Determination of effective standards for the introduction of fodder additive Aquatan in the diet of rainbow trut with a biological assessment of the influence on fisheries

Author(s):  
Dmitry Dmitrievich Zekov ◽  
Mikhail Vladimirovich Ulyanov ◽  
Daniil Veniaminovich Mikryakov ◽  
Tatyana Alexandrovna Suvorova

In connection with the global tendency to prohibit the use of antibiotics in animal husbandry, the prospect of using in ichthyopathological practice preparations from plant materials, which are mostly non-toxic, rarely cause side effects, have an antibacterial effect against a wide range of pathogens of bacterial diseases, opens up. One of these preparations is the feed additive Aquatan (Farmatan Aqua) based on ellagitannins from sweet chestnut wood manufactured by Tanin Sevnica (Slovenia). The aim of this work was to study the effect of different dosages of Aquatan on the survival rate, the rate of mass accumulation and the growth rate of rainbow trout reared in the industrial conditions of the cage farm on the waste warm waters of the nuclear power plant and to assess the production and economic efficiency of the application. The tests were carried out for 34 days in February-March 2021 on the basis of an aquaculture cage farm of LLC “Fish Federation”, located in the water area of the waste canal of warm waste water of the Leningrad nuclear power plant (LNPP) in the area of the LNPP-2 industrial zone in the city of Sosnovy Bor, Leningrad Region. The object of the study is rainbow trout yearlings brought from different fish farms. A total of 247,131 specimens were planted, with an average weight of 156.5–235.7 g and a total weight of 43 950.67 kg. The main hydrochemical indicators of water at the enterprise for the trial period met the water quality requirements for growing salmon fish OST 15.372-87. The feeding was carried out with the production compound feed for salmonids of the firm Alltech® Coppens Supreme-22. In experimental cages, fish were fed with compound feed with the addition of the preparation Aquatan at various concentrations (1, 2, and 3 g/kg of feed); in the control, feed without additive was used. As a result of the experiment, a positive effect of the Aquatan additive in dosages of 2–3 g / 1 kg of feed on growth, mass accumulation, survival and feed costs was established, while when adding 1 g / 1 kg of feed, such an effect was not recorded.

Author(s):  
Young Sik Pyun ◽  
Ruslan Karimbaev ◽  
Seimi Choi ◽  
Jun Suek Ro ◽  
Choong Ho Sanseong ◽  
...  

Abstract Additive Manufacturing (AM) which is also known as metal 3D printing technique is one of the promising manufacturing processes due to the capability to process a complex geometry component. This is implemented in wide range of applications in various industries such as automotive, aerospace, power plants, etc. The aging nuclear power plant components and the obsolescence of those components has become a concern in this industry, and AM has come as an alternative solution for this matter. The Board on Pressure and Technology Codes and Standards (BPTCS) and Board on Nuclear Codes and Standards (BNCS) Special Committees started to study the application of Powder Bed Fusion (PBF) technique for pressure retaining equipment made from UNS S31603. Also, later Korean International Working Group (KIWG) was also started a Task Group on Additive Manufacturing for Valves which focusing on Powder Bed Fusion (PBF) and Direct Energy Disposition (DED) process for pressure-retaining valve manufacturing especially for nuclear power plant application with the same material. However, the poor mechanical properties and performance, especially fatigue strength of AM materials become a concern due to the defects and flaws as the results of layering and multiple interfaces and welding related discontinuities. In this study, the fatigue strength of PBF and DED manufactured and Ultrasonic Nanocrystal Surface Modification (UNSM) treated UNS S31603 austenitic stainless steel was investigated.


Author(s):  
I. Pinchuk ◽  
◽  
S. Boltonosov ◽  
N. Atamanchuk ◽  
N. Stepanova ◽  
...  

The article is devoted to the problem of completed suicides among veterans of the Joint Forces for National Security and Defense operation in Donetsk and Luhansk regions (JFO) and liquidators of the consequences of the Chornobyl accident (LCCA). The results of the analysis of surveys of families and close associates of JFO veterans who committed a completed suicide in the period 2014–2019 are presented. The survey was conducted as part of criminal proceedings initiated on the facts of suicide. Objective: to analyze the current dynamics of suicidal behavior in veterans of JFO and the impact of psychosocial factors on its development and compare with the relevant indicators among LCCA at the Chornobyl nuclear power plant. Materials and methods: 175 questionnaires are presented, socio-demographic characteristics are compiled and psychosocial factors that influenced the development of suicidal behavior in environmental protection veterans are identified. An analysis of the status of such studies among liquidators of the Chornobyl accidents. Results: the data analysis of suicidal behavior in veterans of environmental protection, the impact on its development of psychosocial factors and comparison with the indicators among LCCA at the Chornobyl Nuclear Power Plant. Conclusions: The results of the study show that in emergency situations, mostly men from all regions of the country, both professional servicemen and civilians, are involved in its elimination. It has been proven that while performing their official duties, the veterans of JFO and LCCA at the Chornobyl nuclear power plant experienced mental stress. But most of them, returning home, did not seek medical treatment, prevent the development of diseases and their complications and remained for a long time without proper medical, social and psychological care. Key words: completed suicides, suicidal behavior, psychosocial factors, veterans of environmental protection, liquidators of the Chornobyl accident.


