DOI: 10.55176/2414-1038-2019-2-215-227
Authors & Affiliations
Boev A.V., Belozerova A.R., Zhemkov I.Yu., Ishunina O.V., Naboyshchikov Yu.V., Pavlov V.V., Chernysheva T.I.
Joint Stock Company “State Scientific Center — Research Institute of Atomic Reactors”,
Dimitrovgrad, Russia
Boev A.V. – Junior Researcher, Joint Stock Company “State Scientific Center – Research Institute of Atomic Reactors”.
Belozerova A.R. – Senior Researcher, Cand. (Phys.-Math.) Sci., Joint Stock Company “State Scientific Center – Research Institute of Atomic Reactors”.
Zhemkov I.Yu. – Expert-Head of laboratory, Proffessor, Joint Stock Company “State Scientific Center – Research Institute of Atomic Reactors”.
Ishunina O.V. – Senior Researcher, Joint Stock Company “State Scientific Center – Research Institute of Atomic Reactors”.
Naboyshchikov Yu.V. – Senior Researcher, Joint Stock Company “State Scientific Center – Research Institute of Atomic Reactors”. Contacts: 9, Zapadnoye Shosse, Dimitrovgrad, Ulyanovsk region, 433510. Tel.: +7(84235) 7-98-41, E-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Pavlov V.V. – Lead Engineer, Joint Stock Company “State Scientific Center – Research Institute of Atomic Reactors”.
Chernysheva T.I. – Lead Engineer, Joint Stock Company “State Scientific Center – Research Institute of Atomic Reactors”.
Abstract
The BOR-60 reactor is actively used for conducting irradiation experiments in support of nuclear re-actors both under operation, construction and design. Most of these experiments are conducted in the reactor core using various types of irradiation rigs. However, in recent years there has been keen in-terest in conducting reactor tests in the BOR-60 blanket. This is associated with several factors: the availability of blanket cells, weak influence on the reactor neutronic characteristics and safety, wide range of irradiation conditions (temperature, neutron flux density, damage doses, neutron spectrum), and cost of irradiation.
The experience in BOR-60 blanket computational and experimental studies showed an ill agree-ment between the calculated and experimental neutronic characteristics. In addition to no orientation of the samples under study relative to the core center, there is a significant radial non-uniformity in the neutronic characteristics distribution in the BOR-60 blanket that limits its application for experimental studies. Therefore, detailed computational and experimental studies of the spatial-energy distribution of neutrons in the BOR-60 steel blanket is an important and urgent task.
Keywords
BOR-60 reactor, blanket, neutron fluence, irradiation rig
Article Text (PDF, in Russian)
References
1. Gadzhiev G.I., Zhemkov I.Yu. Obzor issledovaniy neytronno-fizicheskikh kharakteristik, vypolnennykh pri puske reaktora BOR-60 [Review of studies of neutron-physical characteristics performed during the start-up of the BOR-60 reactor]. Dimitrovgrad, SSC RF RIAR Publ., 2011. 88 p.
2. Zhemkov I.Yu. Raschetnoe modelirovanie kharakteristik reaktora BOR-60 v protsesse ego ekspluatatsii i sovershenstvovaniya [Design modeling of the characteristics of the reactor BOR-60 during its operation and improvement]. Dimitrovgrad, SSC RF RIAR Publ., 1997. Pp. 59–65.
3. Zhemkov I.Yu., Ishunina O.V., Yakovleva I.V. Sbornik neytronno-fizicheskikh kharakteristik reaktora BOR-60 [Collection of neutron-physical characteristics of the reactor BOR-60]. Dimitrovgrad, SSC RF RIAR Publ., 2000. 38 p.
4. Zhemkov I.Yu. Nauchno-metodicheskoe soprovozhdenie ekspluatatsii issledovatel'skogo reaktora na bystrykh neytronakh. Diss. dok. tekhn. nauk [Scientific and methodological support of operation of a fast neutron research reactor. Dr. techn. sci. diss.]. Dimitrovgrad, 2014. 42 p.
