ROSATOM State  Atomic Energy Corporation


Joint Stock Company “State Scientific Center – Research Institute of Atomic Reactors”


On May 27-31, 2019, JSC “SSC RIAR” (Dimitrovgrad, Russia) will host the 11th Conference on Reactor Materials Science dedicated to the 55th Anniversary of the RIAR’s Reactor Materials Testing Complex.


Conference Venue: The Slavsky Conference Center

Arrival date: May 27, 2019

Conference opening: May 28, 2019, 9 AM

Conference closing: May 30, 2019

Departure date: May 31, 2019

Registration of participants: The Slavsky Conference Center,

                          May 27, 2019, from 3 PM to 5 PM,

                          May 28, 2019, from 8 AM to 9 AM.

Transfer for the Conference participants from and to Ulyanovsk and Samara airports will be provided on the arrival and departure dates.


Dear colleagues!

We are pleased to invite you to attend the 11th Conference on Reactor Materials Science dedicated to the 55th Anniversary of the RIAR’s Reactor Materials Testing Complex to be held on May 27-31, 2019 at JSC “SSC RIAR” (Dimitrovgrad).


Conference Topics

Radiation materials science and nuclear materials enhancement:

  • Power reactor fuel and fuel elements;
  • Structural materials of nuclear and fusion reactors;
  • Absorbing and moderating materials.


To participate in the Conference, please fill in a registration form and send it to the Conference Committee with a scanned copy of your passport attached before February 11, 2019.  

Plenary papers and posters are accepted. Conference proceedings will be issued prior to the Conference. The deadline for submitting the abstracts in English is March 11, 2019. The plenary papers and posters are to be submitted to the Conference Committee before the Conference opening.  


Organizational issues

  • The Conference languages are Russian and English.
  • You can take part in the Conference either as a speaker or an attendee (provided the registration fee is paid).
  • The Conference Program and Conference proceedings will be provided to the Conference participants before the Conference opening.
  • The abstracts to be published must be submitted to the Conference Committee in the electronic format following the guidelines before March 11, 2019.



If you need transfer, please email your name, arrival date and flight No. at

Arrival date: May 27, 2019

Departure date: May 31, 2019


Conference Committee:

Chairperson         A.A. Tuzov
Chairperson Deputies V.D. Risovany
  E.A. Zvir
Scientific Secretary V.S. Neustroev
Secretary S.S. Shipulina


Conference Committee Members:

A.F. Grachev

Innovation and Technology Center of “PRORYV” Project


B.A. Gurovich

NRC “Kurchatov Institute”


A.B. Dolgov



A.V. Dub

JSC “Science and Innovations”


S.V. Evropin



A.A. Enin



A.L. Izhutov



B.A. Kalin



F.N. Kryukov



B.Z. Margolin

NRC “Kurchatov Institute” - CRISM “PROMETEY”


V.V. Novikov



V.V. Petrunin

JSC “OKBM Afrikantov”


V.A. Piminov



L.P. Sinelnikov



M.V. Skupov



V.M. Troyanov

JSC “Rosenergoatom Concern”


A.V. Ugryumov






Conference venue

The Conference will be held at the Slavsky Conference Center, Dimitrovgrad.

Address: Russia, Dimitrovgrad, Dimitrov Ave., 12.



Conference registration form

Attention, please!

Final date for applications for participation is February 22

  • A conference registration form is to be completed before February 11, 2019. A scanned copy of your passport must be uploaded as well.
  • An abstract in English should either be uploaded when completing the registration form or sent by e-mail at Please follow the Abstract Guidelines.
  • Application/invoice: please note that there are two different forms of an application/invoice depending on the currency you use (USD or euros).









The abstracts should be submitted in English in the electronic format at

Abstract text: A4 paper format, margin 25 mm, Times New Roman Cyr, 12 pt, single spacing.

