CALCULATION OF THE ACTIVITY OF A STEEL AMPOULE AFTER REACTOR IRRADIATION
https://doi.org/10.52676/1729-7885-2023-4-85-90
Abstract
The paper considers a method for evaluating the activity of a steel ampoule after reactor irradiation by the Monte Carlo method. The object of study is a single-wall ampoule made of steel 12Cr18Ni10Ti. This ampoule serves as a protective barrier during reactor tests with experimental devices at the IGR reactor. Forecasting the activity value of the ampoule after the reactor start-up will allow timely planning and organization of work on further safe handling of the ampoule. The results of the neutron-physical calculation of the radiation characteristics of the ampoule, performed in the MCNP program using two methods, are presented.
About the Authors
A. S. Surayev
Branch “Institute of Atomic Energy” RSE NNC RK
Kazakhstan
Kazakhstan
G. G. Kakimova
Branch “Institute of Atomic Energy” RSE NNC RK; Shakarim University
R. A. Irkimbekov
Branch “Institute of Atomic Energy” RSE NNC RK
References
1. Batyrbekov E., Vityuk V., Vurim A., Vityuk G. Experimental opportunities and main results of the impulse graphite reactor use for research in safety area // Annals of Nuclear Energy. – 2023.– Vol. 182. – P. 109582. https://doi.org/10.1016/j.anucene.2022.109582
2. MCNP6 Monte Carlo N–Particle Transport Code System, MCNP6.1. LANL, 2013.
3. Sajranbaev D. S. Issledovanie nejtronno-fizicheskih harakteristik aktivnoj zony issledovatel'skogo reaktora VVR-K s bokovym berillievym otrazhatelem: spec. 6D060500 dissertaciya na soiskanie stepeni doktora filosofii PhD. KazNU im. Al'-Farabi. – Almaty, 2022. – 113 p.
4. Ponomarenko. P.A., Tıapkına V.A. Teoretıcheskıe osnovy eksperımentalnogo opredelenııa dınamıcheskogo spektra bystryh neıtronov // Iaderna ta radіatsіına bezpeka. – 2010. – No. 2 (46). – P. 50–52.
5. Metrologııa neıtronnyh ızmerenıı na ıaderno-fızıcheskıh ýstanovkah (rekomendýemye spravochnye dannye ı metodıkı ızmerenıı): Materıaly I Vsesoıýznoı shkoly/ Pod red. R.D. Vasıleva. – T. 1 & 2. – Moscow.: TsNIIatomınform, 1976. – 253 p.
6. Glaser, A. Neutronics Calculations Relevant to the Conversion of Research Reactors to Low-Enriched Fuel. Ph.D. Thesis. 2005. http://tuprints.ulb.tu-darmstadt.de
7. A. c. IS 006968 dated 12/27/16 Republic of Kazakhstan. Computer model of the IGR reactor for stationary neutronic calculations / A.D. Vurim, V.M. Kotov, R.A. Irkimbekov, L.K. Zhagiparova, A.A. Baigozhina. – No. 2738; 12/27/2016 – P. 1.
Supplementary files
Review
For citations:
Surayev A.S., Kakimova G.G., Irkimbekov R.A. CALCULATION OF THE ACTIVITY OF A STEEL AMPOULE AFTER REACTOR IRRADIATION. NNC RK Bulletin. 2023;(4):85-90. (In Russ.) https://doi.org/10.52676/1729-7885-2023-4-85-90
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