2019-2 (31)

Nuclear, radiation and environmental safety

Article Name10.26583/GNS-2019-02-01
Validation of the Transport Packing Set Compatibility to Safety Requirements
AuthorsYu.Yu. Lushina*1, O.Yu. Zhabunina**2, N.Yu. Parshukova*3

* Snezhinsk Physics and Technology Institute of the National Research Nuclear University MEPhI,
Snezhinsk, Russia

** Federal State Unitary Enterprise «Russian Federal Nuclear Center – Zababakhin All-Russia Research Institute of Technical Physics», Snezhinsk, Russia

1ORCID: 0000-0002-3328-3989

Researcher ID:  W-3732-2017

e-mail: yulyaledy94@mail.ru

2ORCID: 0000-0001-9823-3651

e-mail: O.S.Putilin@vniitf.ru

3ORCID:  0000-0001-9872-8996

Researcher ID:  W-3192-2017

e-mail: p.i.e@yandex.ru

AbstractThe aim of the article is the computational validation of compatibility of the developed transport packing set (TPS) to normative safety requirements in the conditions of land transportation of used fuel assemblies (UFA). The safety of UFA transportation should be confirmed by TPS tightness preservation at emergency falling from height of 9 m on a horizontal surface and from height of 1 m on the pin with circular section. The mentioned tests are simulated by numerical calculations in the finite-element analysis program which shows that suggested TPS construction meets normative requirements.
Keywordssafety, transportation, used fuel assemblies, radioactive material, dangerous cargo, transport packing set, tightness, hermetic sealing system, container, case, finite-element analysis program, strength.



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Papers7 - 14
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Article Name10.26583/GNS-2019-02-02
Analysis of Existing Protection Systems from Buffer Overflow and Methods of their Bypass
AuthorsM.A. Parinov

 Institute of Nuclear Physics and Technology (INP&T), National Research Nuclear University «MEPhI», Kashirskoye shosse, 31, Moscow, Russia 115409

1ORCID iD: 0000-0002-6947-8753

WoS Researcher ID: G-9341-2019

e-mail: mafimka@gmail.com

AbstractThe issue of detecting and preventing attacks on applications has been and remains one of the urgent tasks of information security. Flaws in the program code lead to disruption of the normal operation of the software. Data integrity, availability and confidentiality of the data, interruption of the execution of running processes or even the system as a whole may occur due to design flaws. This paper discusses the mechanism of buffer overflow on a stack as well as existing modern means of detecting or preventing buffer overflows such as ASLR, StackGuard, and a non-executable stack. These security features are chosen as the research target because they are the most common and are built-in security features in Linux. The objective of the work is to analyze the problem of buffer overflow and the incomplete effectiveness of existing commonly used means of preventing and detecting this type of attack as well as a description of an alternative way to solve the problem of buffer overflow. As part of the work for each of the widespread means of protection considered a way to circumvent it. The result of this work was the conclusion that the existing security tools have significant drawbacks and therefore requires the development of an additional remedy, the idea of which is proposed at the end of the article.
Keywordsbuffer overflow, system calls, code injection, Data Execution Prevention, ASLR, StackGuard, information security.
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    (in English).
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  17. Dmitry Evtyushkin, Dmitry Ponomarev, Nael Abu-Ghazaleh. Jump Over ASLR: Attacking Branch Predictors to Bypass ASLR. URL: http://www.cs.ucr.edu/~nael/pubs/micro16.pdf.
Papers15 - 22
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 Open Article

Design, manufacturing and commissioning of nuclear industry equipment

Article Name10.26583/GNS-2019-02-03
Influence of Various Parameters on the Hollow Element Stability
AuthorsS.A. Rashchepkina

The Balakovo engineering and technological Institute – branch of the

National research nuclear University «MEPhI», 140 Chapaeva St., Balakovo, Saratov region, Russia, 413800

ORCID ID: 0000-0003-1136-4689

e-mail: SARashchepkina@mephi.ru

AbstractThe work studied core elements of the hollow cross-section created by a promising technology that does not require large energy costs. The change in the critical forces depending on its transverse dimensions is revealed based on the numerical analysis of the hollow element stability under central compression. It is found that the material of the rod element influences the critical stresses. The paper shows that the calculations of the hollow element stability are coherent with the experimental data on models.
Keywordsnuclear power plant, metal, hollow element, calculation, stability, experiment.
  1. E`nergosberezhenie na atomnom urovne [Energy Saving Technologies]. URL: http://www.saveplanet.su/#teh (in Russian).
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  5. Rashchepkina S.A. Novy`e prostranstvenny`e rebristy`e metallicheskie konstrukcii zdanij i sooruzhenij [New Spatial Ribbed Metal Structures of Buildings and Structures] Industrial and Civil Engineering. 2009. №7. ISSN 0869-7019. P. 48-50 (in Russian).
  6. Rashchepkina S.A. K voprosu ob ustojchivosti metallicheskoj cilindricheskoj obolochki iz sborny`x e`lementov [Stability of Steel Cylindrical Shell of Prefabricated Elements] Global Nuclear Security. Moscow-Volgodonsk : VETI NRNU «MEPhI». 2016. № 1 (18). ISSN 2305-414Х.
    P. 51-59 (in Russian).
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    (in Russian).
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Article Name10.26583/GNS-2019-02-04
Weld Pool Static Equilibrium in Butt Welds with Full Penetration
AuthorsA.M. Rybachuk*1, V.F. Cubarew**2, Yu.V. Doronin***3

*Bauman Moscow State Technical University, Build 1, Vtoraja Baumanskaya St., 5, Moscow, Russia 105005

1ORCID iD: 0000-0002-9078-2653

Wos Researcher ID: O-6229-2017

e-mail: amrybachuk@mail.ru

**National Research University «MPEI», Krasnokazarmennaya St., 14, Moscow, Russia 111250

2ORCID iD: 0000-0001-8493-8933

WoS Researcher ID: J-5424-2017

e-mail: kubarevvf@mail.ru

***LTD «Certification Center of municipal services»,

Office 36, Tkatskaya St., 46,Moscow, Russia 105187

3ORCID iD: 0000-0002-3294-882X

 WoS Researcher ID: O-6190-2017

e-mail: doronin-45@mail.ru

AbstractThe article deals with the influence of surface tension forces in one-sided arc welding of butt joints on weight. It shows analytically the possibility of holding the liquid metal of the weld pool when the thickness of the welded parts is from 10mm. and above.
Keywordsweld pool, pressure of the arc, surface tension liquid steel.
  1. Tyul`kov M.D. Rol` sil poverxnostnogo natyazheniya v formirovanii kornya sty`kovy`x shvov [The Role of Surface Tension Forces in the Formation of the Root of Butt Joints]. Leningrad. 1958.  Trudy` LPI im. M.I. Kalinina [Leningrad 1957. Proceedings of Kalinin LPI.]. № 189. P. 34-41
     (in Russian).
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  6. Razmyshlyaev A.D. Gidrodinamicheskie parametry` plenki zhidkogo metalla na perednej stenke kratera vanny` pri dugovoj svarke. Avtomaticheskaya svarka [Hydrodynamic Parameters of the Liquid Metal Film on the Front Wall of the Bath Crater during Arc Welding. Automatic Welding]. 1982. №1. P. 20-25 (in Russian).
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  10. S Yamana,T. Ishikava, T Nakajma Torch welding and feed-forward control of back bead in one-side backing less.V-groove welding by using back welding. Quarterly Journal of the Japan Welding society Vol.25. 2007. №1. P. 159-164 (in English).
  11. GU C., Rybachuk A.M. Deformaciya vneshnego magnitnogo polya pri dugovoj svarke magnitny`x metallov [Deformation of the External Magnetic Field in Arc Welding Magnetic Metal]. Global`naya yadernaya bezopasnost`  [Global Nuclear Safety]. 2017. № 4. P.7 (in Russian).