The complete abstract should not exceed three pages including tables and figures.
The title should be centered, capitalized and bold.
Names of all authors (initials, last name) should be written in small letters (first letters and initials are capitalized) two spaces below the title in the middle of the page.
Organization (company, institution), city and country should be written two spaces below the names of all authors in the middle of the page.
Abstracts must be clear and concise.


The poster size: 0.70×1.00 m (portrait orientation).
The posters must be of high printing quality.
Recommended font size: at least 18 pt.
The following details must be specified: poster name, authors’ initials and last names, company, city, and country.
The posters must be clear and concise. It is recommended that the main information be presented as tables and figures and the wording be minimized.
The graphics must be of high quality, please follow the textual order.




To make a presentation or present a paper please provide an electronic version of your paper or presentation. There are no specific guidelines for papers or presentations.


Registration fee & accommodation

The registration fee per participant is 400 euros or 480 US dollars. It includes transfer, simultaneous interpreting, coffee breaks, welcome reception, all Conference events, Conference proceedings, and other Conference-related documents.

The registration fee does not include hotel meals and accommodation; those are paid individually by an attendee.

The participants will be accommodated in Raduga and D-Grad Hotels. Please specify the number of rooms to be booked in the registration form. If you have any questions or concerns regarding the hotel accommodation, please feel free to contact us by phone: +7 (84235) 7-96-10 or e-mail:      

The registration fee shall be paid before May 13, 2019.

Please note!

The registration fee shall be paid through a wire transfer only.



Conference participant application/invoice (for payments in US dollars)


Conference participant application/invoice (for payments in euros)

Programme ХI Conference on Reactor Material Science dedicated to the 55th anniversary of the RIAR’s Materials Testing Complex 

Mailing Address:
Joint Stock Company “State Scientific Center – Research Institute of Atomic Reactors”, Russian Federation, 433510, Ulyanovsk region, Dimitrovgrad, Zapadnoye Shosse, 9

Contact persons:
Organizational issues should be addressed to Mrs. Elena Agibaeva,
Tel./ Fax: +7(84235) 7-96-10 , e-mail:


The Conference participants will be accommodated in Raduga Hotel and D-Grad Hotel.

How to reach us:

by air: Ulyanovsk Airport, Samara Airport
by rail: Railway station in Ulyanovsk or in Dimitrovgrad

On 27 May 2019 (arrival), transfer to the hotel will be provided for the Conference participants.

On 31 May 2019 (departure), transfer from the hotel to the railway station and airport will be provided for the Conference participants.



Key results of post-irradiation examinations performed at JSC “SSC RIAR” in 2014–2018. E.A. Zvir, V.A. Zhitelev, A.V. Zakharov, F.N. Kryukov, V.Yu. Shishin (JSC “SSC RIAR”, Dimitrovgrad, Russia)

The expectations of the fuel vendor in the field of reactor material science of nuclear fuel, the results of the cooperation and material science aspects of future research in the midterm perspective. A.V. Ugryumov (JSC “TVEL”, Moscow, Russia)

Analysis of the directions to create an accident tolerant fuel. B.A. Kalin, A.V. Tenishev, A.A. Polyansky (NRNU “MEPhI”, Moscow, Russia)

Development of a new swelling position for PWR austenitic internals, reflecting much lower swelling compared to higher-temperature fast reactor experience.  F. A. Garner (NRNU “MEPhI”, Department of Materials Science, Moscow, Russia)

Current state and plans on validation of the mixed nitride fuel for fast reactors.  M.V. Skupov1, L.M. Zabudko2 (1JSC "VNIINM", Moscow, Russia; 2ITCP "Proryv", Moscow, Russia)


Upgrading Nuclear Icebreaker Cores Based on Operating Experience and Post Irradiation Examinations. O.B. Samoylov, O.A. Morozov, A.N. Lepekhin, V.Yu. Silayev, A.A. Zakharychev, V.V. Vasilyev (JSC "Afrikantov OKBM", Nizhny Novgorod, Russia)

