=Paper=
{{Paper
|id=Vol-3085/paper05
|storemode=property
|title=The use of specialized software for liquid radioactive material spills simulation to teach students and postgraduate students
|pdfUrl=https://ceur-ws.org/Vol-3085/paper05.pdf
|volume=Vol-3085
|authors=Oleksandr O. Popov,Yurii O. Kyrylenko,Iryna P. Kameneva,Anna V. Iatsyshyn,Andrii V. Iatsyshyn,Valeriia O. Kovach,Volodymyr O. Artemchuk,Valery N. Bliznyuk,Arnold E. Kiv
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==The use of specialized software for liquid radioactive material spills simulation to teach students and postgraduate students==
https://ceur-ws.org/Vol-3085/paper05.pdf
The use of specialized software for liquid radioactive
material spills simulation to teach students and
postgraduate students
Oleksandr O. Popov1,2,3 , Yurii O. Kyrylenko1,2,4 , Iryna P. Kameneva2 ,
Anna V. Iatsyshyn1,5 , Andrii V. Iatsyshyn1,2 , Valeriia O. Kovach1,3,6 ,
Volodymyr O. Artemchuk1,2 , Valery N. Bliznyuk7 and Arnold E. Kiv8
1
State Institution “The Institute of Environmental Geochemistry of National Academy of Sciences of Ukraine”,
34a Palladin Ave., Kyiv, 03142, Ukraine
2
G. E. Pukhov Institute for Modelling in Energy Engineering of NAS of Ukraine, 15 General Naumova Str., Kyiv, 03164,
Ukraine
3
Interregional Academy of Personnel Management, 2 Frometivska Str., Kyiv, 03039, Ukraine
4
State Scientific and Technical Center for Nuclear and Radiation Safety, 35-37 V. Stusa Str., Kyiv, 03142, Ukraine
5
Institute for Digitalisation of Education of the National Academy of Educational Sciences of Ukraine, 9 M. Berlynskoho
Str., Kyiv, 04060, Ukraine
6
National Aviation University, 1 Liubomyra Huzara Ave., Kyiv, 03058, Ukraine
7
Clemson University, 342 Computer Court, Anderson, SC 29625, United States of America
8
Ben-Gurion University of the Negev, P.O.B. 653, Beer Sheva, 8410501, Israel
Abstract
The study proves relevance of specialized software use to solve problems of emergencies prevention of
radioactive liquids spills to teach students and graduate students. Main assessment criteria of accidents
at radiation-hazardous objects associated with radioactive liquids spillage is identified. A model of
radioactive substances transport in emergency rooms is developed. It takes into account physical features
of radioactive liquid spill from the source, air pollution during transition of radioactive liquid from the
spill surface into the air and subsequent scattering in the emergency room under influence of local
air flows. It is determined that the existing software tools for radiation exposure assessment do not
comprehensively cover features of such events and possess number of shortcomings regarding accidents
modeling with spillage of radioactive liquids indoors. Computer modeling and forecasting examples
for hypothetical event related to liquid radioactive spill in the JRODOS system are presented. The
training process of future specialists, specialties 183 “Environmental Protection Technologies”, 143
“Nuclear Energy”, 103 “Earth Sciences”, and 122 “Computer Science” should be based on application of
powerful scientific and methodological training base using modern achievements in the field of digital
technologies. It is advisable to supplement curricula for students‘ and postgraduate students’ preparation
in the mentioned above specialties by studying issues related to: development of mathematical models
and software for solving problems of emergencies prevention in case of radioactive liquids spills; usage
of features of specialized decision software of emergencies prevention during spills of radioactive liquids.
