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One-Group Cross-Sections of High-Threshold Reactions for Precision Neutronics Calculations

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Low-concentration nuclides – impurity nuclides – are increasingly in demand in radiochemistry for defining more precisely the neutronic characteristics of the medium. On use in precision calculations, impurity nuclides afford more accurate calculations. This article considers aspects of the calculation of one-group cross sections of the high-threshold reactions (n, nt), (n, 2α), (n, 2p), (n, pα), (n, nd), (n, np), (n, 2nα), and others in extended libraries and their influence on the nuclide composition of irradiated compositions in calculations using the MZK precision program. This program affords guaranteed accuracy of calculated nuclides, including impurities. A procedure is proposed for calculating one-group cross sections as applied to the spectrum in fast reactors.

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References

  1. D. M. Zhuk, V. B. Manichev, and M. K. Sakharov, “SADEL – a library of ‘high-precision’ solvers for the PA10 software package (SADEL-PA10),” in: Proc. MES-2012, IPPM RAN, Moscow (2012), pp. 147–153.

  2. E. F. Mitenkova, E. V. Solovjeva, V. B. Manichev, and D.Yu. Kozhevnikov, “MZK program for solving stiff systems in nuclide kinetics problems,” At. Energiya, 130, No. 6, 323–326 (2021).

    Google Scholar 

  3. E. F. Mitenkova, E. V. Solovjeva, and D. Yu. Kozhevnikov, MZK – Precision Program for Nuclide Kinetics Problems, Preprint IBRAE RAS No. IBRAE-2021-01 (2019).

  4. ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6, BNL-NCS-44945-01/04-Rev. (2001).

  5. A. Plompen, O. Cabellos, G. Žerovnik , et al., “The joint evaluated fission and fusion nuclear data library, JEFF-3.3,” EUR. Phys. J. A, 56, No. 7, 181–288 (2020).

    Article  ADS  Google Scholar 

  6. M. Chadwick, M. Herman, and P. Obložinskii, “ENDF/B-VII.1: nuclear data for science and technology: cross sections, covariances, fission product yields and decay data,” Nucl. Data Sheets, 112, 2887–3152 (2011).

    Article  ADS  Google Scholar 

  7. R. Macfarlane and A. Kahler, “Methods for processing ENDF/B-VII with NJOY,” Nucl. Data Sheets, 111, 2739–2890 (2010).

    Article  ADS  Google Scholar 

  8. V. B. Manichev, E. F. Mitenkova, and E. O. Fel’dman, “Reliability and accuracy of the solution of nuclide kinetics problems,” Inform. Tekhnol., 26, No. 4, 231–238 (2020).

  9. E. F. Mitenkova, E. V. Solovjeva, and D. Yu. Kozhevnikov, MZK Precision Program for Calculating Impurity Nuclides in Nuclide Kinetics Problems, Preprint IBRAE RAS No. IBRAE-2022-02 (2022).

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Authors and Affiliations

  1. Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAS), Moscow, Russia

    E. F. Mitenkova, N. V. Novikov & E. V. Solovjeva

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  1. E. F. Mitenkova
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  2. N. V. Novikov
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  3. E. V. Solovjeva
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Correspondence to E. F. Mitenkova.

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Translated from Atomnaya Énergiya, Vol. 133, No. 4, pp. 219–223, October, 2011.

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Mitenkova, E.F., Novikov, N.V. & Solovjeva, E.V. One-Group Cross-Sections of High-Threshold Reactions for Precision Neutronics Calculations. At Energy 133, 228–232 (2023). https://doi.org/10.1007/s10512-023-01001-7

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  • DOI: https://doi.org/10.1007/s10512-023-01001-7

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