5. Zhemkov I.Yu., Naboyshchikov Yu.V., Tellin A.I., Ryazanov D.K. Raschetno-eksperimental'noe opredelenie prostranstvenno-energeticheskogo raspredeleniya neytronov v bokovom ekrane reaktora BOR-60 [Calculation and experimental data analysis of neutron spatial-energy distribution in the BOR-60 blanket]. Voprosy Atomnoy Nauki i Tekhniki. Seriya: Yaderno-reaktornye konstanty - Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constans, 2017, no. 2, pp. 67–76.
6. Bregadze Yu.I., Stepanov E.K., Yaryna V.P. Prikladnaya metrologiya ioniziruyushchikh izlucheniy [Applied metrology of ionizing radiation]. Moscow, Energoatomizdat Publ., 1990. 264 p.
7. FENDL-3.1b: Fusion Evaluated Nuclear Data Library Ver.3.1b Released on 1 July 2016. Available at: https://www-nds.iaea.org/fendl/index.html (accessed 24.08.2016).
8. X-ray and Gamma-ray Decay Data Standards for Detector Calibration and Other Applications: International Atomic Energy Agency Nuclear Data Section. Available at: https://www-nds.iaea.org/xgamma_standards/ (accessed 20.07.2018).
9. Mednis I.V. Secheniya yadernykh reaktsiy, primenyaemykh v neytronno-aktivatsionnom analize: Spravochnik [Cross sections of nuclear reactions used in neutron activation analysis: Handbook]. Riga, Zinatne, 1991. 119 p.
10. Sertifikat o kalibrovke № 9/4-17 na Gamma-spektrometricheskuyu sistemu HPGe GEM-25185-P DSPECPLUS ORTEC GammaVision-32 ot 24.03.2017, AO "GNTs NIIAR" OMIT.
11. Svidetel'stvo №1171-01.00050-2014-2018 ob attestatsii Metodiki (metoda) izmereniy navedennoy aktivnosti neytronno-aktivatsionnykh detektorov po reestru metodik AO "GNTs NIIAR" reg. no. 1171, data attestatsii 20.06.2018.
12. Svidetel'stvo №1075-01.00050-2014-2016 o metrologicheskoy attestatsii "Metodiki rascheta kharakteristik polya neytronov pri neytronno-dozimetricheskom soprovozhdenii reaktornogo oblucheniya" po reestru metodik AO "GNTs NIIAR" reg. no. 1075, data attestatsii 15.06.2016.
13. Kamnev V.A., Troshin V.S. Kompleksnaya programma MIXER dlya vosstanovleniya spektra neytronov pri aktivatsionnykh izmereniyakh [A comprehensive program MIXER to restore the neutron spectrum during activation measurements]. Trudy IV Vsesoyuznogo soveshchaniya po metrologii neytronnogo izlucheniya na reaktorakh i uskoritelyakh [Proc. 4th All-Union Meeting on Metrology of Neutron Radiation at Reactors and Accelerators]. Moscow, 1985, p. 37.
14. Gomin E., et al. The MCU Monte Carlo Code for 3D Depletion Calculation. Proc. of Intern. Conf. on Mathem. and Comput., Reac. Phys., and Envir. Analyses in Nucl Applications. Spain, Madrid, 1999, vol. 2, pp. 997–1006.
15. Seregin A.S., Kislitsyna T.S., Tsibulya A.M. Annotatsiya kompleksa programm TRIGEX.04 [Annotation of the TRIGEX.04 program complex]. Preprint FEI-2846 - Preprint IPPE-2846. Obninsk, 2000. 14 p.
16. Zhemkov I.Yu. Kompleks avtomatizirovannogo rascheta kharakteristik reaktorov na bystrykh neytronakh [Complex automated calculation of the characteristics of fast-neutron reactors]. Dimitrovgrad, SSC RF RIAR Publ., 1996, no. 4, pp. 56–68.
17. Programmnyy kompleks TRIGEX.05 [TRIGEX.05 software package]. Certification passport of software no. 312 dated 09.10.2012.
UDC 621.039.51
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 2, 2:21