Keywords
computer simulation, specialized information system, mathematical modelling, emergencies prediction,
radioactive liquids, training of students, graduate students
306
1. Introduction
Nuclear energy has provided a significant share of Ukraine’s total electricity production for
many decades. So, stable operation of nuclear energy is a necessary condition for continued
economic development of the country. Today in Ukraine there are main directions of theory
and practice of safe operation ensuring of nuclear power plants (NPPs) that addresses complex
issues of minimizing risk levels. There is a need for more realistic and accurate modeling of
hazardous events at NPPs related to normal operation (events, frequency of implementation)
which may exceed value of 0.01, 1/year) due to conduct of probabilistic safety analysis for
Ukrainian NPP units and introducing of NRBU-97/D-2000 requirements for potential exposure
of population in recent decades. Such events included accidents involving spillage of liquid
radioactive material (LRM) after a probabilistic safety analysis. One of representative events
related to radioactive heavy water spill took place at the Pakistani Karachi NPP (power unit
No. 1) in 2017. Four people were irradiated as a result of the spill localization. The effective
radiation dose of one of the liquidators reached a value of almost 40 mSv, which is 2 times
higher than the set limit dose for personnel in Pakistan. This event was classified as the 2nd
level according to the International Nuclear Event Scale (INES) according to the investigation
results. Events of this type also took place in Ukraine. Insufficient level of staff skills and lack of
readiness to eliminate emergencies of radioactive liquids spillage fast leads to emergencies and
huge material costs for energy supply restoration [1].
Nuclear power workers should have skills to use digital technologies which help in modeling
and prediction of systemic accidents conditions at radiation-hazardous facilities. Ability to
apply these technologies is important for further professional activity. Given that digital
technologies are constantly improving and new management systems are developing. It is
important to familiarize training staff with the latest developments, systems, software and
experience-exchange to apply these tools in further professional activities.
LRM spills are also possible at the Chornobyl Liquid Radioactive Waste Processing Plant, at
CTE 2021: 9th Workshop on Cloud Technologies in Education, December 17, 2021, Kryvyi Rih, Ukraine
" sasha.popov1982@gmail.com (O. O. Popov); uo_kyrylenko@sstc.ua (Y. O. Kyrylenko); kamenevaip@gmail.com
(I. P. Kameneva); anna13.00.10@gmail.com (A. V. Iatsyshyn); iatsyshyn.andriy@gmail.com (A. V. Iatsyshyn);
valeriiakovach@gmail.com (V. O. Kovach); ak24avo@gmail.com (V. O. Artemchuk); deeescu@gmail.com
(V. N. Bliznyuk); kiv.arnold20@gmail.com (A. E. Kiv)
~ https://www.nas.gov.ua/EN/PersonalSite/Pages/Contacts.aspx?PersonID=0000010803 (O. O. Popov);
https://www2.scopus.com/authid/detail.uri?authorId=57208404766 (Y. O. Kyrylenko);
https://www.nas.gov.ua/EN/PersonalSite/Pages/default.aspx?PersonID=0000005199 (I. P. Kameneva);
https://www.nas.gov.ua/EN/PersonalSite/Pages/default.aspx?PersonID=0000030359 (A. V. Iatsyshyn);
https://www.nas.gov.ua/EN/PersonalSite/Pages/default.aspx?PersonID=0000015808 (A. V. Iatsyshyn);
https://www.nas.gov.ua/EN/PersonalSite/Pages/default.aspx?PersonID=0000005869 (V. O. Kovach);
https://www.nas.gov.ua/EN/PersonalSite/Pages/default.aspx?PersonID=0000000337 (V. O. Artemchuk);
https://www.scopus.com/authid/detail.uri?authorId=7006587198 (V. N. Bliznyuk);
https://ieeexplore.ieee.org/author/37087598865 (A. E. Kiv)
0000-0002-5065-3822 (O. O. Popov); 0000-0003-3493-201X (Y. O. Kyrylenko); 0000-0003-2659-4487
(I. P. Kameneva); 0000-0001-8011-5956 (A. V. Iatsyshyn); 0000-0001-5508-7017 (A. V. Iatsyshyn); 0000-0002-1014-8979
(V. O. Kovach); 0000-0001-8819-4564 (V. O. Artemchuk); 0000-0002-3883-6941 (V. N. Bliznyuk); 0000-0002-0991-2343
(A. E. Kiv)
© 2020 Copyright for this paper by its authors.
