scholarly journals Procedure for Implementation of the Method of Artificial Deposition of Radioactive Substances from the Atmosphere

2019 ◽  
pp. 13-25 ◽  
Author(s):  
M. Kustov ◽  
E. Slepuzhnikov ◽  
V. Lipovoy ◽  
I. Khmyrov ◽  
Ilgar Firdovsi Dadashov ◽  
...  

Studies of the response to nuclear emergencies with the release of gaseous and dispersed radioactive substances into the atmosphere allowed us to develop a procedure for the practical implementation of this method. The emergency response method is aimed at depositing hazardous radioactive substances from the atmosphere that enter the atmosphere during man-made accidents at nuclear power plants and other facilities for the storage and processing of radioactive materials. The developed procedure with the proposed algorithm of actions operates within the framework of a unified state system of civil protection. The presented procedure allows solving three main tasks on the elimination of emergency consequences: monitoring of the affected area, taking effective management decisions and direct influence on the affected area. The basis for making effective management decisions is to predict the dynamics of radioactively contaminated areas, predict the intensity of precipitation with various methods of artificial deposition and predict the effectiveness of deposition effects on the dynamics of changes in contaminated areas. In order to expand the capabilities of available methods for predicting contaminated areas, their modification has been proposed taking into account deposition features. The use of this procedure allows minimizing the scale of major emergencies at regional and state levels. Due to the use of artificial deposition methods, as provided for in the procedure, there is the possibility of depositing dangerous radioactive substances from the atmosphere from a height of several kilometers, which cannot be implemented by other known methods. The developed algorithm of actions and the procedure for implementing the emergency response method by artificially initiated deposition are the basis for the development of a procedure for practical emergency rescue units during emergency response at regional and state levels. Thus, there is a reason to believe that the use of the proposed procedure will improve the efficiency of response to man-made emergency with the release of hazardous radioactive substances to the atmosphere.

2012 ◽  
Vol 30 (1) ◽  
pp. 44-63 ◽  
Author(s):  
Keiji Nagatani ◽  
Seiga Kiribayashi ◽  
Yoshito Okada ◽  
Kazuki Otake ◽  
Kazuya Yoshida ◽  
...  

2020 ◽  
pp. 9-23
Author(s):  
Yuri Obolonsky

In certain situations, conflicts in the organization are not only possible, but also desirable. Their role depends on how effectively they are managed. Managers, as subjects of conflict management, must determine the strategic line of behavior and program of action, as well as the tactics of influencing this complex object of management. This requires making effective management decisions, checking the results of their practical implementation, adjusting if necessary, promptly obtaining information about the effectiveness or ineffectiveness of the measures taken in order to find the optimal option for overcoming (resolving) the conflict.


Author(s):  
L. Sihver ◽  
N. Yasuda

In this paper, the causes and the radiological consequences of the explosion of the Chernobyl reactor occurred at 1:23 a.m. (local time) on Apr. 26, 1986, and of the Fukushima Daiichi nuclear disaster following the huge Tsunami caused by the Great East Japan earthquake at 2.46 p.m. (local time) on Mar. 11, 2011 are discussed. The need for better severe accident management (SAM), and severe accident management guidelines (SAMGs), are essential in order to increase the safety of the existing and future operating nuclear power plants (NPPs). In addition to that, stress tests should, on a regular basis, be performed to assess whether the NPPs can withstand the effects of natural disasters and man-made failures and actions. The differences in safety preparations at the Chernobyl and Fukushima Daiichi will therefore be presented, as well as recommendations concerning improvements of safety culture, decontamination, and disaster planning. The need for a high-level national emergency response system in case of nuclear accidents will be discussed. The emergency response system should include fast alarms, communication between nuclear power plants, nuclear power authorities and the public people, as well as well-prepared and well-established evacuation plans and evacuation zones. The experiences of disaster planning and the development of a new improved emergency response system in Japan will also be presented together with the training and education program, which have been established to ensure that professional rescue workers, including medical staff, fire fighters, and police, as well as the normal populations including patients, have sufficient knowledge about ionizing radiation and are informed about the meaning of radiation risks and safety.


