scholarly journals Cytogenetic bio-dosimetry techniques in the detection of dicentric chromosomes induced by ionizing radiation: A review

2021 ◽  
Vol 136 (5) ◽  
Author(s):  
G. M. Ludovici ◽  
M. G. Cascone ◽  
T. Huber ◽  
A. Chierici ◽  
P. Gaudio ◽  
...  

AbstractIonizing radiation is ubiquitous in the environment. Its source can be natural, such as radioactive materials present in soil and cosmic rays, or artificial, such as the fuel for nuclear power plants. Overexposure to ionizing radiation may damage living tissue and could cause severe health problems (i.e., mutations, radiation sickness, cancer, and death). Cytogenetic bio-dosimetry has the great advantage to take into account the inter-individual variation, and it is informative even when physical dosimetry is not applicable; moreover, it is the definitive method to assess exposure to ionizing radiation recommended by the World Health Organization (WHO). Such a procedure involves counting the frequency of dicentric chromosomes (DCs), which are the most studied chromosomal aberrations used as absorbed radiation biomarkers, during the metaphase of cells. A set of algorithms, tested on different programming languages to automatically identify DCs, is analyzed by the authors together with an Automated Dicentric Chromosome Identifying software (ADCI) mostly based on OpenCV programming libraries. The purpose of this work is to review the main results regarding the correlation between ionizing radiation and dicentric chromosomes in cytogenetic bio-dosimetry.

Author(s):  
Boo Ho Yoon ◽  
Jae Hak Cho ◽  
Sang Chul Lee ◽  
Dong Woo Kang ◽  
Yong Joon Choi ◽  
...  

For the research on the vitrification of the low-level radioactive wastes (LLRW) produced in nuclear power plants, one pilot plant with plasma arc melter system was built and several tests were done on it. Some surrogate wastes, which were spiked with several materials and were made very similar to the real LLRW, were used for these tests. For the vitrification of the surrogate wastes, the surrogate wastes were classified into the combustible, the non-combustible and the resin. Then each waste was spiked with special materials and was melted in separate. Off-gases produced in each test were picked up and analyzed. Real radioactive materials cesium (Cs) and cobalt (Co) were spiked in each wastes. Data gained from the final glass formulation were follows. Glass density is 2.42 ∼ 2.95(g/cm3), the compressive strength is 30 ∼ 175 Mpa, micro hardness is 5.5 ∼ 5.8 Gpa. The leaching ratio for Co is 1.27×10−4 ∼ 1.08×10−3 (10mL/g) and that for Cs is 2.46×10−3 ∼ 3.23×10−2 (10mL/g). The leaching speed for Co is 4.14×10−7 ∼ 5.53×10−6 (g/m2) and that for Cs is 4.58×10−5 ∼ 3.87×10−4 (g/m2). In off-gas, dioxin & furan is 0.016 mano gram on the average, CO is about 20 ppm, NO2 is about 15 ppm and SO2 is about 15 ppm.


Author(s):  
Naoki Horiguchi ◽  
Hiroyuki Yoshida ◽  
Akiko Kaneko ◽  
Yutaka Abe

As revealed by Fukushima Daiichi nuclear disaster, countermeasures against severe accidents in nuclear power plants are an urgent need. In particular, from the viewpoint of protecting containment and suppressing diffusion of the radioactive materials, it is most important to install filtered venting devices to release high pressure contaminated gas to the atmosphere with elimination radioactive materials in the gas. A Multi Venturi Scrubber System (MVSS) is one of the filtered venting devices, and used in European reactors [1, 2]. One of the main components of the MVSS is a Venturi Scrubber (VS). It is considered that a dispersed or dispersed annular flow is formed in the VS by a self-priming phenomena. In the self-priming phenomena, the liquid was suctioned from a surrounding region of the VS to the inside of the VS. And a part of the radioactive materials are eliminated through the gas-liquid interface of the dispersed or annular dispersed flow. Therefore, to consider the MVSS operation characteristics, it is important whether to occur the self-priming or not and the liquid flow rate of the self-priming of the VS. The objective of this paper is to understand the self-priming phenomena of the VS for the filtered venting. And theoretical analysis and experiment were conducted. By comparing these results, we discussed about the mechanism of the self-priming phenomena. As results, the self-priming phenomena in the VS was confirmed and, at a high gas flow rate, the suspension of the self-priming is confirmed experimentally and theoretically.


2018 ◽  
pp. 66-70
Author(s):  
O. V. Taran ◽  
O. G. Sandul

The nuclear energy use progressively becomes part of the life of every modern person, who more and more faces radioactive materials in medical institutions, in industry. Half of all electricity generated in Ukraine is generated by nuclear power plants. The peculiarities of the nuclear energy use generate appropriate rules for people dealing with radioactive materials. The article analyzes the standards of the Criminal Code of Ukraine, which provides for liability for acts related to the illegal handling of radioactive materials, for violation of the nuclear and radiation safety rules, violation of radiation safety requirements, the threat of theft of radioactive materials, the illicit manufacturing of a nuclear explosive device, abduction or capture of radioactive materials, attack on radioactive materials transportation means. The grounds and peculiarities for bringing to criminal liability have been reviewed, the range of persons who can be prosecuted has been defined. Conditions and grounds for exemption from criminal liability in the absence of a person's criminal intent to use radioactive material are considered. It has been demonstrated that the Criminal Code of Ukraine, by prohibiting certain actions on the illegal radioactive materials handling, ensures protection of the most important social relations and social benefits.