Use permitted under Creative Commons License Attribution 4.0 International (CC BY 4.0).
CEUR
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Proceedings
http://ceur-ws.org
ISSN 1613-0073
CEUR Workshop Proceedings (CEUR-WS.org)
307
oncology hospitals that use radioisotopes to treat patients, at uranium mining and uranium
processing facilities, during transportation of liquid radioactive waste etc.
Thus, the urgent tasks are the following:
1) for scientists and experts – to improve the enterprises and organizations safety with risk of
LRM spillage by developing mathematical and software solutions to prevent emergencies of
this type;
2) for scientific and pedagogical workers – to update educational-professional and educational-
scientific training programs for future specialists in Earth sciences, computer science, nuclear
energy, and environmental protection technologies on development of mathematical and
software tools ensuring solution of emergency prevention problems during LRM spills.
Various aspects of digital technologies use to prevent emergencies are discussed in publica-
tions [2, 3, 4, 5, 6]. Specialized software for computer modeling of various processes is described
in works [7, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17, 18]. Analysis of foreign and domestic accidents
and incidents with LRM spills [1, 19, 20, 21] shows that problem of radiation emissions impact
estimation in such accidents remains relevant and needs further research. Existing mathematical
and computer tools for radiation exposure assessment (MELCOR, CONTAIN, MAAP, etc.) do not
comprehensively cover features of such dangerous events and possess number of shortcomings
in modeling of accidents with LRM spills.
Peculiarities of future specialists training in Earth sciences, computer science, and environ-
mental protection technologies were the subject of research in [22, 23, 24, 25, 26, 18, 27, 28,
29, 30, 31, 32]. However, the problem of specialized software usage for solving problems of
emergency prevention (for example, the LRM spill) in training of students and graduate students
is not sufficiently considered. Therefore it is relevant and needs further research.
The research aim – to investigate peculiarities of mathematical and software tools development
for solving problems of emergency prevention in case of LRM spills and to describe 7 directions
of this software application during preparation of students and graduate students majoring
in environmental sciences, Earth sciences, computer science, nuclear energy, environmental
protection technology.
The research tasks are:
1) analysis of incidents with LRM spills;
2) description of features of development of mathematical and software tools for solving
problems of emergency prevention during LRM spills;
3) showing examples of computer modeling of atmospheric dispersion and effective dose by
using system JRODOS.
2. Research results
In accordance with the probabilistic safety analysis for Ukrainian NPP units and the radiation
safety standard NRBU-97/D-2000 requirements for potential public exposure, there is a need
for more realistic and precise modeling of events at NPPs related to abnormal operation the
frequency of which may exceed the value of 0.01 1/year). After conducting a probabilistic safety
308
analysis, such events include accidents involving the spills of radioactive liquids at the area of
facilities.
LRM are liquid solutions, which include impurities of radioactive elements (possible bounds
in high-molecular complexes). The isotopic composition of LRM is determined primarily by the
source of radioactive impurities. The main sources of LRM at nuclear power plants and nuclear
complexes are as follows: primary coolant that is discharged for operational reasons; water that
is used to backflush filters and ion exchangers; floor drains that collect water that has leaked
from the active liquid systems and fluids from the decontamination of the plant and fuel flasks;
leaks of secondary coolant; laundries and changing room showers; and chemistry laboratories.
According to INES [33], accidents involving spills of radioactive liquids, depending on the
magnitude of the release and the corresponding radiation effects, can be assigned different
levels of danger (from level 0 “Event with a deviation below the scale" to 7 “Major accident”).
This approach reflects the design features of heat dissipation from the core of reactors operating
on liquid coolant. During the severe accident with melting of the reactor core, the products of
nuclear fuel fission come into direct contact with the liquid coolant and water of the emergency
cooling systems, which will lead to further formation of radioactive liquids. Neutron activation
of the coolant during the campaign at the reactor units also makes a significant contribution to
the atmospheric release activity. In both, the first and the second case, the activity of the liquids
represents a small part of the total release activity. Therefore, when assessing the consequences
of severe accidents, the source term associated with evaporation of liquid spills is often neglected.