E110-M alloy fuel rod claddings in-reactor tests in water-cooled reactors and post-irradiation examination results. A.Yu. Shevyakov, V.A. Markelov, V.V. Novikov, N.S. Saburov, A.Yu. Gusev, V.F. Kon’kov, M.M. Peregud (JSC «VNIINM», Moscow, Russia)

Comparative analysis of the fuel rod state with E110 and E110 opt. claddings irradiated up to burnup of 49,6–63,7 MW·day/kgU. A.V. Strozhuk, V.A. Zhitelev, I.N. Volkova, Yu.D. Goncharenko, A.S. Khrenov, G.V. Shevlyakov, A.A. Bokov

High temperature oxidation of the alloy E110 with coatings based on Fe-Cr-Ni and Cr-Ni alloys.  A.S. Yashin1, B.A. Kalin1, N.V. Volkov1, D.A. Safonov1, P.S. Dzhumayev1, V.V. Novikov2, V.I. Kuznetsov2, P.V. Fedotov2, A.A. Mokrushin3, K.К. Polunin3 (1NRNU “MEPhI”, Moscow, Russia; 2JSC "VNIINM", Moscow, Russia; 3FSUE «SRI "SIA “Luch”"», Podolsk, Russia) 

Interim examinations of experimental fuel rods tested in the MIR reactor under PWR conditions. A.L. Izhutov, A.V. Burukin, O.N. Vladimirova, A.I. Dolgov, P.A. Ilyin, V.V. Kalygin, M.A. Mokeichev, V.A. Ovchinnikov (JSC “SSC RIAR”, Dimitrovgrad, Russia)

Studying of the VVER-1000 fuel rods behaviour under the loss-of-coolant-accident (LOCA) conditions: in-pile MIR-LOCA/45 and MIR-LOCA/45 and MIR-LOCA/69 tests. A.V. Alekseev1, A.V. Goryachev1, O.I. Dreganov1, A.L. Izhutov1, L.V. Kireeva1, I.V. Kiseleva1, V.N. Shulimov1, V.I. Kuznetsov2, V.V. Novikov2, A.V. Salatov2, P.V. Fedotov(1JSC «SSC RIAR», Dimitrovgrad, Russia; 2JSC "VNIINM", Moscow, Russia)

Study of stained shells of the fuels of reactor type PWR with protective coating in conditions characteristic for an accident with heat carrier loss. A.A. Urusov, A.A. Mokrushin, D.M. Soldatkin, K.K. Polunin (FSUE «SRI "SIA “Luch”"», Podolsk, Russia)

Changes in the geometry of VVER-1000 TVS-2 and TVS-2M and their components under operation. G.V. Shevlyakov, A.V. Strozhuk, O.G. Sidorenko, A.S. Khrenov, A.A. Bokov (JSC "SSC RIAR", Dimitrovgrad, Russia)

Development and application of techniques for evaluation of coolant activity during operation of VVER power units. P.M. Kalinichev, I.A. Evdokimov, V.V. Likhanskii, E.Yu. Afanasyeva, A.G. Khromov (JSC "SRC RF TRINITI", Troitsk, Russia)

Integrity testing of the TVSA-ALFA fuel elements by gamma-spectrometry of the gas plenum. S.S. Sagalov, V.A. Zhitelev, G.V. Shevlyakov, А.V. Strozhuk, V.G. Teplov, Е.G. Iliyna (JSC «SSC RIAR», Dimitrovgrad, Russia)

Effect of neutron irradiation in the VVER-1000 reactor on the characteristics of secondary phases in zirconium alloys E110 and E635. A.V. Obukhov, G.P. Kobylyansky, S.S. Sagalov, A.R. Belozerova (JSC «SSC RIAR», Dimitrovgrad, Russia)

Engineering-economic analysis of the use of accident tolerant fuel in nuclear power engineering. V.V. Kharitonov, B.A. Kalin, A.N. Silenko, Yu.A. Ul’yanin (NRNU "MEPhI", Moscow, Russia)