2018 ◽  
Vol 47 (3-4) ◽  
pp. 214-220 ◽  
Author(s):  
D.A. Cool

Committee 4 of the International Commission on Radiological Protection (ICRP) is charged with the development of principles and recommendations on radiological protection of people and the environment in all exposure situations. For the term beginning in July 2017, the Committee has a total of 18 members from 12 countries. The programme of work includes a wide range of activities in five major thematic areas. The first is the consolidation and preparation of reports elaborating application of the system of protection in existing exposure situations. Second is the continuation of work on emergency exposure situations, and ICRP updates to recommendations in light of the accident at Fukushima Daiichi nuclear power plant. Third is examination of fundamentals of protection recommendations, including the ethical principles underlying the recommendations and application of those principles in practical decision making. Fourth is the new area of integration of protection of the environment into the system of protection. Finally, Committee 4 continues work to prepare specific topical reports on subjects in which additional information is useful to understand and apply the Commission’s recommendations in particular circumstances.


Author(s):  
Byeongnam Jo ◽  
Shinji Takahashi ◽  
Daehun Song ◽  
Wataru Sagawa ◽  
Nejdet Erkan ◽  
...  

Experimental and numerical studies into thermal stratification by direct steam condensation in a torus type suppression pool were carried out to investigate the reactor core isolation cooling in the accidents of Fukushima Daiichi nuclear power plants. The suppression pool was manufactured to be a 1/22 scaled model of a Fukushima Daiichi nuclear power plant. Two different types of spargers were employed to simulate different units of the plants. In a sparger, 132 holes were uniformly drilled on the side of a pipe. However, the other sparger injected steam to the bottom. Flow rate was varied in a wide range to examine the effect on thermal stratification in the suppression pool. The experimental results showed that the sparger type influenced formation of thermal stratification. Moreover, steam flow rate strongly affected the onset time of thermal stratification, and the disappearance of the thermal stratification was affected by subcooling temperature. Computer simulation using a commercial software was conducted and the results show similar temperature profiles to the experimental results. Steam condensation was visualized in a vicinity of the spargers using high speed camera.


2020 ◽  
Author(s):  
Toyoaki Sawano ◽  
Akihiko Ozaki ◽  
Masaharu Tsubokura

In the radiation industry, occupational health is a significantly important issue. As the workers belong to a wide range of socioeconomic classes, the management of the health of the workers, especially in a lower socioeconomic status, such as migrant workers, is essential. After the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident, migrant decontamination workers were recruited to help clean up and mitigate the ionizing radiation in evacuation zone, in order to resume life. As this was the first attempt at such decontamination work after a nuclear accident, these workers were the first to experience these conditions. However, limited information is available on the health of the workers engaged in this work. This paper comprehensively reviews the existing health risks faced by the workers after the FDNPP accident to provide general health guidelines to mitigate the health risks of decontamination workers in future disasters. Following previous literature, the health risks were categorized by those associated with occupational hazards and those associated with the living environment. Not only a mitigation of the direct occupational hazards, such as radiation exposure, work-related infection and trauma during work, but also the management of lifestyle should be adequately supported for decontamination workers of future nuclear disasters.


Author(s):  
Young Sik Pyun ◽  
Seimi Choi ◽  
Ruslan Karimbaev ◽  
Jun Suek Ro ◽  
Choong Ho Sanseong ◽  
...  

Abstract Additive Manufacturing (AM) which is also known as metal 3D printing technique is a promising process with a massive potential for developing a component for wide range applications for various industries. Recently, AM process was introduced to the nuclear power plant industry as AM is capable of manufacturing the substitution of aging and obsolete component. However, the AM component has inferior mechanical properties and performance in terms of fatigue strength and wear resistance compared to its conventionally manufactured counterpart. Ultrasonic Nanocrystal Surface Modification (UNSM) is one of mechanical surface modification treatment known for improving fatigue strength and wear resistance of wrought material. Hence, in this study effect of UNSM treatment on fatigue strength and wear resistance of additive manufactured material was investigated. The investigation was done to Ni-based alloy 718 (UNS N07718) as this material is used for nuclear power plant components and was manufactured with two different AM techniques namely Powder Bed Fusion (PBF) and Direct Energy Deposition (DED) processes. The evaluation was conducted by comparing the as-polished and UNSM-treated specimens for each AM processes by performing fatigue and tribo tests. This result will become a part of the technical basis for KEPIC Code Case development.


2018 ◽  
Vol 7 (2.12) ◽  
pp. 210
Author(s):  
Vinay Kumar ◽  
Dewanshu Pratihar ◽  
Anil Kumar Tripathi

Probabilistic Safety Assessment approach has been successfully applied in engineering, economics, computer science and statistics to re-solve a wide range of safety-related problems. However, using Probabilistic Safety Assessment for quantifying safety of a safety critical system is a challenging task in Safety Engineering community. This method plays an essential role in analyzing safety of safety critical sys-tems and its various components. Therefore, in this paper, we present Probabilistic Safety Assessment framework which can be used to quantify the critical failures of a systems. The approach is well demonstrated on a Digital Feed Water Control System uses in a Nuclear Power Plant as safety critical system. 


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