However, if the accident involves the release solely from the evaporation from open surfaces,
depending on the concentration of radionuclides in the liquid and the conditions of the accident,
the release can pose a significant threat to personnel, public and environment.
2.1. Events related to spill of radioactive liquids
In previous publications, we analysed and systematized accidents with the spills of radioactive
liquids. The place and year of the accident or incident, the level on the INES scale are indicated
and a brief description of the event is given. It should be noted the low number of official reports
on the radiation consequences of accidents and incidents related to the spillage of radioactive
liquids.
As an example, in 2010 at the Ignalina NPP [34] there was a spill of about 300 tons of
radioactive decontamination solution. Figure 1 shows the pictures of this incident. For this
event, no official information on the results of dosimetric monitoring at the NPP site, as well
as the classification according to the INES scale, was provided. Figure 2 presents the author’s
infographics of incidents with LRM spills at Ukrainian NPPs.
2.2. Mathematical model of radioactive substances transfer in emergency
rooms
Figure 3 schematically shows processes that occur after incident with spill of LRM in the rooms
of radiation-hazardous object.
Modeling of the LRM Evaporation. To solve the problem of unsteady LRM evaporation, four
balance differential equations (1) were written to relate the main parameters of LRM and air
309
Figure 1: Photos of the accident with the spill of radioactive decontamination solution at the Ignalina
NPP (Lithuania, 2010): view of the broken pipeline (a), general view of the spill part (b) [34].
Figure 2: Infographics of LRM spill accidents at Ukrainian NPPs.
space of area over time:
310
Figure 3: Conceptual scheme of air pollution after incident with spill of LRM in the rooms of radiation-
hazardous object.
⎧
𝑑𝑚𝑤
𝑑𝑡 = −𝛽𝑠𝑤 (𝑝𝑠𝑤 − 𝑝𝑚 )𝑆 − 𝐺𝑑
⎪
⎪
⎪
⎨ 𝑑𝑚𝑎 = 𝛽 (𝑝 − 𝑝 )𝑆 − 𝐺 𝑚𝑎
⎪
𝑠𝑤 𝑠𝑤 𝑚 𝑉 𝑉
𝑑𝑡
𝑑𝑚𝑞 𝑚𝑎 (1)
𝑑𝑡 = 𝐺𝑉 𝑉 (1 − Ψ)
⎪
⎪
⎩ 𝑑𝑇𝑤 = 𝑟𝑤 𝛽𝑠𝑤 (𝑝𝑠𝑤 −𝑝𝑚 )𝑆+𝑘𝐹 (𝑇𝑊 −𝑇𝑓 ) ,
⎪
⎪
𝑑𝑡 𝑐𝑝 𝑚𝑤
where 𝑚𝑎 – current mass of SARM in air of the area, 𝑘𝑔;
𝐺𝑑 – flowrate of LRM through the drainage channel (it also includes the volume of LRM
leakage from the area), 𝑘𝑔/𝑠;
𝑉 – air volume in the area, 𝑚3 ;
𝐺𝑉 – flowrate of involved air of forced ventilation (this parameter includes SARM leakage
through the gaps or clearances in walls of the emergency area), 𝑚3 /𝑠;
Ψ – coefficient of filtration (efficiency of filtration);
𝑚𝑞 – mass of released SARM into the atmosphere, 𝑘𝑔.
This system of nonlinear differential equations includes polynomial functions. Using the
Mathcad sphere for solving the system of equations (1) provides the desired functions in matrix
form (the values of the functions at particular moments of accident).
Average activity concentration of the radionuclide in the area air 𝐴𝑎𝑖𝑟 (𝐵𝑞/𝑚3 ) is given by
the formula
𝐴𝑤
𝐴𝑎𝑖𝑟 = 𝐻𝑚𝑎 , (2)
𝑉
where 𝐴𝑤 – concentration of radionuclide in LRM, 𝐵𝑞/𝑘𝑔;
𝐻 – fraction of carried away solute with solvent vapors during evaporation.
