EDN: ELPTXL
Authors & Affiliations
Chertovskikh O.I., Belov A.A., Kryachko M.V.
Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, Russia
Chertovskikh O.I. – Engineer. Contacts: 52, st. Bolshaya Tulskaya, Moscow, Russia, 115191. Tel: +7 (495) 955-23-11-52; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Belov A.A. – Researcher.
Kryachko M.V. – Engineer.
Abstract
Authors present the methodology description and results of the uncertainty evaluation in FNS (Fusion Neutronics Source) experiment simulation. The calculations of evolution of the steel SS-304 and SS-316 compositions under 5-minutes and 7-hour irradiation with following decay mode calculations were provided with inventory code BPSD. Uncertainty evaluation of the calculated parameters were conducted by stochastic GRS method. Uncertainty of the initial compose were taken as a source of uncertainty. The bounds of the interval for drawing the composition of steel elements are taken from the ASTM A213/A213M-18. The content of the element in steel was played assuming its uniform distribution over the interval.
The results of the experiment, calculations using the FISPACT-II program and the BPSD code are compared. The results of estimating the uncertainty of the significant nuclide concentrations, their residual heat release and the total residual heat release are presented numerically and graphically on the activation and exposure intervals, the resulting uncertainty of the activity of nuclides and the total activity is presented graphically. The obtained results of estimation of the uncertainties of nuclear concentrations are explained, the channels of reactions of important nuclides are shown for the purpose of explaining the behavior of the uncertainty of the total decay heat.
Keywords
steel activation, isotopic kinetics, BPSD, FNS, fast-neutron reactor, GRS, uncertainty of the calculation, uncertainty in input data, SS-304, SS-316
Article Text (PDF, in Russian)
References
- NP-001-15. Federal'nyye normy i pravila v oblasti ispol'zovaniya atomnoy energii “Obshchiye polozheniya obespecheniya bezopasnosti atomnykh stantsiy” [NP-001-15. Federal regulations in the field of the use of atomic energy “General provisions for safety of nuclear power plants”]. Moscow, 2016. 57 p.
- Poryadok provedeniya ekspertizy programm dlya elektronnykh vychislitel'nykh mashin, ispol'zuyemykh v tselyakh postroyeniya raschetnykh modeley protsessov, vliyayushchikh na bezopasnost' ob"yektov ispol'zovaniya atomnoy energii i (ili) vidov deyatel'nosti v oblasti ispol'zovaniya atomnoy energii [Procedure of examination of the programs used for design of the computational models of the processes affecting the safety of nuclear facilities and/or activities in the field of atomic energy use]. Approved by the order of Rostechnadzor No. 325, 30.07.2018.
- RB-166-20. Rukovodstvo po bezopasnosti pri ispol'zovanii atomnoy energii “Rekomendatsii po otsenke pogreshnostey i neopredelennostey rezul'tatov raschetnykh analizov bezopasnosti atomnykh stantsiy” [RB-166-20.Safety guide of the use of atomic energy “Recommendations for uncertainty evaluation of the results of calculation analyses in nuclear power plant safety”]. Approved by the order of Rostechnadzor No. 288, 30.07.2020.
- Best estimate safety analysis for nuclear power plants: uncertainty evaluation. Safety reports series, no. 52. IAEA, 2008. 199 p.
- Pisarev A.N., Kolesov V.V. A study into the propagation of the uncertainties in nuclear data to the nuclear concentrations of nuclides in burnup calculations. Izvestiya vuzov. Yadernaya Energetika, 2020, no. 2, pp. 108–121. DOI: https://doi.org/10.26583/npe.2020.2.10.
- Garcı´a-Herranz N., O. Cabellos O., Sanz J. et al. Propagation of statistical and nuclear data uncertainties in Monte Carlo burn-up calculations. Annals of Nuclear Energy, 2008, vol. 35, pp. 714–730. DOI: https://doi.org/10.1016/j.anucene.2007.07.022.
- Wilks S.S. Determination of Sample Sizes for Setting Tolerance Limits. The Annals of Mathematical Statistics, 1941, vol. 12, pp. 91–96.
- Wilks S.S. Mathematical statistics. W. Anderson, Ed. Wiley, New York, 1967. 693 p.
- Seleznyov E.F., Belov A.A., Belousov V.I., Chernova I.S. BPSD code upgrade for solving the nuclear kinetics problem. Izvestiya vuzov. Yadernaya Energetika, 2018, no. 4, pp. 115–127. DOI: https://doi.org/10.26583/npe.2018.4.10.
- The FISPACT-II User Manual. Tech. Rep. UKAEA-CCFE-R(18)001, CCFE, 2018.
- Radhakrishnan K. and Hindmarsh A.C. Description and use of LSODE, the Livermore solver for ordinary differential equations. Technical Report LLNL Report UCRL-ID-113855, LLNL, 1993.
- Gilbert M.R., Sublet J-Ch. Fusion decay heat validation, FISPACT-II & TENDL-2017, EAF2010, ENDF/B-VIII.0, JEFF-3.3, and IRDFF-1.05 nuclear data libraries. Tech. Rep. UKAEA-CCFE-R(18)002, CCFE, 2018.
- Eastwood J.W., Morgan J.G., Sublet J-Ch. Inventory Uncertainty Quantification using TENDL Covariance Data in Fispact-II. Nuclear Data Sheets, 2015, vol. 123, pp. 84–91. DOI: https://doi.org/10.1016/j.nds.2014.12.015.
- Belov A.A., Kryachko M.V., Chertovskikh O.I. Calculation of the structural materials activation by a fusion neutron flux with BPSD code. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2021, no. 4, pp. 47–62. DOI: 10.55176/2414-1038-2021-4-47-62.
- American Society for Testing and Materials. Standart Specification for Seamless Ferritic, Austenitic Alloy-Steel Boiler, Superheater and Heat-exchanger Tubes, 2018, 14 p.
UDC 621.039:519.23
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 2, 2:3
