Authors & Affiliations
Vilensky O.Yu., Ryabtsov A.V.
Afrikantov Experimental Design Bureau for Mechanical Engineering, Nizhny Novgorod, Russia
Vilensky O.Yu. – Head of Department, Cand. Sci.(Tech.), Afrikantov Experimental Design Bureau for Mechanical Engineering. Contacts: 603074, 15 Burnakovsky proezd, Nizhny Novgorod, Russia. Tel.: +7 (831) 246-97-21; e-mail
Ryabtsov A.V. – Deputy Head of Department, Afrikantov Experimental Design Bureau for Mechanical Engineering.
During the operation of fuel assemblies in the active zone of fast sodium reactors, a significant degradation of the structural material of fuel assemblies and fuel cladding occurs. As a result, along with a significant change in the basic mechanical properties, the effects of radiation-induced swelling and radiation-induced creep of the materials appear. Radiation shaping of fuel assemblies under conditions of high doses of irradiation with fast neutrons affects the safe operation of the reactor core and leads to the limitation of fuel burnup. Therefore, mathematical models are needed that would most fully reflect the processes occurring in the active zone of fast reactors and are in good agreement with available experimental data. Based on the analysis of the results of the inspected regular and experimental fuel assemblies, the core sleeves of the BN-600 reactor control and protection system, as well as the steel EP-450 samples irradiated in the BR-10 and BN-350 reactors in terms of the radiation swelling rate and the radiation creep modulus obtained depending on the temperature of irradiation, the dose-temperature dependences of these processes are proposed for assemblies of the core of BN reactors made of EP-450 steel. Taking into account the existing dose-temperature dependences of the swelling and creep of the structural materials of the active zones (currently used and promising), mathematical models are recommended for use in calculating the rationale for the radiation formation of assemblies, with the use of the software complex “ANSYS” certified in the Rostechnadzor, expand its capabilities. The computational analysis of the radiation-induced assembly of assemblies, using the presented mathematical models, showed a good agreement between the results obtained with the “ANSYS” software package and the results of post-reactor measurements of the radiation shaping of hexagonal covers of experimental FAs, as well as the sleeves of the BN-600.
fuel assembly, radiation shaping, radiation-induced swelling, radiation-induced creep, experimental data, BN-600, cover, EP-450, mathematical model, computational analysis, software complex “ANSYS”
1. Vremennye rukovodyashchie materialy po ispol'zovaniyu dannykh po svoystvam konstruktsionnykh materialov i SNUP topliva dlya obosnovaniya rabotosposobnosti eksperimental'nykh tvelov ETVS reaktora BN-600 [Provisional guiding materials on usage of structural material property and MNUP fuel property data to validate operability of experimental fuel rods in EFSAs for BN-600 reactor]. The State Atomic Energy Corporation ROSATOM, 2-nd rev. Moscow, 2014.
2. Chuev V.V. Povedenie konstruktsionnykh materialov v spektre neytronov bystrogo reaktora bol'shoy moshchnosti. Diss. dok. tech. nauk [Behavior of structural materials in the neutrons spectrum of high power fast reactor. Dr. tech. sci. diss.]. Zarechnyy, 2007.
3. Zabud'ko L.M., Korostin O.S., Ogorodov A.N, Kozmanov E.A. Issledovanie raspukhaniya i radiatsionnoy polzuchesti chekhlovykh staley ferritno-martensitnogo klassa po rezul'tatam poslereaktornykh izmereniy geometrii chekhlov TVS reaktora BN-600 [Radiation-induced swelling and creep research of ferritic-martensitic class casing steels based on the results of post-reactor measurements of the BN-600 fuel assemblies cladding geometry]. Trudy 3 mezhotraslevoy konferentsii po reaktornomu materialovedeniyu [Proc. 3th Interdisciplinary Conference on Reactor Materials Science]. Dimitrovgrad, 1992, p. 54.
4. Karaulov V.N., Blynskiy A.P., Yakovlev I.L., Kononova E.V. Povedenie TVS i tvelov aktivnoy zony reaktora BN-350 pod oblucheniem [Irradiation behavior of fuel assemblies and fuel rods BN-350 reactor core]. Trudy mezhdunarodnoy nauchno-prakticheskoy konferentsii "Nuclear Power Engineering in the Republic of Kazakstan. Perspectives of Development" [Proc. Int. Sci. Practical Conference "Nuclear Power Engineering in the Republic of Kazakstan. Perspectives of Development (Ne-96)"]. Aktau, Kazakhstan, 1996.
5. ANSYS software package. Software tool certificate No. 327 dated April 18, 2013. (In Russian)
6. Borodin O.V., Bryk V.V., Voevodin V.N., et al. Radiatsionnoe raspukhanie ferritno-martensitnykh staley EP-450 i NT-9 pri obluchenii metallicheskimi ionami do sverkhvysokikh doz [Radiation swelling of ferrite-martensitic steels EP-450 and NT-9 under irradiation with metallic ions to ultrahigh doses]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika radiatsionnykh povrezhdeniy i radiatsionnoe materialovedenie – Problems of Atomic Science and Technology. Series: Physics of Radiation Damage and Radiation Material Science, 2011, no. 2(97), pp. 10-15.