The ultimate objective of the model is to determine the dynamics of LRM evaporation, SARM
activity in the air space and the integral release of radioactive substances into the atmosphere.
311
Table 1
Modelling results and monitoring data.
Personnel Effective dose received during re- Actual effective dose Ratio 𝑘𝑚𝑎𝑥
member No sponse, 𝑚𝑆𝑣 𝐷𝑒𝑓 𝑓 , 𝑚𝑆𝑣
1 6.9. . . 43.0 20.8(+-30%) 2.07
2 9.3. . . 57.6 24.2(+-30%) 2.38
3 11.4. . . 71.0 30.9(+-30%) 2.30
4 12.6. . . 78.7 36.2(+-30%) 2.17
The mass fraction of a radionuclide in the release relative to its original content in radioactive
liquid is commonly used in practice:
𝐴𝑤
𝑞= 𝐻𝑚𝑞 100%, (3)
𝑚0
where 𝑚0 – initial mass of LRM, 𝑘𝑔.
This value is used as an input parameter for the assessment of doses to the public from
atmospheric release.
2.3. Model testing
To confirm the effectiveness and accuracy of the modelling, a partial testing was performed
at an example of real event that occurred at the Pakistani nuclear power plant in Karachi in
2017: overexposure of 4 staff members as a result of the accident. Reconstruction of irradiation
doses was performed using the developed model and compared with the actual value of the
dose accumulated by the liquidators during the works (table 1, figure 4).
According to the results of testing, the following is highlighted: the actual data are included in
the calculated ranges of the effective dose, which is acceptable; the pessimistic estimate exceeded
the actual measurement data by ~2.0-2.3 times (ratio 𝑘𝑚𝑎𝑥 in table 1), which is acceptable; the
development can be used as a tool for the reconstruction of exposure doses. However, further
testing of the source term model are required.
2.4. Application of the model
Results of source term model can used as initial data to provide atmospheric dispersion mod-
elling results and dose projection for the hypothetical event associated with the spill of liquid
radioactive material. The example of such calculation in JRODOS system are shown in figures 5,
6.
Presented calculations were done using local scale model chain of JRODOS system. Total
amount of activity released into the atmosphere (primarily 60 𝐶𝑜 and 137 𝐶𝑠) has been assumed
about 2.5 𝐺𝐵𝑞. Hourly resulted source term was used as input data to provide the results on
near ground air concentration. Meteorological data in NetCDF format was provided as WRF
results with 0.05° spatial resolution and selected from previous several years numerical weather
312
Figure 4: Modelling results and monitoring data.
Figure 5: JRODOS atmospheric dispersion modelling results: air concentration near ground, time-
integrated using LASAT model (a), total aerosol deposition using DEPOM model (b).
data. All results of radioactive material spreading as well as dose assessment were performed
on the least calculation grid size 20 𝑘𝑚.
For selected hypothetical scenario, 1-year effective doses at 2.5 𝑘𝑚 (size of sanitary protection
zone around Ukrainian NPPs) do not exceed 3 𝜇𝑆𝑣 that is lower than established annual level
for public 40 𝜇𝑆𝑣. According to the results, on-site values for 137 𝐶𝑠 deposition can be around
1.5 𝐵𝑞/𝑚2 (dry weather). Ground contamination is foremost limited by the NPP site and near
range.
Practice of an application shows the source term model can serve as an useful tool to provide
initial data for radiological consequence calculations. However, it depends on context of
application and leave a place for further sensitivity analysis and model chains improvement.
313
Figure 6: JRODOS dose projection results 1-year effective dose from all exposure pathways except
ingestion (child).
2.5. Software for solving problems of emergency planning
In frame of FASTNET project experience of more than 20 countries was analyzed. The main
output of the project is an investigation in the area of qualitative characteristic of source term –
resolution in time. Taking into account spatial and temporal resolution of numerical weather
predictions used in Europe countries, FASTNET group recommend the use of 15-min intervals
in source term.
