EDN: JSBHPP
Authors & Affiliations
Popov E.P., Tykleeva K.V., Grabezhnoi V.A., Zabrodskaya S.V., Smykov V.B., Zhdanov V.P., Mezentsev A.N.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Tykleeva K.V. – Researcher. 1, pl. Bondarenko, Obninsk, Kaluga Region, Russia. Tel.: +7 (484) 399-53-75;
e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Grabezhnoi V.A. –Senior Researcher, Cand. Sci. (Phys.-Math.).
Zabrodskaya S.V. – Leading Researcher, Cand. Sci. (Phys.-Math.).
Popov E.P. – Senior Researcher.
Smykov V.B. – Deputy Head of Department, Cand. Sci. (Tech.).
Zhdanov V.P. – Lead Engineer.
Mezentsev A.N. – Head of Service «D».
Abstract
IPPE JSC has developed a method of solid-phase oxidation (SPO) of alkali metals with copper smelting slag, which must be worked out in relation to the entire chain of work with radioactive sodium of the 1st circuit and implemented in plants that meet modern safety requirements.
The main way of research is the development of a fully functional sample of a scaled MINERAL unit and storage at the final burial stage of sodium recycled into “stone” (in a slag-like compound according to RB-155-20 terminology, SPO). One of the tasks was to building out preliminary calculations to determine the dose gamma fields when loading a reaction vessel with a solid product of sodium processing in the form of SLC in two versions of the unit MINERAL.
Studies were aimed at selecting a container, determining the initial data for the calculated modeling of various options for determining dose gamma fields when loading a reaction container with a solid product of sodium processing.
The basis for the study was the spent alkaline coolant (radioactive waste Na, Na-K alloy with Hg impurities) of the BR-10 research reactor, which operated with different types of fuel (PuO2, UO2, UC, UN) in the period 1956–2002.
Keywords
BR-10, fast reactor, sodium of the 1st circuit, sodium processing, slag-like compound, solid-phase oxidation method, RW, long-term storage tank, dose gamma fields
Article Text (PDF, in Russian)
References
1. Smykov V.B., Kryuchkov Ye.A., Bagdasarov Yu.Ye. et al. Problemy konditsionirovaniya radioaktivnykh otkhodov shchelochnykh teplonositeley pri vyvode iz ekspluatatsii issledovatel'skoko reaktora BR-10 [Problems of conditioning of radioactive wastes of alkaline coolant during decommissioning of BR-10 reactor]. Sbornik dokladov konferentsii “50 let puska reaktora BR-5” [Proc. of the conference “50 years of the BR-5 reactor start-up”]. Obninsk, IPPE Publ., 2009, pp. 115–127.
2. Website OAO “345 Mekhanicheskiy zavod” [Website of JSC 345 Mechanical Plant]. Available at: https://345mz.ru/kontejneryi-dlya-rao/zhelezobetonnyie-kontejneryi (accessed 07.02.2023).
3. GOST 26633-2012. Mezhgosudarstvennyy standart. Betony tyazhelyye i melkozernistyye. Tekhnicheskiye usloviya [State Standard 26633-2012. Concrete is heavy and fine-grained. Specifications]. Moscow, Standartinform Publ., 18 p.
4. GOST R 51824-2001. Konteynery zashchitnyye nevozvratnyye dlya radioaktivnykh otkhodov iz konstruktsionnykh materialov na osnove betona. Obshchiye tekhnicheskiye trebovaniya [State Standard 51824-2001. Protective non-returnable containers for radioactive waste made of concrete-based structural materials. General technical requirements]. Moscow, Izdatel'stvo standartov Publ., 2001. 8 p.
5. Kanukhina S.V., Kononyuk M.K., Butov K.A. et al. Computational and Experimental Studies of Solid-Phase Oxidation of Alkali Metal Slag From Copper Smelting Operations. Atomic Energy, 2016, vol. 120, issue 6, pp. 403–411. DOI: https://doi.org/10.1007/s10512-016-0149-0.
6. Voloschenko A.M., Gukov S.V., Kryuchkov V.P. et al. The CNCSN: one, two- and three-dimensional coupled neutral and charged particle discrete ordinates code package. Proc. Internat. Conf. Math. And Comput., Supercomput., Reactor Phys. and Nucl. and Biol. Applic. Avignon, France, September 12–15, 2005, on CD-ROM.
7. BNAB-93. Certificate of State Registration no.&bnbsp;2014620091 dated January 15, 2014.
8. Orsi R. BOT3P Version 5.1: A Pre/Post-Processor System for Transport Analysis. ENEA report FIS-P9H6-014, Italy, 2006.
UDC 621.039
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 1, 1:15