Author(s):  
Gaetano Ruggeri ◽  
Luigi Brusa

Abstract Scope of the paper is to summarise the experience about management of materials arising from decommissioning of Italian NPPs, and to illustrate criteria, procedures and systems, which Sogin is defining to manage the problem of the clearance of sites and materials, considering the international experience and boundary conditions existing in the Country. Since 1962 Enel (the largest Italian utility for electric power) has operated the four Italian nuclear power plants: Garigliano (160 MWe BWR), Latina (210 MWe GCR), Trino (270 MWe PWR) and Caorso (882 MWe BWR). These NPPs were shutdown in the 80’s: Garigliano NPP was shutdown in 1982 following a decision made by Enel, based on technical and economical reasons, Latina, Trino and Caorso NPPs following decisions made by the Italian Government after the Chernobyl accident. The “deferred decommissioning (SAFSTOR)” was the decommissioning strategy selected by Enel and approved by the competent Authorities, due to the lack of a repository for the disposal of radioactive materials and of release limits for clearance of materials. Activities have been started aimed at reaching the “Safe Enclosure” condition, which would have lasted for some decades, before final dismantling of plants. In 1999 the liberalisation of the Italian electricity market led Enel to separate its nuclear activities, forming a new Company, named Sogin, to which decommissioning Italian NPPs was committed. At the same time, considering pressures, both at national and local level, to adopt the “prompt decommissioning (DECON)” strategy, in December 1999 the Italian Minister of Industry, with the intent to accelerate the dismantling of Italian NPPs, presented the plans to create a national repository for nuclear waste, and asked Sogin to revise the decommissioning plans, according to the new global strategy, taking into account all the relevant technical, organisational, financial and legislative aspects of the problem. As the DECON strategy enhances the importance of “clean-up” both of sites and materials, the related aspects are held in due consideration in developing the decommissioning plans, which deal with the following: • characterisation of plant systems, components and structures; • decontamination and dismantling techniques; • monitoring of dismantled materials for clearance; • treatment of dismantled, radioactive materials (which cannot be cleared), prior to disposal; • treatment and conditioning of radioactive waste, prior to disposal; • final clearance of sites. Authorisation requirement related to the release, recycle and reuse of materials produced during plant decommissioning, together with the acceptance criteria for disposal of radioactive materials, are of key importance, considering that the change in decommissioning strategy increases the quantity of radioactive waste to be disposed of, the costs for waste treatment, transportation and disposal, and the capacity of the national repository. In this connection, Sogin is discussing with competent Authorities and Bodies in order to define clearance criteria and disposal acceptance criteria, which neither impair nor complicate the future dismantling operations. In (1) details are given about Italian decommissioning Regulation, decommissioning strategy and Organisation, in order to show the boundary conditions, which exist in Italy for planning and development of NPPs Decommissioning Projects. In the following paragraphs the decommissioning strategy is summarised first together with some critical items of decommissioning; then the Italian regulation about the management of radioactive waste is reported. The management of waste and materials, which will arise from the decommissioning of Italian nuclear power plants, is driven by the requirements imposed by the competent Authorities basing on this regulation.


2009 ◽  
Vol 160 (4) ◽  
pp. 625-630 ◽  
Author(s):  
Bernhard O Boehm ◽  
Marianna Steinert ◽  
Johannes W Dietrich ◽  
Ralf U Peter ◽  
David Belyi ◽  
...  

ContextRadioactive contamination from the Chernobyl nuclear accident that happened on the morning of 26th April 1986 had a major impact on thyroid health in the Belarus region.ObjectiveObservational study of a cohort of 99 adults, most strongly exposed to ionizing radioactivity.Design, setting and patientsObservational study performed between 1998 and 2000. The cohort comprised 99 workers (92 male) of the Chernobyl nuclear power plant. Examination including physical examination, ultrasonography of the thyroid gland and measurement of serum free thyroxin (fT4), free triiodothyronine (fT3) and TSH. Anti-thyroperoxidase (anti-TPO), antithyroglobulin (anti-Tg) antibodies and thyroid stimulating immunoglobulin were also determined.Main outcome measuresThe impact of exposure to high-dose radiation, including radioactive iodine, on the thyroid gland was examined.ResultsLevels of fT4in all probands were within the normal World Health Organization-defined range. Elevated levels of fT3were found in two workers (2%), high titres of anti-TPO and anti-Tg antibodies were present in four subjects (4%). Mild hypothyroidism was present in one patient. Enlargement of the thyroid gland was observed in 17 workers (17%). There was no evidence of clinically overt thyroid cancer.ConclusionsThe Chernobyl accident showed surprisingly little impact on the thyroid in a cohort of workers strongly exposed to radiation. Our data suggest an age-dependent heterogeneity in response to the short-lived radioiodine isotopes and favours long-term follow-up analysis.


1997 ◽  
Vol 506 ◽  
Author(s):  
H.-F. Beer ◽  
M. Jermann

ABSTRACTBecause of its experience in handling radioactive materials including waste generated on-site PSI was charged with managing the treatment and interim storage of the radioactive waste from medicine, industry and research in Switzerland. Combustible operational waste from the Swiss nuclear power plants is conditioned on a contract base and stored temporarily at the sites of the power plants. Because of the decommissioning of old facilities provoked by the change in the research priorities at PSI, temporarily an additional amount of waste is released on-site to be treated. PSI possesses the facilities and the organisational structure to fulfil the tasks it is charged with. In the near future the major part of the conditioning procedures, except the conditioning of some of the waste containing α-emitters, will be performed by ZWILAG. PSI will stay responsible for the management, organisation and interim storage of all radioactive waste, except for nuclear power plant waste, as before.


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