Practice of regular calculations demonstrates significant uncertainties in conjunction “source
term – NWP-data”. Under unstable meteorological condition with complex patterns of integrated
concentrations, using of more than 15-min. source term intervals can lead to crusual impact on
radiological consequences results.
Today JRODOS users can operate pre-estimated source terms data. Source term library filling
can be specified by requirements to source term files taking into account meteorology data
resolution.
Uncertainties of the source term on the prediction of atmospheric dispersion of released
radioactivity involve both the amounts of radionuclides released and the temporal evolution
of the release. Furthermore, the combined uncertainties of atmospheric dispersion model
forecasting stemming from both the source term and the meteorological data are examined in
[22].
In AVESOME project, a methodology is developed which can handle both a few-member
314
source-term ensemble and a large ensemble spanning all possible releases. The AVESOME
methodology will work well with the Rapid Source Term Prediction (RASTEP) system, which
provides a set of possible source terms with associated probabilities based on pre-calculated
source terms. The methods, which are being developed in AVESOME, allows for efficient real-
time calculations by making use of scaling properties in the equations governing the release and
the atmospheric dispersion of radionuclides. Accordingly, the computer-resource demanding
calculations should be carried out at the high-performance computing (HPC) facilities available
e.g. at national meteorological services, whereas less demanding post-processing should be
carried out at the computer hosting the DSS.
A protocol is suggested for interactive communication between the DSS and the HPC fa-
cility enabling the requests from the DSS user for long-range atmospheric dispersion model
calculations. It is based on an existing operational protocol extended with the capability of
simultaneous handling of a number of source-term descriptions, including a full source-term
ensemble.
Based on the results of the mathematical model with a view to further determination of
radiological impact on the workers, public and the environment the environment can be used
analytical methods and software tools:
• RODOS: ADM RIMPUFF with 10-min. time step + FDMT [12];
• RASCAL (INTERRAS) [11], HOTSPOT [7] ;
• ARGOS: complex terrain ADM, dose projection module (any other DSS);
• simplified gaussian models;
• sophisticated models for short range (CFD-, LES-modeling);
• NRC MACCS code (probabilistic tool) [15];
• GENII, RESRAD, PAVAN, ARCON 96, XOQDOQ (RAMP family) [13]; etc.
Worker’s exposure (internal) can be assessed using analytical base and methods (NRC, ICRP,
UNSCEAR [13]); dose conversion factors FGR-11/13, EPA [13]; analytic base of organization
such as NRC, EPA, ICRP, and skin dose assessment in VARSKIN code; MICROSHIELD, ISOCSR
to calculate dose from equipment and spill domain.
2.6. Features of future specialists training for nuclear energy industry
Experience of nuclear power units operating, the Chernobyl disaster, the tragic events at the
Fukushima-1 nuclear power plant indicated the need to pay attention to safety issues and adhere
to the principles of its culture at nuclear facilities. This can be achieved only with personnel
qualitative training for nuclear energy industry. Currently in Ukraine there are 9 institutions of
higher education that educate specialists for work in nuclear energy sector: National Technical
University of Ukraine “Igor Sikorsky Kyiv Polytechnic Institute”, Lviv Polytechnic National
University, National Technical University “Kharkiv Polytechnic Institute”, Odessa National
Polytechnic University, Taras Shevchenko National University of Kyiv, Vinnytsia National
Technical University, National University of Water and Environmental Engineering, Ukrainian
State University of Chemical Technology, Kyiv Energy College. RNPP Vocational School also
prepares specialists for work at nuclear power plants [35].
315
The Standard of Higher Education of Ukraine in the specialty 143 “Nuclear energy” [36] of
bachelor’s level was developed taking into account the needs of vocational education (approved
and put into effect by the Order of the Ministry of Education and Science of Ukraine No. 964 of
July 10, 2019). Also the National Technical University of Ukraine “Igor Sikorsky Kyiv Polytechnic
Institute” for the first time recruited for the master’s program “Physical Protection, Accounting
and Control of Nuclear Materials” in the specialty 143 “Nuclear energy” in 2019. Term of study
for Master degree is 1 year 6 months. Educational and professional training program meets
requirements of current national legislation and recommendations of the International Atomic
Energy Agency.