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Article Name10.26583/GNS-2019-02-05
Development of Methodical Recommendations to Improve Treatment Accuracy of Nuclear Engineering Products
AuthorsV.T. Saunkin1*, V.V. Krivin, N.G2*. Grigoriev3**, O.E. Draka4*


*Volgodonsk Engineering Technical Institute the branch of National Research Nuclear University «MEPhI»,

Lenin St., 73/94, Volgodonsk, Rostov region, Russia 347360

**«Atommash» the branch of «AEM-Technologies» JSC, Volgodonsk, Rostov region, Russia

1ORCID ID: 000-0002-3462-4853

Wos Researher ID: F-3352-2017

e-mail: saunkin@mail.ru

2ORCID ID: 0000-0003-0903-0786

Wos Researher ID: E-2267-2018

e-mail: krivin1949@mail.ru

3ORCID ID: 000-0002-5654-5021

Wos Researher ID: F-3370-2017

e-mail: grigoryev@mail.ru

4ORCID ID: 000-0002-3397-6830

Wos Researher ID: F-3316-2017

e-mail: oed17@mail.ru

AbstractThe paper deals with the problem of increasing the accuracy of the processing of nuclear engineering products. The calculations show that the main (significant) component of the processing error is the dynamic error, that is, in the conditions of the system. Experimental studies is confirmed this conclusion and shows that the main factor is the temperature deformation of the product during processing. The influence of this factor can be minimized by changing the parameters of the processing modes so the experimental dependencies can be used.
Keywordsnuclear power engineering products, product dimensional accuracy, product temperature deformation, processing, technological mode of product processing.
  1. Saunkin V.T., Onishhuk S.G., Miranczov S.L. Povy`shenie proizvoditel`nosti i tochnosti avtomaticheskogo kontrolya detalej [Improving Performance and Accuracy of Automatic Parts Control]. Bulletin of the Donbass State Machine-Building Academy. 2008. № 1 (11). P. 162-165
    (in Russian).
  2. Kovalevskij S.V., Onishhuk S.G., Saunkin V.T. Tipovy`e texnologicheskie processy` v tyazhelom mashinostroenii [Typical Technological Processes in Heavy Engineering]. Donbass State Machine-Building Academy. 2009. 124 p. (in Russian).
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  4. Saunkin V.T., Onishhuk S.G. Issledovanie pogreshnosti obrabotki detalej pri ispol`zovanii sredstv aktivnogo kontrolya [The Study of Accuracy of Machining Parts Using Active]. Bulletin of Ternopil State National Technical University. 2010. T.15. Issue. 4. P. 85-89 (in Russian).
  5. Saunkin V.T., Onishhuk S.G. Oshibki obrabotki detalej pri ispol`zovanii sredstv aktivnogo kontrolya [Parts Processing Errors when Using Means of Active Control. Reliability of Tool and Optimization of Technological Systems: a Collection of Scientific Papers]. Donbass State Engineering Academy. 2010. Vol. 27. P. 136-140 (in Russian).
  6. Kovalevskij S.V., Saunkin V.T., Voloshin O.N. Tipovy`e texnologicheskie processy` v tyazhelom mashinostroenii [Typical Technological Processes in Heavy Engineering]. Donbass State Machine-Building Academy. 2010. 116 p. (in Russian).
  7. Saunkin V.T., Onishhuk S.G. Issledovanie pogreshnosti obrabotki detalej pri ispol`zovanii sredstv aktivnogo kontrolya [The study of Accuracy of Machining Parts Using Active Control]. Bulletin of the Azov National Technical University. 2011. Vol. 22. P. 189-192 (in Russian).
  8. Kovalevskij S.V., Onishhuk S.G., Saunkin V.T. Texnologii v oblasti tyazhelogo mashinostroeniya – processov i upravleniya [Technologies in the Field of Heavy Engineering - Processes and Management]. Vrnjacka, Banja: SATCIP, 2011. 350 p. (in Russian).
  9. Saunkin V.T., Grigor`ev N.P., Draka O.E. Razrabotka metodicheskix rekomendacij ocenki perexodnogo processa pri mexanoobrabotke krupnogabaritny`x izdelij [Development of Guidelines for Assessing the Transition Process during the Machining of Large-Sized Products]. Global`naya yadernaya bezopasnost`. [Global Nuclear Safety]. 2017.  № 1 (22).  P. 54-58 (in Russian).
  10. Sovietov, B.Ya., Yakovlev S.A. Modelirovanie sistem [System Modeling]. Moscow. Higher school. 2005. 343 p. (in Russian).
Papers39 - 46
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Article Name10.26583/GNS-2019-02-06
Study of the Impact of Hydraulic Rolling Technology on the Condition of Press Connections
AuthorsA.M. Smirnov*1, V.V. Shishov**2

*Institute of Nuclear Physics and Technology (INP&T), National Research Nuclear University «MEPhI»,

Kashirskoye shosse, 31, Moscow, Russia 115409

e-mail: v.terehov@eatom.ru

** Experienced Design Office «GIDROPRESS», Ordzhonikidze st., 21, Podol'sk, Russia 142103

2 e-mail: v.shishov@eatom.ru

AbstractThe problem of the failure of steam generator collectors is actualized and its causes are revealed, one of which is the use of irrational technological processes of fixing heat exchanging pipes to tube sheets. The results of the study of the hydraulic rolling technology influence on the state of press joints are given which allowed to analyze the existing technology and determine reliable criteria to assess the quality of the pipe-tube-board connections.
Keywordspress connection, heat exchange tubes, collector, hydraulic rolling, clearance, tension
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  2. Kondratenko L.A. Raschetno-ehksperimental'nye metody issledovaniya tekhnologicheskih napryazhenij i deformacij v neraz"emnyh trubnyh soedineniyah ehnergoustanovok: avtoref. dokt. tekhn. nauk [Computational and Experimental Methods for Studying Technological Stresses and Deformations in Permanent Pipe Joints of Power Plants: Thesis abstract]. Moscow. 2017
    (in Russian).
  3. Ovseenko A.I. Poverhnostnyj sloj detalej: problemy tekhnologicheskogo obespecheniya kachestva. Sbornik materialov: Vliyanie tekhnologii na sostoyanie poverhnostnogo sloya [Surface Layer Details: the Problems of Technological Quality Assurance]. Poznan'. 2002. P. 411-415.
  4. Kondratenko L.A., Mironova L.I. K voprosu ob uprochnenii materiala val'covochnyh soedinenij v teploobmennyh apparatah [Hardening of Material of Milling Connections in Heatexchange Devices]. Engineering & Automation Problems. 2016 №. 3. Р. 106-112 (in Russian).
  5. Kondratenko L.A., Terekhov V.M., Mironova L.I. K voprosu o vliyanii dinamiki rolikovogo val'cevaniya na kachestvo izgotovleniya teploobmennyh apparatov v atomnyh ehnergeticheskih ustanovkah [Effect of Roller Rolling Dynamics on the Quality of Manufacture of Heat Exchangers of Nuclear Power Units]. Heavy engineering construсtion. 2016. № 3. Р. 10-14 (in Russian).
  6. Kondratenko L.A., Terekhov V.M., Mironova L.I. Analiz nekotoryh problem mekhanicheskogo zakrepleniya teploobmennyh bimetallicheskih trub v ehnergeticheskih ustanovkah [Analysis of Some Problems of Mechanical Fastening of Heat Exchange Bimetallic Tubes in Energy Apparatus]. Engineering & Automation Problems. 2017. № 3. Р. 83-88 (in Russian).
  7. Terekhov V.M., Kondratenko L.A. Matematicheskaya model' processa zakrepleniya teploobmennyh trub posredstvom gidrorazdachi [Mathematical Model of the Process of Fixing the Heat Exchange Tubes by Means of Hydraulic Distribution]. Engineering technology. 2001. № 1. P. 55-57
    (in Russian).
  8. Kondratenko L.A., Terekhov V.M., Vinnikov V.S., Averin A.S. Tekhnologicheskie vozmozhnosti teploobmennyh trub v operacii zakrepleniya [Technological Capabilities of Heat Exchange Tubes in the Operation of Fixing]. Engineering technology. 2014. № 7. P. 28-33 (in Russian).
  9. Smirnov A.M., Mironova L.I., Terekhov V.M., Kondratenko L.A. Issledovanie sostoyaniya poverhnostnogo sloya teploobmennyh trub iz vysokolegirovannyh stalej austenitnogo klassa [Investigation of the State of the Surface Layer of Heat Exchange Tubes of High-Alloyed Austenitic Steels]. Proceedings of the St. Moscow IMASH RAN. Moscow IMASH RAN. 2018. Vol. 1. P. 814-818 (in Russian).
  10. Smirnov A.M., Terekhov V.M., Averin A.S. Osobennosti tekhnologii razdachi teploobmennyh trub dostatochnoj tolshchiny i ocenka kachestva pressovyh soedinenij [Features of Technology of Radial Deformation of Heat-Exchanging Pipes of Sufficient Thickness and Assessment of Quality of Press Connections]. Engineering & Automation Problems. 2019. № 1. P. 150-155 (in Russian).
Papers47 - 58
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Article Name10.26583/GNS-2019-02-07
Method of Heat-Hydraulic Tests of Long-Relined Pipes of Separator – Vapor Heaters for NPP with Water-Water Energy Reactors
AuthorsM.YU. Khizhov