Analysis of VVER-1000 fuel rods elongation under thermal tests simulating dry storage conditions.  G.P. Kobylyansky, A.O Mazaev, E.A. Zvir, P.A. Ilyin, A.V. Obukhov (JSC "SSC RIAR", Dimitrovgrad, Russia)

Structural materials for fast neutron reactors with sodium and lead coolants. M.V. Leontyeva-Smirnova, M.V. Skupov, A.A. Nikitina, I.A. Naumenko, N.M. Mitrofanova (JSC "VNIINM", Moscow, Russia)

Role of JSC «OKB "Gidropress"», JSC "SSC RIAR" and CRISM "Prometey" in international project ТАСIS-2002 (R2/01.02). V.M. Komolov1, V.V. Evdokimenko1, V.A. Piminov1, I.O. Tregubov1, V.I. Tsofin1, B.Z. Margolin2, A.A. Sorokin2, A.I. Minkin2, I.Yu. Zhemkov3, V.S. Neustroev3, V.K. Shamardin3 (1JSC «OKB "Gidropress"», Podolsk, Russia; 2NRC «"Kurchatov Institute" — CRI SM "Prometey"», Saint-Petersburg, Russia; 3JSC "SSC RIAR", Dimitrovgrad, Russia)

Swelling, creep and embrittlement of D9 stainless steel cladding and duct in four FFTF driver fuel assemblies after high neutron exposures. F.A. Garner (NRNU “MEPhI”, Department of Materials Science, Moscow, Russia)

HIgh temperature irradiation embrittlement in neutron irradiated austenitiс stainless steels 08Kh18N10T, EI-847, EP-172 and ChS-68. S.I. Porollo, A.А. Ivanov, Yu.V. Konobeev, S.V. Shulepin (NRC «"Kurchatov Institute" — SSC RF — IPPE», Obninsk, Russia)

Radiation phenomena in irradiated austenitic steels after long irradiation in BOR-60 reactor. V.S. Neustroev, S.V. Belozerov, E.I. Makarov, D.E. Markelov, A.V. Obukhov, D.A. Sokolovsky (JSC "SSC RIAR", Dimitrovgrad, Russia)

Optimization of structural-phase state of fuel pin claddings made of steel EK164 in order to increase the resource efficiency of fast neutron reactors fuel assemblies. T.А. Churyumova, N.М. Mitrofanova (JSC "VNIINM", Moscow, Russia)

The effect of oxygen and hydrogen on stress corrosion cracking of 304NG stainless steel in high temperature water with trace chloride ion for PWR primary loop. P. DeQuan, W. Hui, H. Yong, Z. BaoLiang (CIAE, Beijing, China)

Microstructural and chemical characterization of irradiation effects in claddings with different alloy compositions. K.D. Johnson1, K.I. Lafchiev1, D. Jädernäs1, O. Tengstrand1, A.Y. Shevyakov2, A.B. Dolgov3, A.V. Ugryumov3 (1Studsvik Nuclear AB, Studsvik, Sweden; 2JSC "VNIINM", Moscow, Russia; 3JSC "TVEL", Moscow, Russia)

Effect of irradiation on susceptibility of ferritic-martensitic steels to liquid metal embrittlement in liquid lead-bismuth environment. S. Gavrilov, E. Stergar, M. Lambrechts, M. Konstantinovic, J. Van den Bosch (SCK / CEN, BNRC, Mol, Belgium)

Radiation creep and swelling of steel 08Х18Н10Т at 350–420 °С.  E.I. Makarov, V.S. Neustroev, A.V. Obukhov, D.E. Markelov (JSC "SSC RIAR", Dimitrovgrad, Russia)