Students of specialty 143 “Nuclear Energy” have an opportunity to learn not only basics of
nuclear and information safety and design of physical protection systems. They are also able
to assess vulnerabilities and identify threats, develop regulations, prevent measures, manage
emergencies and crisis situations. Training is conducted by highly professional teaching staff,
including practitioners, specialists who completed internships at the University of Texas at
Austin, Sandia National Laboratories and participated in training courses at the International
Atomic Energy Agency. Also, students learn to operate nuclear power plants. They are engaged
in of neutron-physical modeling and thermohydraulic processes in NPP equipment. The students
solve problems of reliability and safety of NPPs. The graduates have exclusive right to obtain a
license to operate nuclear power plants. They can hold positions from NPP engineer to CEO or
work in other industry enterprises [35]. In February 2021, the first graduation of masters in
the specialty 143 “Nuclear Energy” took place. Of course, specialists at various specialties and
fields of knowledge (technical, chemical, ecological, biological, engineering) are required for
work at NPPs.
The Standard of higher education for the master’s level of knowledge 18 “Production and
technology” in the specialty 183 “Environmental technologies” determined that the main pur-
pose of training is: formation of professional competencies necessary for innovative research
and production activities for development and implementation of modern technologies for
environmental protection.
The publication authors analyzed the Standard of Higher Education for specialty 183 “En-
vironmental Protection Technologies” [37] and identified number of competencies of future
professionals to use specialized software for solution of emergency prevention problems during
spills of radioactive liquids. Also, the Standard of Higher Education for the master’s level in
the field of knowledge 12 “Information Technology”, specialty 122 “Computer science” [38]
was analyzed. Number of future professionals competencies to develop, maintain and improve
specialized software for solving problems of emergency prevention in case of spills of radioactive
liquids, they include (special (professional) competencies) were defined:
• specialty 183 “Environmental protection technologies”
K04. Ability to use modern computer and communication technologies during collection,
storage, processing, analysis and transmission of information about the state of
environment and industrial sphere;
K08. Ability to ensure environmental safety and sustainable development of society;
K09. Ability to use scientifically grounded methods in processing of research results in
the field of environmental protection technologies;
316
K11. Ability to create physical and mathematical models of processes occurring in man-
made pollution;
K14. Ability to assess impact of industrial facilities, their emissions and discharges on
the environment;
K16. Ability to monitor state of environmental safety and assess degree of air pollution
and industrial emissions into the atmosphere, water and water bodies, soils and
land resources;
K19. Ability to design systems and technologies for environmental protection and ensure
their functioning.
• specialty 122 “Computer science”
CK5. Ability to use mathematical methods for analysis of formalized models of subject
area of particular project of its implementation and maintenance process;
CK9. Ability to develop software: understand and apply logic basics to solve problems; be
able to design, execute and debug programs using modern integrated software (vi-
sual) development environments; understand programming methodologies, includ-
ing object-oriented, structured, procedural and functional programming; compare
currently available programming languages, software development methodologies
and development environments, as well as select and use those that correspond to
particular project; be able to evaluate code for reuse or inclusion in an existing li-
brary; be able to assess the configuration and impact on settings in terms of working
with third-party software packages;
CK11. Ability to develop and administer databases and knowledge, possess modern theories
and models of data and knowledge, methods of their interactive and automated
development, processing and visualization technologies;
CK12. Ability to assess quality of IT projects, computer and software systems for vari-
ous purposes, to possess methodologies, methods and technologies to ensure and
improve quality of IT projects, computer and software systems based on interna-
tional standards for quality assessment of information systems software, maturity
assessment models information and software systems development processes;
CK13. Ability to initiate and plan computer systems and software development processes,
including its development, analysis, testing, system integration, implementation
and maintenance;
CK14. Ability to identify problem situations during the software operation and formulate
tasks for its modification or reengineering.
