assess the public dose around nuclear facilities. The radioactivity of Be-7, K-40, Th-232, U-238 and Pb-210 nuclides in aerosols and fallout samples were analyzed by using a low level background gamma spectrometer equipped with HPGe detector of high resolution. The results show that the deposition velocities of Be-7, K-40, Th-232, U-238 and Pb-210 nuclides from the air are in ranges of 0.04÷1.71; 1.84÷27.46; 1.46÷23.63; 0.80÷26.13 and 0.06÷1.53 (cm/s), with average values of 0.55; 13.81; 8.22; 8.12 and 0.58 (cm/s), respectively. The deposition velocities of the radionuclides in the survey areas are comparable with those found in tropical and subtropical regions and these results could be served as the database of the World radioactive transport parameters.

scholarly journals Termination of the nuclear and radiation legacy of Russia: scientific basis for the radiation-hygienic regulation

2019 ◽  
Vol 12 (3) ◽  
pp. 114-119
Author(s):  
I. K. Romanovich
Keyword(s):  
Social Protection ◽  
Radiation Safety ◽  
Natural Radionuclides ◽  
Scientific Basis ◽  
Federal Law ◽  
Nuclear Facilities ◽  
The Public ◽  
The Past ◽  
The Social ◽  
Zone Of Influence

For the provision of the radiation safety of the public during the termination of the nuclear and radiation legacy within the boundaries of the Federal Targeted Program “Provision of the nuclear and radiation safety for 2016-2020 and up to 2030”, the following documents were developed: draft of the sanitary rules “Hygienic requirements for the remediation of the facilities and territories contaminated by man-made and natural radionuclides due to the past activities of the facilities of nuclear and non-nuclear branches of industry” and three methodical guidelines on the survey of the remediated territories, buildings and structures and assessment of the doses of the public residing in the zone of influence of the nuclear legacy facilities. The sanitary rules were based on the directions of the future use of the remediated territories, buildings and structures as well as on the radiation-hygienic safety criteria. It was assumed that dose criteria for the public considering the quota (0.3 mSv/year) is applied for remediated sites of the nuclear facilities (radiation facilities). The remediation of the radioactively contaminated areas with the residing public is based on the requirements of the Federal Law № 1244-1, 15.05.1991 “On the social protection of the citizens exposed due to the Chernobyl NPP accident”. Originally the drafts of documents were developed considering the approval in 2019 of the new Norms of the Radiation Safety – 2019, harmonized with the international recommendations and standards. Due to prolongation of the existing Norms of the Radiation Safety 99//2009 for the extra five years, the drafts of the regulations are adapted to the existing NRB 99/2009 and OSPORB 99/2010.

In Situ Measurement Technique of Low-Energy β-Contaminated Waste Sorting

2018 ◽  
Author(s):  
Yue Weihong ◽  
Xu Yeqiang
Keyword(s):  
Radioactive Waste ◽  
Waste Disposal ◽  
Measurement Techniques ◽  
Radioactive Waste Disposal ◽  
Solid Waste Disposal ◽  
Nuclear Facilities ◽  
The Public ◽  
Novel Technique ◽  
Contaminated Waste

Operation and decommissioning of nuclear facilities will produce radioactive waste, and different radionuclides in the waste will bring different hazards to the public and the environment. The waste would be sorted more reasonably by distinguishing different radionuclides. Yet it is still very difficult to measure directly the pure Beta radioactive waste in situ, though in situ Gamma-analytical and Alpha-waste-barrel measurement techniques have become more sophisticated. The aim is to propose a scientific technique to sort the radioactive waste in situ. This study focused on the 90Sr-contaminated material in China Institute of Atomic Energy and optimized the design of the existing solid waste disposal facilities. A novel technique to measure the radioactive waste 90Sr-90Y online was proposed, trying to sort the radioactive waste as optimally as possible to realize further separation of exemption waste. Theoretically, the exemption waste can be further sorted, and it can guide the design of radioactive waste disposal system.

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