OA OKB «GIDROPRESS», Podol'sk, Russia

e-mail: grpress@grpress.podolsk.ru

AbstractThe paper proposes methodology and design of the stand which allowed to conduct thermal tests of longitudinally-finned tubes of separators-superheaters for nuclear power plants with water-water power reactors of high efficiency. According to the results of tests of longitudinally ribbed pipes with the number of U-shaped ribs equal to six and eight, a comparative analysis is conducted. It is shown that the increase in heat transfer surface exceeds the decrease in heat transfer coefficient for such structures.
Keywordsheat exchange tubes, separator-superheater, thermal hydraulic tests, heat transfer coefficient, heat exchange surface.
  1. Smirnov A.M., Hizhov M.YU., Leksikov V.I. Ocenka kachestva orebrennyh teploobmennyh trub separatora-paroperegrevatelya [Estimation of Quality of Heat Exchange Pipes with External Ribs for the Separator-Superheater]. Engineering & Automation Problems. 2018. №. 4. P. 135-141
    (in Russian).
  2. Kondratenko L.A., Terekhov V.M., Mironova L.I. K voprosu o vliyanii dinamiki rolikovogo val'cevaniya na kachestvo izgotovleniya teploobmennyh apparatov v atomnyh ehnergeticheskih ustanovkah [Effect of the Dynamics of the Rolling on the Quality of Manufacture of Heat Exchangers of Nuclear Power Units] Heavy engineering construсtion. 2016. № 3. P. 10-14
    (in Russian).
  3. Smirnov A.M., Terekhov V.M., Averin A.S. Osobennosti tekhnologii razdachi teploobmennyh trub dostatochnoj tolshchiny i ocenka kachestva pressovyh soedinenij [Features of Radial Deformation Technology of Heat-Exchanging Pipes of Sufficient Thickness and Assessment of Quality of Press Connections]. Engineering & Automation Problems. 2019. №. 1. P. 150-155 (in Russian).
  4. Otchyot NIOKR №EHCR-0613. Teplogidravlicheskie ispytaniya prodol'no-orebrennyh trub paroperegrevatelya SPP-1000-1 [Report NIOKR №EHCR-0613. Thermohydraulic Testing of Longitudinally Finned Tubes of the SPP-1000-1 Superheater]. Podol'sk. PAO «ZiO-Podol'sk». 2017. 51 p. (in Russian).
  5. Aver'yanov I.D., Bakin A.I., Bogdanov V.V., Burov V.K. EHksperimental'nye issledovaniya teploobmena i aehrodinamiki shtatnoj kassety iz rebristyh trub separatora-paroperegrevatelya SPP-220M. [Experimental Studies of Heat Transfer and Aerodynamics of a Standard Cassette Made of Finned Tubes of a SPP-220M Separator-Superheater] Otchyot NIOKR №FR 00698. Podol'sk. PAO «ZiO-Podol'sk». 2017. 74 p. (in Russian).
  6. Gorobec V.G. Sravnitel'nyj analiz teplootdachi i gidravlicheskogo soprotivleniya puchkov trub s orebreniem razmennogo tipa [Comparative Analysis of Heat Transfer and Hydraulic Resistance of Bundles of Tubes with Barreled Fins]. Proceedings of the St. Moscow. Moscow Power Engineering Institute. 2006. P. 182-186 (in Russian).
  7. Separatory – paroperegrevateli turbin AEHS. Raschyot i proektirovanie. RTM 108.020.107-84 [Separators - Steam Superheaters of NPP Turbines. Calculation and Design. RTM 108.020.107-84]. Leningrad : CKTI. 1986. 15 p. (in Russian).
  8. Legkostupova V.V. Raschyotnoe obosnovanie modernizacii separatorov-paroperegrevatelej ehnergoblokov AEHS : – diss. kand. tekhn. nauk. [Estimated Justification for the Modernization of Separators-Superheaters of NPP Power Units]. St. Petersburg. OAO «NPO CKTI». 2018. 172 p.
    (in Russian).
  9. Terekhov V.M. Tekhnologicheskie osnovy obespecheniya kachestva glubokih otverstij i soedinenij teploobmennyh trub s trubnymi reshetkami i kollektorami apparatov atomnyh ehnergoustanovok: dis. dokt. tekhn. nauk [Technological Basis for Quality Assurance of Deep Holes and Heat Exchanger Tube Connections with Tube Sheets and Collectors of Nuclear Power Plants. Thesis]. Moscow. 2006 (in Russian).
  10. Kondratenko L.A. Raschetno-ehksperimental'nye metody issledovaniya tekhnologicheskih napryazhenij i deformacij v neraz"emnyh trubnyh soedineniyah ehnergoustanovok: avtoref. dokt. tekhn. nauk [Computational and Experimental Methods for Studying Technological Stresses and Deformations in Permanent Pipe Joints of Power Plants: Thesis abstract]. Moscow. 2017
    (in Russian).
Papers59 - 67
URL ArticleURL Article
 Open Article

Operation of nuclear industry facilities

Article Name10.26583/GNS-2019-02-08
Possibilities of Logistics in Ensuring Efficiency and Radiation Safety of Production Process of Nuclear Power Stations Unit Decommissioning
AuthorsA.I. Berela1, S.A. Tomilin2, A.G.Fedotov3

Volgodonsk Engineering Technical Institute the branch of National Research Nuclear University “MEPhI”,

Lenin St., 73/94, Volgodonsk, Rostov region, Russia 347360

1e-mail: berelaleks@yandex.ru

2ORCID ID: 0000-0001-8661-8386

Wos Researher ID: G-3465-2017

e-mail: SATomilin@mephi.ru

3e-mail: AGFedotov@mephi.ru

AbstractThe paper considers the possibilities of applying logistics in the design and implementation of the decommissioning process of nuclear power plant units to improve the efficiency and safety of design and practical solutions for managing material and information flows.
Keywordsdecommissioning, nuclear power plant unit, logistics, production process efficiency, radiation safety.
  1. Berela A.I., Fedotov A.G., Tomilin S.A., By`lkin B.K.  Razrabotka texnologicheskix processov demontazha oborudovaniya pri vy`vode iz e`kspluatacii atomny`x stancij [Development of Technological Processes for Dismantling Equipment during Decommissioning of Nuclear Power Plants]. Inzhenerny`j vestnik Dona [Engineering Herald of the Don]. 2013. №2 (25). URL: ivdon.ru/ru/magazine/archive/n2y2013/1734 (in Russian).
  2. Tomilin S.A., Berela A.I., Podrezov N.N., Fedotov A.G. Osobennosti proektirovaniya demontazha oborudovaniya blokov atomny`x stancij s uchetom normativnogo regulirovaniya ix vy`voda iz e`kspluatacii [Features of the Design of Dismantling the Equipment of Nuclear Power Units, Taking into Account the Regulation of their Decommissioning]. Global`naya yadernaya bezopasnost`[Global Nuclear Safety].  2017. № 1(22). P. 59-67 (in Russian).
  3. Berela A.I., Tomilin S.A., Fedotov A.G. Postanovka zadach proektirovaniya texnologicheskix processov demontazha osnovnogo oborudovaniya pri vy`vode iz e`kspluatacii blokov AE`S s korpusny`mi reaktorami [Setting the Tasks of Designing Technological Processes for Dismantling the Main Equipment during Decommissioning of NPP Units with Tank Reactors]. V sbornike trudov nauchno-prakticheskoj konferencii BITI NIYaU MIFI: «E`nergoe`ffektivnost` i e`nergosberezhenie» [Energy Efficiency and Energy Saving]. 2016. P. 8-11 (in Russian).
  4. SP Sanitarny`e pravila «Obespechenie radiacionnoj bezopasnosti pri vy`vode iz e`kspluatacii bloka atomnoj stancii» [Sanitary rules «Ensuring radiation safety during decommissioning of a nuclear power plant unit»]. Moscow. 2007 (in Russian).
  5. NP-012-16. Federal`ny`e normy` i pravila v oblasti ispol`zovaniya atomnoj e`nergii «Pravila obespecheniya bezopasnosti pri vy`vode iz e`kspluatacii bloka atomnoj stancii» [Federal Rules and Regulations in the Field of Atomic Energy Use «Rules for Ensuring Safety during Decommissioning of a Nuclear Power Plant Unit»]. Moscow : Federal`naya sluzhba po e`kologicheskomu, texnicheskomu i atomnomu nadzoru [Federal Service for Environmental, Technical and Nuclear Supervision]. 2016 (in Russian).
  6. Berela A.I., By`lkin B.K., Tomilin S.A., Fedotov A.G. Analiz i predstavlenie sredy` dejstviya v sisteme proektirovaniya texnologii demontazha oborudovaniya pri vy`vode iz e`kspluatacii bloka AE`S [Analysis and Representation of the Environment of Action in the Design System of Equipment Dismantling Equipment during Decommissioning of the NPP Unit]. Global`naya yadernaya bezopasnost`[Global Nuclear Safety]. 2014. № 1(10). P. 25-31(in Russian).
  7. Berela A.I., By`lkin B.K., Tomilin S.A., Fedotov A.G Adaptaciya texnologii demontazha oborudovaniya vy`vodimy`x iz e`kspluatacii blokov AE`S k trebovaniyam radiacionnoj bezopasnosti [Adaptation of the Technology of Dismantling the Equipment of Decommissioned NPP Units to the Requirements of Radiation Safety]. Inzhenerny`j vestnik Dona [Engineering Herald of the Don]. 2014.  №2 (29). URL: ivdon.ru/magazine/archive/n2y2014/2416 (in Russian).
  8. Berela A.I., Tomilin S.A., Fedotov A.G. Realizaciya procedur obespecheniya radiacionnoj bezopasnosti v texnologicheskix processax demontazha oborudovaniya pri vy`vode blokov AE`S iz e`kspluatacii [Implementation of Procedures for Ensuring Radiation Safety in Technological Processes of Dismantling Equipment when Decommissioning NPP Units]. Inzhenerny`j vestnik Dona [Engineering Herald of the Don]  (in Russian).
  9. Berela A.I., Fedotov A.G., Tomilin S.A. Texnologicheskoe oborudovanie, primenyaemoe v rabotax po vy`vodu iz e`kspluatacii blokov AE`S [Technological Equipment Used in the Decommissioning of NPP Units]. Global`naya yadernaya bezopasnost`[Global Nuclear Safety]. 2013. № 1(6). P. 58-66 (in Russian).
  10. Berela A.I., By`lkin B.K., Tomilin S.A., Fedotov A.G. Vy`bor znachenij parametrov texnologicheskogo processa demontazha oborudovaniya blokov AE`S, vy`vodimy`x iz e`kspluatacii [The Choice of the Values ​​of the Parameters of the Technological Process of Dismantling the Equipment of NPP Units Decommissioned]. Global`naya yadernaya bezopasnost` [Global Nuclear Safety]. 2013. № 3(8). P. 60-64 (in Russian).
  11. Berela A.I., By`lkin B.K., Shaposhnikov V.A. Optimizacionny`e aspekty` proektirovaniya texnologicheskogo processa demontazha oborudovaniya pri vy`vode iz e`kspluatacii bloka atomnoj stancii [Optimization Aspects of the Design Process of Dismantling Equipment during Decommissioning of a Nuclear Power Plant Unit]. Tyazheloe mashinostroenie [Heavy Engineering]. 2004. №6. P. 9-14 (in Russian).
  12. Berela A.I., Tomilin S.A., Fedotov A.G.  Osnovny`e principy` razrabotki konkurentosposobny`x proektov demontazhny`x rabot pri vy`vode iz e`kspluatacii blokov atomny`x stancij [Basic Principles for the Development of Competitive Dismantling Projects during Decommissioning of Nuclear Power Units]. Izvestiya Moskovskogo gosudarstvennogo texnicheskogo universiteta MAMI [News of Moscow State Technical University MAMI]. 2015. Т.5. № 4 (26). P. 191-195
     (in Russian).
  13. Gadzhinskij, A.M. Logistika: Ucheb. [Logistics: Textbook]. Moscow : Izdatel`sko-torgovaya korporaciya «Dashkov i Kº» [Dashkov and Kº Publishing and Trade Corporation]. 2009. 484 p.
    (in Russian).
  14. Ivanov M.Yu., Ivanova. Logistika: Ucheb. posobie [Logistics: Textbook manual]. Moscow : RIOR (in Russian).
Papers68 - 75
URL ArticleURL Article
 Open Article
Article Name10.26583/GNS-2019-02-09
Interactive Album of Neutron-Physical Characteristics of WWER Reactor Fuel Column
AuthorsA.A.Lapkis 1, V.A.Ignatkin2, M.A.Kolomietz 3

Volgodonsk Engineering Technical Institute the branch of National Research Nuclear University «MEPhI»,

