Nuclear Physics and Atomic Energy 14 (2013) 367

Ядерна фізика та енергетика
Nuclear Physics and Atomic Energy

ISSN: 1818-331X (Print), 2074-0565 (Online)
Publisher: Institute for Nuclear Research of the National Academy of Sciences of Ukraine
Languages: Ukrainian, English
Periodicity: 4 times per year

Open access peer reviewed journal

Home page

About

Nucl. Phys. At. Energy 2013, volume 14, issue 4, pages 367-371.
Section: Atomic Energy.
Received: 08.11.2013; Published online: 30.12.2013.

Full text (ru)
https://doi.org/10.15407/jnpae2013.04.367

Calculations of the nuclide composition of spent nuclear fuel of RBMK-1000 for verification of computer module SCALE-6

V. V. Soloviov, E. O. Lebedev

Chernobyl Nuclear Power Plant, Slavutych, Ukraine

Abstract: The article presents the calculation of the nuclide composition of spent nuclear fuel of RBMK using modules TRITON/T6-DEPL and ORIGEN-ARP of modular code system SCALE-6 and comparison with the experimental nuclide composition. In the analysis of the results of calculations and comparison with experimental data only actinides were considered, which constitute 99% of the mass of spent nuclear fuel. The calculation of the nuclide composition of the inner and outer rings of fuel rods, and its combined value were performed. The discrepancy with the experimental data on isotopes ²³⁵U, ²³⁹Pu, ²⁴¹Pu, which are major contributors to the effective neutron multiplication factor, does not exceed 22%. The design model which was created in this paper can be used to calculate the nuclide composition of the fuel of RBMK-1000 using modular code system SCALE-6.

Keywords: nuclide composition, spent nuclear fuel, RBMK-1000, modular code system SCALE.

References:

1. Приказ ГКЯРУ № 24. Положение о системе измерения ядерных материалов (2006).

2. Гальченко В. В., Макодим В. І., Соловйов В. В., Ількович В. В. Урахування вигоряння ядерного палива при обґрунтуванні ядерної безпеки систем зберігання та транспортування відпрацьованого ядерного палива РВПК-1000. Ядерна фізика та енергетика 11 (2010) 415. https://jnpae.kinr.kyiv.ua/11.4/Articles_PDF/jnpae-2010-11-0415-Galchenko.pdf

3. Plukien R., Plukis A., Germanas D., Remeikis V. Numerical sensitivity study of irradiated nuclear fuel evolution in the RBMK reactor. Lithuanian Journal of Physics 49 (2009) 461. http://dx.doi.org/10.3952/lithjphys.49410

4. SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Version 6.0, Vols. 1-3 (ORNL/TM-2005/39, 2009).

5. Широков С. В. Ядерні енергетичні реактори. Навч. посібник (Київ: НТУУ "КПІ", 1997) 280 с.

6. Murphy B. D. ORIGEN-ARP Cross-Section Libraries for the RBMK-1000 system (ORNL/TM-2006/139, November 2006).

7. Makarova T. Investigation of Spent Fuel from WWER-440, WWER-100 and RBMK-1000, report prepared for IAEA by the Khlopin Radium Institute (2004).

8. Murphy B. D. ORIGEN-ARP Cross-Section Libraries for Magnox, Advanced Gas-Cooled, and VVER Reactor Designs (ORNL/TM-2003/263, February 2004).

9. DeHart M. D. TRITON: A Two-Dimensional Transport and Depletion Module for Characterization of Spent Nuclear Fuel, Version 6, Vol. 1, Sect. T1 (ORNL/TM-2005/39, 2009).

10. Gauld I. C., Bowman S. M., Horwedel J. E. ORIGENARP: Automatic Rapid Processing for Spent Fuel Depletion, Decay, and Source Term Analysis, Version 6, Vol. 1, Sect. D1 (ORNL/TM-2005/39, 2009).

11. Ковбасенко Ю. П., Еременко М. Л. Определение изотопного состава отработавшего топлива реакторов РБМК для последующего анализа ядерной безопасности с учетом выгорания топлива. Ядерна та радіаційна безпека 50 (2011) 35.