2021 ◽  
Vol 1 ◽  
pp. 31-31
Author(s):  
Roman Winter ◽  
Bernd Flemisch ◽  
Holger Class ◽  
Rainer Merk

Abstract. When nuclear power plants are dismantled, only a small portion is heavily contaminated with radioactivity and must be stored in a repository. The remaining material, mainly concrete rubble (construction waste), is decontaminated if necessary and can be stored in conventional surface landfills after clearance. The focus of this work is on the modelling of such landfills and the radioactive substances during raining events. The influence of the heterogeneous nature of the construction rubble should also be investigated. The simulation environment DuMux, mainly developed by our institute, is used to compare different modelling approaches. It follows a previous work by Merk (2012). The research work is supported and accompanied by the Federal Office for Radiation Protection (BfS). Parts of the research initiatives of the BfS in the area of clearance of materials with negligible radioactivity are also presented.


Author(s):  
V. V. Sorokin

Localizing safety systems are provided to contain radioactive substances in an accident and attenuate ionizing radiation at a modern nuclear power plant. Together with radioactive substances, hydrogen is also retained, which is formed during the decomposition of the primary coolant. The accumulation of hydrogen in the presence of oxygen from the atmosphere in the accident localization zone carries the danger of the formation of flammable and explosive concentrations of these components. Nuclear power plant (NPP) deigns with water-water energetic reactor (WWER) provides for a hydrogen removal system including passive catalytic hydrogen recombiners. The device capacity  is confirmed experimentally under reference conditions (lean air-hydrogen mixture, pressure and temperature close to normal, no interference with gas exchange). Capacity is an important safety parameter. In the event of an accident, conditions inside the ealed enclosure of the localizing system of NPP with WWER can  differ from the reference  ones and affect the capacity.  On the basis of calculations, the operation of recombiners with lack of  oxygen  and with hindered  gas exchange has been investigated in the paper. The decrease in capacity with lack of oxygen reaches 50 %, which is mainly  caused by an increase in underburning. Compared to the reference conditions, the effect is more pronounced in the event of an accident – 60–70 %. The hindered gas exchange is modeled by a decrease in the height of recombiner traction channel. This case can be reduced to the placement of the device in cramped conditions and the effect of the atmosphere speed inside the enclosure. Regardless of the hydrogen concentration, the operating characteristic of the device remains linear, with a two-fold decrease in height leads to a decrease in capacity by 20 %. The results can be used to substantiate the safety of NPPs with WWER and to review on the safety subtantiation of power units.


Author(s):  
Jun Zhou

Severe weather such as typhoon has long been a great challenge threats the safe operation of nuclear power plants. To cope with typhoon, Qinshan III NPP has developed an effective management system, including building powerful organizations, creating standard response procedures and consumable storage, which proven to be effective to ensure the safe operation of Qinshan III plant under severe weather conditions.


Author(s):  
Wang Renze ◽  
Zhang Jiangang ◽  
Yang Yapeng ◽  
Feng Zongyang ◽  
Jia Linsheng ◽  
...  

Abstract The safety characteristics and potential hazards of reprocessing facilities are different from those of nuclear power plants (NPPs). Emergency action level (EAL) development is an important aspect of emergency preparedness, and EAL is an important basis for emergency response of reprocessing facilities. EAL quantitative research can enhance its operability. At present, the domestic and foreign literature, generally only gave the principle method for EAL development. There are no operational guidance documents for specific EAL quantification in reprocessing facilities. According to the features of the functions and configurations of the reprocessing facilities, two additional categories EAL, E category for the spent fuel pool accident and W category for the high level liquid waste tank accident, have been added. Meanwhile, four categories-S, F, A, H are retained with similar implication as NPPs. On the basis of existing principles and practical experience, specially the reference from DOE G 151.1-1A, EAL quantification was developed according to the characteristics and symptoms related to the safety of reprocessing facilities. EAL quantification for several accidents was developed, and it was with good maneuverability. The study for EAL quantification in reprocessing facilities shows that, quantitative, indicative, practical EALs can make emergency response more accurate and efficient, and ongoing research is strongly requisite.


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