Lenin St., 73/94, Volgodonsk, Rostov region, Russia 347360

1ORCID ID: 0000-0002-9431-7046

e-mail: aalapkis@mephi.ru

2ORCID ID: 0000-0002-1759-5675

3ORCID ID: 0000-0002-0027-4306


AbstractThe paper describes the method and software developed by the authors for automating operational calculations of reactivity changes of the WWER-1000 reactor. The main calculation dependencies, screen forms and test results are given. Rising of the calculation accuracy is shown. The development path of the developed software as an element of the digital twin of the WWER 1000 nuclear reactor is proposed.
KeywordsWWER-1000, reactivity, fuel loading, reactivity effects, reactivity coefficients, control rod, rod bank, neutron-physical characteristics.
  1. Sistema PRIS MAGATE` [The IAEA PRIS System]. Resurs MAGATE` PRIS posvyashhenny`j opy`tu e`kspluatacii AE`S v mire [The IAEA PRIS Resource Dedicated to the Experience of Operating Nuclear Power Plants in the World]. URL :  https://www.iaea.org/PRIS/ (in Russian).
  2. NP-082-07 «Pravila yadernoj bezopasnosti reaktorny`x ustanovok atomny`x stancij» [Nuclear Safety Regulations for Nuclear Installations at Nuclear Installations] (in Russian).
  3. Belozerov V.I., Zhuk M.M., Kuzina Yu.A., Ternovy`x M.Yu.. Fizika i e`kspluatacionny`e rezhimy` reaktora VVE`R-1000 [Physics and Operating Conditions of the WWER-1000 Reactor]. Monograph. Moscow: National Research Nuclear University MEPHI. 2014. 288 p. (in Russian).
  4. RD E`O «Trebovaniya k soderzhaniyu al`boma nejtronno-fizicheskix xarakteristik toplivny`x zagruzok reaktorov VVE`R 1000 i VVE`R-1200» [Requirements for the Content of the Album of Neutron-Physical Characteristics of the Fuel Column of WWER 1000 and WWER -1200 Reactors] (in Russian).
  5. Rosatom vy`straivaet edinuyu cifrovuyu strategiyu razvitiya atomnoj otrasli [Rosatom is Building a Unified Digital Strategy for the Nuclear Industry Development] The site of Rosatom State Corporation. URL : https://www.rosatom.ru/journalist/news/rosatom-vystraivaet-edinuyu-tsifrovuyu-strategiyu-razvitiya-atomnoy-otrasli (in Russian).
  6. Kalugin, M.A. Razvitie precizionny`x i inzhenerny`x metodov i programm rascheta yaderny`x reaktorov s ispol`zovaniem algoritmov Monte-Karlo : dis. dokt. tex. nauk: 05.13.18  [Development of Precision and Engineering Methods and Programs for Calculating Nuclear Reactors Using Monte-Carlo Algorithms: Thesis of Dr. in Engineering: 05.13.18]. Moscow. 2009. 295 p.
    (in Russian).
  7. Mitenkova E.F., Kizub P.A., Koltashev D.A. Analiz nejtronno-fizicheskix xarakteristik v yacheechny`x raschetax reaktora VVE`R s ispol`zovaniem kodov MCNP5 i MCU_FREE [Analysis of Neutron-Physical Characteristics in Cell Calculations of a WWER Reactor Using the MCNP5 and MCU_FREE codes] Preprint. Instute of Problems of Nuclear Energy Security Development RAS. IBRAE-2013-04.  Moscow: IBRAE RAS. 2013. 23 p. (in Russian).
  8. Kurchenokov A.Yu., Bol`shagin S.N. Programma TVS-M. Opisanie algoritma i instrukciya dlya pol`zovatelej [TVS-M program Description of the Algorithm and Instructions for Users]. Report of RRC KI. inv. № 32/1-18-203. 21.04.2003. Moscow. 2003 (in Russian).
  9. Tomilov M.Yu., By`chkova N.A., Kosourov E.K.. Kompleks programm KASKAD. Instrukciya po ispol`zovaniyu graficheskogo interfejsa kompleksa KASKAD [Complex Programs CASCADE. Instructions for Using the Graphic Interface of the CASCADE Complex] Report of the RRC KI. inv. № 32/1-51-402. 28.11.2002. 2002 (in Russian).
  10. Dobrotvorskij, A.N. Razrabotka i obosnovanie metodiki opredeleniya srednevzveshennoj moshhnosti reaktora e`nergoblokov AE`S s VVE`R-1000 : dis. kand. texn. nauk : 05.14.03[Development and Substantiation of the Methodology for Determining the Weighted Average Power of the NPP units with WWER -1000 Reactor:Abstract Thesis of PhD in Engineering]. Novovoronezh. 2017. 190 p. (in Russian).
  11. Amosov A.A., Dubinskij Yu.A., Kopchenova N.V.  Vy`chislitel`ny`e metody` dlya inzhenerov: Ucheb. Posobie [Computational Methods for Engineers: Proc. Manual]. Moscow: Higher School 1994. 544 p. (in Russian).
  12. Semyonov V.K., Vol`man M.A. Ocenka tochnosti metoda opredeleniya koe`fficientov reaktivnosti i e`ffektivnosti tverdy`x poglotitelej na osnove resheniya obratnoj zadachi dinamiki tochechnogo reaktora [Accuracy Estimation of the Method for Determining the Reactivity Coefficients and Efficiency of Solid Absorbers Based on the Solution of the Inverse Problem of the Point Reactor Dynamics] // Global nuclear safety. 2018. №3. P. 64-72 (in Russian).
Papers76 - 85
URL ArticleURL Article
 Open Article
Article Name10.26583/GNS-2019-02-10
Metrological Tests of Measuring Subsystems
AuthorsE.I. Cvetkov*1, Yu.P. Mucha**2, I.Y. Koroleva**3, A.D. Korolev**4

*State Electrotechnical University (LETI), St. Petersburg, Russia, post office box 654 (Information-measuring systems and technologies, Russia, 197046, St. Petersburg, PO Box 654)