Quality improving of education is one of the most important issues in development of any
society. The modern world is evolving and changing rapidly, information technologies are being
updated and improved. Therefore the domestic higher education system does not have time to
adapt curricula and plans to requirements of the market and society. This problem is relevant
in the field of training specialists in the following specialties: 183 “Environmental protection
technologies”, 103 “Earth sciences”, 122 “Computer science” [18] and in the new specialty 143
“Nuclear energy". Therefore, we believe that it is important to add topics for development of
317
mathematical and a software solution for emergency prevention in case of LRM spills in training
of future professionals in the outlined specialties.
The choice of used software in educational process should be based on the need to form
professional skills in students and graduate students. Also it is necessary to develop systematic
thinking, the ability to select optimal tool for solving particular application problem [18]. It will
greatly enrich their experience and allow them to understand specifics of LRM spills events
simulating. It is important in preventing emergencies.
The following measures should be taken to increase effectiveness of specialists training for
nuclear energy sector on issues of risk reduction during LRM spill incidents elimination:
• supplementing curricula of training students and graduate students to ensure acquisition
of competencies to reduce risks during elimination of incidents with LRM spills;
• to introduce study of issues: on development of mathematical models and software for
solving problems of emergency prevention during LRM spills;
• use of specialized software for solving problems of emergency prevention during LRM
spills;
• to expand topics of bachelor’s, master’s, dissertation works of students and scientific
degrees with problems on various aspects of the development of mathematical models
and software tools for solving problems of emergency prevention in case of LRM spills.
3. Conclusions
1. It is determined that the main criteria for the assessment of accidents at radiation-
hazardous facilities associated with the spill of radioactive liquids are: possible sources
of release, the range of chemical and isotopic composition of the radioactive liquid; tem-
peratures of radioactive liquids involved in heat and mass transfer processes; features of
drainage, filtering and localizing; potential scale and degree of radioactive contamination;
critical pathway and critical exposure group; characteristic conditions of on-site as well
as off-site spreading of radioactive substances.
2. Existing mathematical models of the distribution of radionuclides in the air as a result
of emissions cannot be used to solve the problem of estimating the radiation impact in
accidents with spills of radioactive liquids due to some set of disadvantages. The authors
of the publication developed a model that takes into account the physical features of
radioactive fluid leakage from the source, air pollution during the transition of radioactive
liquid from the spill surface into the air and their subsequent dispersion in the emergency
room under the influence of local air currents (caused by ventilation).
3. A mathematical model of radioactive substances transport in emergency areas has been
developed, which, unlike other models, takes into account the parameters of radioactive
liquids composition and design conditions of their storage.
4. Features of the software of the decision of problems of the prevention of emergencies
at flood of radioactive liquids are analyzed. It is determined that the existing software
tools for radiation exposure assessment do not comprehensively cover the features of
such events and have a number of shortcomings (do not take into account the process
318
of radioactive decay; inadequacy of the results and high uncertainties; do not allow to
obtain most of the dynamic parameters required for a comprehensive analysis of radiation
exposure, lack of models describing the transport of multicomponent radioactive air
mixtures) for modelling the course of accidents with spillage of radioactive liquids indoors.
5. The publication provides examples of computer simulation of atmospheric dispersion
and dose projection for a hypothetical event involving the spillage of liquid radioactive
material in the JRODOS system.
6. Process of future specialists training in the specialties: “Environmental protection tech-
nologies”, “Nuclear energy", “Earth sciences”, and “Computer science” should be based on
the use of powerful scientific and methodological training base using modern advances
in digital technology. Therefore, we consider it appropriate to supplement curricula for
preparation of students and graduate students in the outlined specialties by studying
issues of: development of mathematical models and software to solve problems of emer-
gency prevention in case of LRM spills; features of specialized software use to solve
problems of emergencies prevention during LRM spills. For this purpose, it is proposed to
use mathematical model of radioactive substances transport in emergency rooms devel-
oped by the authors and the corresponding software tools for assessing radiation impact
on population and environment.
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