Evolution of the microstructure of austenitic steels after irradiation at 300–350 °С in reactors BOR-60 and SM. D.E. Markelov1, V.S. Neustroyev1, V.K. Shamardin1, B.Z. Margolin2, A.A. Sorokin2 (1JSC "SSC RIAR", Dimitrovgrad, Russia; 2NRC «"Kurchatov Institute" — CRISM "Prometey"», Saint-Petersburg, Russia)

Examination of corrosion in ЭП823-Ш steel claddings of the fuel rods with lead and helium substrates. Ilnur F. Gilmutdinov1, F.N. Kryukov1, O.N. Nikitin1, I.Yu. Zhemkov1, M.V. Skupov2, Yu.A. Ivanov2 (1JSC "SSC RIAR", Dimitrovgrad, Russia; 2JSC "VNIINM", Moscow, Russia)

Experiment-based and calculation data analysis of the operating conditions for the BOR-60 irreplaceable components. I.Yu. Zhemkov, Yu.V. Naboishchikov, Yu.M. Krasheninnikov (JSC «SSC RIAR», Dimitrovgrad, Russia)

Irradiation-induced swelling of BOR-60 small rotation plug studs. V.S. Neustroyev, D.A. Sokolovsky, S.V. Belozerov, I.Yu. Zhemkov, E.I. Makarov, Yu.V. Naboishchikov, A.I. Plotnikov, N.S. Poglyad, N.I. Shirokova (JSC "SSC RIAR", Dimitrovgrad, Russia)

Quality control procedure applied to welded joints of fuel elements for BN-800 reactor with mixed oxide uranium-plutonium fuel. M.A. Litvinova, A.A. Maltsev (FSUE «PA "Mayak"», Ozyorsk, Russia)

Welding of test specimens and test rigs intended for irradiation testing. A.V. Kaplin, E.M. Tabakin, S.A. Andreyev (JSC "SSC RIAR", Dimitrovgrad, Russia)

Specific details of swelling in uranium-plutonium nitride fuel used for fabrication of helium gas- and liquid metal-bonded test fuel rods. A.V. Belyaeva, F.N. Kryukov, O.N. Nikitin, and S.V. Kuzmin (JSC “SSC RIAR”)

THE METHOD OF THE URANIUM SESQUINITRIDE RESIDUAL AMOUNT FOR DETERMINING IN MIXED NITRIDE NUCLEAR FUEL FUEL.  M.P. Krivov ,G.A. Kireev, A.V. Davydov, A.V. Tenishev (A.A. Bochvar High-technology Research Institute of Inorganic Materials)

Status and Development Areas of Reactor Cores for Icebreaker Nuclear Propulsion Plants and Small-Sized NPPs. V.V. Petrunin, A.I.  Romanov, V.Yu.  Papotin, A.N. Lepekhin, A.A. Zakharychev, S.G. Petrov JSC “Afrikantov OKBM”, Nizhny Novgorod, Russia

RITM-200 Reactor Core for Small-Sized NPPs. A. A. Zakharychev, V.Yu. Papotin, D.M. Stadnik (JSC “Afrikantov OKBM”, Nizhny Novgorod, Russia), A. A. Sheldyakov  (JSC SSC RIAR, Dimitrovgrad, Russia), S. I. Korovushkin (MSZ, JSC, Elektrostal, Russia)

Pre-reactor tests of fragments of uranium-zirconium metal fuel rods obtained during the modernization of the reactor core IVG.1. K.K. Polunin, A.N. Bakhin, D.A. Zaytsev, D.M. Soldatkin, V.A. Solntsev (FSUE «SRI “SIA "Luch"”», Podolsk, Russia)

Examination of experimental dispersed fuel compositions to justify the performance of low neutron poisoning fuel rods to be used in the SM reactor. Ilgiz F. Gilmutdinov, V.Yu. Shishin, F.N. Kryukov, V.V. Pimenov, E.I. Efimov (JSC "SSC RIAR", Dimitrovgrad, Russia)