1ORCID ID: 0000-0001-8733-713X

Wos Researher ID: O-4592-2019

e-mail: er-cvetkov@mail.ru

**Volgograd State Technical University, etc. to them. Lenin, 28, (8442) Volgograd, Russia 400005

2ORCID ID: 0000-0003-0919-5732

Wos Researher ID: M-4084-2015

e-mail: muxaup@mail.ru

3ORCID ID: 0000-0002-9185-6976

Wos Researher ID: N-4037-2015

e-mail: artmd64@rambler.ru

4ORCID ID: 0000-0003-2175-2204

Wos Researher ID: G-21091-2017

e-mail: artmd64@mail.ru

AbstractDevelopment of measuring technologies creates the corresponding problems when carrying out metrological tests. In particular, the need for taking note of the used interface on properties of errors of results of measurements appears. Emergence of errors of dating is a consequence of more and more wide circulation of multipurpose measuring means generates requirement of development of the corresponding procedures of the metrological analysis, including metrological tests. Therefore, the problem of improvement of metrological tests of measuring systems in general and their subsystems is relevant. The scientific novelty consists in development of an algorithm of tests and a conclusion of the estimated ratios connected with definition of probabilistic characteristics of the corresponding errors. The practical importance consists in development of the block diagram of a test experiment. Innovative value consists in a possibility of synthesis of test techniques for certification of the measuring subsystems and measuring systems in general considering dating errors within shift errors.
Keywordsmeasuring technology, metrological tests, metrological analysis, measurement error, the error of dating, complex measuring system, measuring subsystem, probabilistic characteristic of an error, metrological reliability, flexible intelligent interface.
  1. Mucha Y.P., Cvetkov E.I., Koroleva I.Y., Korolev A.D. Osebennosti korrekcii pogreshnosti datirovaniya [Features of correction of errors of dating] [Telecommunications]. 2018. № 4. P. 32-39 (in Russian).
  2. Mucha Y.P., Cvetkov E.I., Koroleva I.Y., Korolev A.D. Pogreshnosti datirovaniya telekommunikaktsionnih sistem izmereniya [Errors of Dating of Telecommunication Systems of Measurement] [Telecommunications]. 2017. № 6. P. 43-48 (in Russian).
  3. Mucha Y.P., Korolev A.D. Svidetelstvo o gosudarstvennoi registracii programmi dlya EVM № 2016616056 ot 3 iunya 2016. Gibkii intellektualnii interfeis [Certificate on the State Registration of the Computer Program № 2016616056, June 3, 2016, Russian Federation. Flexible Intellectual Interface] Volgograd State Technical University. 2016 (in Russian).
  4. Mucha Y.P., Cvetkov E.I., Koroleva I.Y. Pogreshnost datirovaniya (sdviga) rezultatov izmerenii i svyaz s kharakteristikami interfeisa [Error of Dating (Shift) of Results of Measurements and its Communication with Characteristics of the Interface] [Global Nuclear Safety]. 2016. №2 (19).
     P. 50-58 (in Russian).
  5. Mucha Y.P., Koroleva I.Y., Korolev A.D. Sintez algoritma upravleniya GII dlya sistem tekhnicheskogo zreniya [Synthesis of a Control Algorithm of GII for the Systems of Technical Sight] [Telecommunications]. 2016. № 1. P. 7-12 (in Russian).
  6. Mucha Y.P., Koroleva I.Y., Korolev A.D. Gibkii itellektulnii interfeis dlya system peredachi medicinskoi informacii [The Flexible Intelligent Interface for Transmission Systems of medical Information] [Prospero]. 2015. № 5 (17). P. 59-61(in Russian).
  7. Mucha Y.P., Korolev A.D. Razrabotka gibkogo interfejsnogo bloka na baze GHI G-400D [Development of the Flexible Interface Block on the Basis of GHI G-400D.]. Optiko-e`lektronny`e pribory` i ustrojstva v sistemax raspoznavaniya obrazov, obrabotki izobrazhenij i simvol`noj informacii. Raspoznavanie : materialy` XII mezhdunar. nauch.-texn. konf. Yugo-Zapadny`j gos. un-t [Optical-Electronic Devices and Devices in the Systems of Recognition of Images, Processings of Images and Symbolical Information. Recognition XII International Scientifically Technical Conference. Kursk. Southwest state university]. Kursk. 12-16 may 2015. P. 269-270 (in Russian).
  8. Cvetkov E.I. Osnovi matematicheskoi metrologii [Fundamentals of Mathematical Metrology].
    St. Petersburg. Politekhnika. 2005. 510 p. (in Russian).
  9. Cvetkov E.I. Metrologiya. Modeli. Metrologicheskii analiz. Metrologicheskii sintez. [Metrology. Models. Metrological Analysis. Metrological Synthesis]. St. Petersburg State Electrotechnical University. 2014. 293 p. (in Russian).
  10. Cvetkov E.I. Metrologicheskie ispitaniya bez primeneniya etalonov [Metrological Tests without Application of Standards] [World of Measurements]. 2016. P.12-18 (in Russian).
  11. Bobrova M.N., Suloeva E.S., Careva A.V., Cvetkov E.I. Metrologicheskie ispy`taniya sredstv izmerenij veroyatnostny`x xarakteristik sluchajny`x processov [Metrological Tests of Measuring Instruments of Probabilistic Characteristics Of Accidental Processes]. Materialy` XXI Mezhdunarodnoj konferencii po myagkim vy`chisleniyam i izmereniyam. LE`TI [ХХI International Conference on Soft Calculations and Measurements. St. Petersburg State Electrotechnical University]. St. Petersburg. 23-25 may 2018. Vol.1. P.62-65 (in Russian).
Papers86 - 92
URL ArticleURL Article
 Open Article
Article Name10.26583/GNS-2019-02-11
Monitoring of Berth-Calibrator Geometrical Parameters of Fuel Assembly at Nuclear Power Stations
AuthorsY.I. Pimshin*1, G.A. Naumenko**2, Yu.A. Psarev**3


*Volgodonsk Engineering Technical Institute the branch of National Research Nuclear University “MEPhI”,

Lenin St., 73/94, Volgodonsk, Rostov region, Russia 347360

1ORCID: 0000-0001-6610-8725

WoS ResearcherID: J-6791-2017

e-mail: YIPimshin@mephi.ru

**Don State Technical University, Gagarin square 1, Rostov-on-Don, Russia 344000

2ORCID: 0000-0002-7512-4687

WoSResearcherID: J-7170-2017

e-mail: galishka@mail.ru

3ORCID iD: 0000-0002-8609-3687

WoS Researcher ID: P-2357-20

e-mail: psarev161@gmail.com

AbstractThe paper considers the methods of monitoring the geometric parameters of the berth-calibrator of fuel assemblies (FA) used in the WWER-1000 reactor to form a controlled nuclear reaction and to obtain thermal energy. Variants of technology monitoring are implemented under the assumption of fuel assemblies for their installation in the reactor at the stage of the nuclear power plant installation and its operation.
Keywordsnuclear power plant, fuel assembly, control measurements, alignment, location, measurement error, measuring instrument.
  1. Pat. 2242713. Rossijskaya Federaciya. Avtomatizirovanny`j stend kontrolya pryamolinejnosti podvesok [Pat. 2242713 Russian Federation. Automated Stand for Control of Suspension Straightness]. Xoroshilov V.S. Publ. 27.12.2001. Byul. № 36 (in Russian).
  2. Pimshin Yu.I., Burdakov S.M., Naumenko G.A., Psaryov Yu.A. Konturny`e postroeniya pri kontrole geometricheskix parametrov soosnosti e`lementov texnologicheskogo oborudovaniya [Contour Construction in the Geometric Parameters Control of the Alignment of Technological Equipment Elements] Global`naya yadernaya bezopasnost`. [Global nuclear safety]. 2018.
    № 4 (29). P. 40 (in Russian).
  3. Pimshin Yu.I., Sharov V.N., Gluxov V.P. Kontrol` geometrii stapelya (kalibratora teplovy`delyayushhix sborok) [Inspection of The Berth (Fuel Assembly Calibrator) Geometry]. Prikladnaya geodeziya. Rost. Gos. Stroj. Un-t. Rostov-na-Donu [Applied Geodesy. RSSU.Rostov-on-Don], 1999. Р. 5-14. Dep VINITI 7.04.99, №1058-V99
    (in Russian).
  4. GOST 25346-2013 (ISO 286-1:2010). Mezhgosudarstvenny`j standart. Osnovny`e normy` vzaimozamenyaemosti. Xarakteristiki izdelij geometricheskie. Sistema dopuskov na linejny`e razmery`. Osnovny`e polozheniya, dopuski, otkloneniya i posadki. (vveden v dejstvie Prikazom Rosstandarta ot 18.02.2014 N 28-st). [Interstate Standard. Basic Standards of Interchangeability. Geometric Product Characteristics. Linear Tolerance System. The Main Provisions, Tolerances, Deviations and Fit. (entered by the Order of Rosstandart, February 18, 2014 No. 28-st)]. Moscow. Standardinform. 2014.37 p. (in Russian).
  5. GOST 2.308-2011. Edinaya sistema konstruktorskoj dokumentacii (ESKD). Ukazaniya dopuskov formy` i raspolozheniya poverxnostej. (vveden v dejstvie Prikazom Rosstandarta ot 03.08.2011.
     N 211-st) [Unified System for Design Documentation (ESKD). Indication of Tolerances of Shape and Location of Surfaces. (entered by the Order of Rosstandart, August 3. 2011. No. 211-st)]. Moscow : Standardinform. 2014. 25 p. (in Russian).
  6. RD E`O Rukovodyashhij dokument e`kspluatiruyushhej organizacii. Monitoring stroitel`ny`x konstrukcij atomny`x stancij. [Guidance Document of Operating Organization. Monitoring of Building Structures of Nuclear Power Plants]. Moskow. 2011
     (in Russian).
  7. Pimshin Yu.I., Zayarov Yu.V., Burdakov S.M., Naumenko G.A., Postoj L.V. Kalibrovka stankov s chislovy`m programmny`m upravleniem s pomoshh`yu lazernogo trekera VINTAG [Calibration of Machine Tools with Numerical Control Using VINTAG Laser Tracker] // E`lektronny`j nauchny`j zhurnal Inzhenerny`j vestnik Dona: setevoj zhurn. [“Engineering Bulletin of the Don” Electronic Scientific Journal: network journal]. 2016. №3. URL: http://ivdon.ru/ru/magazine/archive/n3y2016/3667 (in Russian).
  8. Pimshin Yu.I., Gubeladze O.A., Klyushin E.B., Zayarov Yu.V., Naugol`nov V.A., Arsen`ev D.M. Primenenie lazernogo trekera dlya opredeleniya deformacionny`x xarakteristik zashhitny`x obolochek [Application of Laser Tracker for Determining the Deformation Characteristics of Protective Shells]. Bezopasnost` yadernoj e`nergetiki : tez. dokl. XI mezhdunar. nauchn.-prakt. konf. [Safety of Nuclear Energy: reports of the XI International Scientific and Practical Conference]. May 27-29.2015. Volgodonsk. ВИТИ НИЯУ МИФИ. Волгодонск: [б.и.], 2015. 1 электнон. опт. диск [СD] [NRNU VITI MEPhI. Volgodonsk, 2015. 1 CD]  ISBN 978-5-7262-2114-4 (in Russian).
  9. Polyansky, A.V. Razrabotka metodiki geodezicheskogo obespecheniya stroitel`stva i e`kspluatacii uskoritel`no-nakopitel`nogo kompleksa na osnove garmonicheskogo analiza: avtoref. dis. kand. texn. nauk.  [Development of Methodology for Geodetic Support for the Construction and Operation of Accelerator-Storage Complex Based on Harmonic Analysis: thesis abstract of PhD in Engineering]. Novosibirsk [Novosibirsk]. 2015. 24 p. (in Russian).
  10. Burenkov, D.B. Razrabotka metodiki geodezicheskogo kontrolya izgotovleniya i ustanovki e`lementov uskoritel`no-nakopitel`ny`x kompleksov s ispol`zovaniem API Laser Tracker 3: avtoref. dis. kand. texn. nauk. [Development of Methods for Geodetic Control of Manufacturing and Installation of Accelerator-Storage Complexes Elements Using API Laser Tracker 3: thesis abstract of PhD in Engineering]. Novosibirsk. 2016. 24 p. (in Russian).
  11. Gurov S., Levichev E., Neyfeld V., Okunev I., Petrov V., Polyansky A.et al. Status of NSLS-II 54 booster. Сайт международных конференций [International Conference Site]. (JACOW (www.JACoW.org). URL : http://accelconf.web.cern.ch/AccelConf/PAC2011
    /papers/wep201.pdf (in Russian).
  12. Bokov M., Burenkov D., Polyanskiy A., Pupkov Yu. and Levashov Yu. Results of Long-term Observations of Deformations of the VEPP-4 Storage Ring Constructions, BINP. 1st FIG International Symposium on Engineering Surveys for Construction Works and Structural Engineering Nottingham. – United Kingdom, 28 June – 1 July 2004. – 1 электнон. опт. диск [CD] [1 CD].
Papers93 - 102
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Article Name10.26583/GNS-2019-02-12
Comparative Analysis of Neutrons Properties of Nuclear Fuel Produced by Westinghouse and Fuel Element for WWER-1000 Reactors by code SERPENT
AuthorsM.A. Abu Sondos1, V.M. Demin2, A. D. Smirnov3

Institute of Nuclear Physics and Technology (INP&T), National Research Nuclear University «MEPhI»,

Kashirskoye shosse, 31, Moscow, Russia 115409

1ORCID ID: 0000-0003-3954-151X

Wos Researher ID: E-2735-2019

e-mail: MAbusondos@mephi.ru

2ORCID ID: 0000-0003-3894-9396

Wos Researher ID: E-2750-2019

e-mail: VMDemin@mephi.ru

3 ORCID ID: 0000-0001-6381-8780

Wos Researher ID: E-3089-2019

e-mail: ADSmirnov@mephi.ru

AbstractThe paper analyzes the impact of spent nuclear fuel of WWER-1000 reactors of various operating conditions, such as the concentration of boric acid dissolved in water, the temperature of the fuel and others on the isotopic composition. Another factor of influence is the technical characteristics implemented in the production of fuel assemblies, in particular the mass of fuel, its enrichment and other mass-dimensional characteristics of fuel assemblies (FA). Calculations are carried out on models of fuel assemblies of the WWER-1000 reactor. The basis was taken of a typical fuel assembly of the Russian suppliers of fuel elements and fuel assembly of the Westinghouse American company.
KeywordsSerpent, FA-A, FA-WR, VVER-1000, SNF, operational conditions
  1. Lötsch T., Khalimonchuk V., Kuchin A. (2009). Proposal of a benchmark for core burnup calculations for a VVER-1000 reactor core. Munich, 2009. 
  2.  Lötsch T., Khalimonchuk V., Kuchin A. (2010). Corrections and additions to the proposal of a benchmark for core burnup calculations for a VVER-1000 reactor. Munich, 2010. 
  3. Lötsch T., Khalimonchuk V., Kuchin A. (2011). Solutions for the task 1 and task 2 of the benchmark for core burnup calculations for a VVER-1000 reactor. Munich, 2011.
  4. Kovbasenko Y. Sravnitel`ny`j analiz vozmozhnostej otrabotavshego topliva VVE`R-1000 Westinghouse i TVE`L [Comparative Analysis of WWER-1000 Westinghouse and TVEL Spent Fuel Capability]. Univers J Phys Appl 10(4), P. 105-109. DOI: 10.13189/ujpa.2016.100401
    (in Russian).
  5. Mirovy`e yaderny`e Novosti E`nergoatom planiruet ispol`zovat` toplivo Westinghouse v Zaporozh`e [World Nuclear News Energoatom Plans Use of Westinghouse Fuel at Zaporozhe] London. 11 November 2015 ISSN 2040-5766. URL: http://www.world-nuclear-news.org/UF-Energoatom-plans-use-of-Westinghouse-fuel-at-Zaporozhe-11111501.html (in Russian).
  6. Čudrnák P., Nečas V. Vliyanie e`kspluatacionny`x uslovij na izotopny`j sostav otrabotavshego topliva reaktora VVE`R-440 [Impact of the Operatinal Conditions on the Isotopic Composition of WWER-440 Reactor Spent Fuel] Int. Konf. 7-9 iyunya 2011 Tatranské Matliare ENERGY – Ecol. – E`konomicheskij [International Conference June 7-9, 2011 Tatranské Matliare ENERGY – Ecol. – Economics] 2011 High Tatras, Slovak Republic. Slovak Univ. Technol. Bratislava, Fac. Electr. Eng. Inf. Technol. Dep. Nucl. Phy. P. 7-10 (in Russian).
  7. Schneider E.A., Deinert M.R., Cady K.B. Vy`chislitel`no prostaya model` opredeleniya zavisyashhego ot vremeni spektral`nogo potoka nejtronov v aktivnoj zone yadernogo reaktora [Computationally Simple Model for Determining the Time Dependent Spectral Neutron Flux in Nuclear Reactor Core]. Zhurnal yaderny`x materialov [Journal of Nuclear Materials]. 2006. Vol. 357. Issue1-3. P. 19-30. DOI: 10.1016/j.jnucmat.2006.04.012 (in Russian).
  8. Kovbasenko Y., Bilodid Y., Yeremenko M. Sravnitel`ny`j analiz izotopnogo sostava otrabotavshego topliva VVE`R-1000 v zavisimosti ot uslovij proizvodstva i e`kspluatacii [Comparative Analysis of Isotope Composition of WWER-1000 Spent Fuel Depending on their Manufactory and Operation Conditions]. 7-j mezhd. Konf. Nucl. Kriticheskij. Bezopasnost` [7th International Conference Nucl Crit. Safety]. Tokai-mura. P. 661-665 (in Russian).
  9. Leppänen J. Vy`stuplenie Del`ta-otslezhivanie val`dshnepa v primenenie fiziki reshetku s pomoshh`yu zmeya fiziki reaktorov metodom Monte-Karlo vy`goraniya kod rascheta, letopisi atomnoj e`nergii [Performance of Woodcock Delta-Tracking in Lattice Physics Application Using the Serpent Monte Carlo Reactor Physics Burnup Calculation Code, Annals of Nuclear Energy] 2010. Vol. 37. Issue 5. P. 715-722. DOI: 10.1016/j.anucene.2010.01.011 (in Russian).
  10. Chadwick MB., Herman M., Obložinský P. ENDF/B-VII.1 yaderny`e danny`e dlya nauki i texniki : secheniya, kovariacii, vy`xody` produktov deleniya i danny`e raspada [ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data] Yaderny`e Pasporta [Nuclear Data Sheets]. 2011. Vol.112. P. 2887-2996. DOI: 10.1016/j.nds.2011.11.002 (in Russian).
  11. Novak O., Chvala O., Luciano N. P. Xmel`niczkij benchmark-analiz, rasschitanny`j Serpent2, Annals of Nuclear Energy [WWER 1000 Khmelnitskiy Benchmark Analysis Calculated by Serpent2, Annals of Nuclear Energy] 2017. Vol. 110. P. 948-957. DOI: 10.1016/j.anucene.2017.08.011
     (in Russian).
Papers103 - 109
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Article Name10.26583/GNS-2019-02-13
Some Aspects of Final Insulation of Radiation Wastes in Russia
AuthorsG.S. Zinoviev*1, V.S. Chembura**2

*Novouralsk Technological Institute the branch of NRNU MEPhI, Novouralsk, Sverdlovsk Region, Russia

**National Research Tomsk Polytechnic University, Tomsk, Russia

1ORCID ID: 0000-0003-0781-9425

e-mail: GSZinovyev@mephi.ru

2ORCID ID: 0000-0001-9028-3312

e-mail: vadimka.holloway@mail.ru

AbstractThis paper is devoted to the study of the state and the problems of radioactive waste management (RW). Particular attention is paid to the final isolation of radioactive waste by the example of a near-surface disposal site for radioactive waste from the Novouralskoye department of the Seversky branch of the National Operator for Radioactive Waste Management (NO RW) in Novouralsk, Sverdlovsk Region. The paper carries out a study of the safety and environmental technologies used in the enterprise. The main research methods are the study of expert opinions, public opinion polls, in particular, students of higher and secondary vocational education of the Novouralsk Technological Institute of the National Research Nuclear University MEPhI as well as their comparative analysis. Recommendations for improving the culture of the population in the use of nuclear technologies are proposed.
Keywordsradioactive waste, RW management, final isolation of RW, national operator for radioactive waste management, near-surface disposal facility for radioactive waste.
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    (in Russian).
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    bellona.org/content/uploads/sites/4/2017/02/RAO_public_site.pdf, 2017.(in Russian)
  10. FGUP «Nacional`ny`j operator po obrashheniyu s radioaktivny`mi otxodami». Klassy` RAO  [FSUE "National Operator for Radioactive Waste Management". Classes of RAO]. URL : http://www.norao.ru/waste/classification/class (in Russian).
  11. Interview of the undergraduate student of NI TPU Chembur V.S. (interviewer) with the head of Novouralskoye branch of Seversky branch of NO RAO. Alexandrov from April 4, 2018 [Audio recording of the conversation] // FSUE "NO RAO", Novouralsk, 26 min. 34 seconds Published with the consent of V.V. Alexandrova.
  12. Otchet po e`kologicheskoj bezopasnosti 2015 [Report on Environmental Safety 2015]. URL : http://www.rosatom.ru/upload/iblock/d4e/d4edde3e02aef7ff28d29ef1883ed18f.pdf (in Russian).
  13. Materialy` obosnovaniya licenzii na e`kspluataciyu pervoj ocheredi stacionarnogo ob``ekta, prednaznachennogo dlya zaxoroneniya radioaktivny`x otxodov – pripoverxnostnogo punkta zaxoroneniya tverdy`x radioaktivny`x otxodov, otdeleniya «Novoural`skoe» filiala «Severskij» FGUP «NO RAO» (vklyuchaya materialy` ocenki vozdejstviya na okruzhayushhuyu sredu) [Materials for the Substantiation of the License for the Operation of the First Stage of a Stationary Facility Intended for the Disposal of Radioactive Waste - the Near-Surface Disposal Facility for Solid Radioactive Waste, Novouralskoye Department of the Seversky Branch of FSUE «NO RAO» (Including Environmental Impact Assessment Materials)]. URL: http://www.norao.ru/upload/MOL%20Novouralsk_Economy_tomy 201.pdf (in Russian).
  14. Pochti tri chetverti rossiyan zayavili o podderzhke atomnoj e`nergetiki [Almost Three-Quarters of Russians Expressed Support for Nuclear Power]. URL: https://lenta.ru/news/2018/04/09/oprosrosatom (in Russian).
  15. Zhiteli rossijskix regionov razmeshheniya AE`S podderzhali atomnuyu e`nergetiku [Residents of the Russian Regions of Nuclear Power Plant Location Supported Nuclear Power]. URL:
    http: //www.atomic energy.ru/news/2015/07/27/58608 (in Russian).
  16. Studenty` Novoural`ska uznali o novy`x narabotkax v oblasti obrashheniya s radioaktivny`mi otxodami [Students of Novouralsk Learned about New Developments in the Field of Radioactive Waste Management]. URL: https://mephi.ru/content/news/1412/121465 (in Russian).
Papers110 - 122
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Article Name10.26583/GNS-2019-02-14
The Formation of the Safety Culture of School Students in the Organization System of Leading Personnel Training for Atomic Energy
Authors1V.A. Rudenko, 2N.F. Privalova

Volgodonsk Engineering Technical Institute the branch of National Research Nuclear University “MEPhI”,

Lenin St., 73/94, Volgodonsk, Rostov region, Russia 347360

1ORCID iD: 0000-0002-6698-5469

WoS Researcher ID: B-7730-2016

e-mail: VARudenko@mephi.ru

1ORCID iD: 0000-0002-6464-188

e-mail: NFPrivalova@mephi.ru

AbstractThe article reveals the relevance of developing a safety culture of schoolchildren in the system of organizing advanced training of engineering personnel for nuclear energy at the stage of innovative development of the industry; considers the possibility of professional orientation to the specialty areas of training, specialized for nuclear energy in the field of developing a safety culture of schoolchildren.
Keywordssafety culture, innovative development, engineering, advanced training, professional orientation.
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     Rosenergoatom Concern JSC for 2016]. Moskow. 2017. URL : http://www.rosenergoatom.ru/
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    (in Russian).
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    № 3. P. 39-44. URL: https://cyberleninka.ru/article/v/tehnologiya-formirovaniya-gotovnosti-uchaschihsya-k-vyboru-professii-v-sfere-bezopasnosti-zhiznedeyatelnosti (in Russian).
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