PIE of three TVEL fuel rods irradiated in Ringhals 3, Sweden. Kalin Lafchiev,  Kyle Johnson, Daniel Jadernas,  Alexander Shevyakov, Aleksey Dolgov, Alexander Ugryumov

Results of post-irradiation examinations of the sponge-based E110 opt. alloy operated as fuel cladding material in alternative TVSA-ALPHA up to attaining a burnup of 42 MW·day/kg U to establish the experimental databank in support of russian fuel licensing for PWR plants. Yu.D. Goncharenko1, S.G. Eremin1, E.V. Chertopyatov1, A.V. Obukhov1, T.M. Bulanova1, G.V. Shishalova1, A.Yu. Shevyakov2, S.A. Bekrenev2, V.V. Novikov2, V.A. Markelov2 (1JSC "SSC RIAR", Dimitrovgrad, Russia; 2JSC "VNIINM", Moscow, Russia)

Problems of examining uranium and plutonium dioxides using scanning electronic microscopy, possible ways to solve the probems, selecting optimum mode for examination of mox-fuel for BN-800 reactors. A.A. Maltsev, M.A. Litvinova (FSUE «PA "Mayak"», Ozyorsk, Russia)

Development of ferritic steel for fuel element cladding. B.A.Tarasov, I.I. Konovalov, M.D. Saveliev, M.S. Tarasova, D.P. Shornikov, N.S. Nikitin  (JSC «VNINM» NRNU MEPHI)

CORROSIVE AND MECHANICAL RESISTANCE OF MgO CERAMICS IN MOLTEN SALTS UNDER METALLIZING AND MILD CHLORINATION OF SPENT NUCLEAR FUEL. Golosov O.A.1, Khvostov S.S.1, Glushkova N.V.1, Evseev M.V.1, Staritsyn S.V.1,Zaikov Yu.P.2, Kovrov V.A.2, Nikitina E.V.2, Kholkina A.S.2, Kazakovtseva N.A.2 (1 JSC «INM», Zarechny, Russia 2 IHTE UB RAS, Yekaterinburg, Russia)

Radiation tolerance of ultrafine-grained materials produced by severe plastic deformation. N.A. Enikeev V.K. Shamardin, B. Radiguet (Ufa State Aviation Technical University Saint Petersburg State University Russian Institute of Atomic Reactors Rouen University)

Mechanical properties and structure of irradiated ultra-fine grained steel 08Х18Н10Т produced by equal-channel angular pressing. V.K. Shamardin1, T.M. Bulanova1, A.A. Karsakov1, A.V. Obukhov1, L.A. Evseyev1, E.P. Belan1, R.Z. Valiev2, N.A. Enikeyev2, I.V. Alexandrov2, M.M. Abramova2, and A.K.Glus (Joint Stock Company "State scientific Center -Research Institute of Atomic Reactors", Dimitrovgrad, Russia, 2    Ufa State Aviation Technical University, Ufa, Russia,Dimitrovgrad Engineering and Technology Institute -Affiliated Branch of Federal State Autonomous Educational Institution for Higher Education "MEPhI", Dimitrovgrad, Ulyanovsk region, Russia)

Production of Large Monocrystalline Ingots and Discs of Molybdenum and its Alloys via Crucibleless Zone Melting for Special Application Products. E.G. Kolesnikov, V.A. Stepanov, P.A. Stepanchikov, R.A. Fedoseev, A.N. Shotaev («SRI SIA «LUCH»,Russia)

Classification of irradiation rigs for material testing in BOR-60 reactor. I.Yu. Zhemkov, S.G. Eremin, A.I. Plotnikov,   N.S. Poglyad, V.Yu.Anisimov, A.V. Boev (JSC "SSC RIAR", Dimitrovgrad, Russia)

Tritium and helium release from beryllium-based materials irradiated up to high neutron doses. V. Chakin, R. Rolli, R. Gaisin (Institute for Applied Materials-Applied Materials Physics, Karlsruhe Institute of Technology, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany)