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Nuclear Data for Science and Technology pp 95–97Cite as

Cross Sections for Actinide Burner Reactors

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Part of the book series: Research Reports in Physics ((RESREPORTS))

Abstract

Recent studies have shown the feasibility of burning higher actinides (i.e., transuranium (TRU) elements excluding plutonium) in ad hoc designed reactors (Actinide Burner Reactors: ABR) which; because of their hard neutron spectra, enhance the fission of TRU. The transmutation of long-lived radionuclides into stable or short-lived isotopes reduces considerably the burden of handling high-level waste from either LWR or Fast Breeder Reactors (FBR) fuels. Because of the large concentrations of higher actinides in these novel reactor designs the Doppler effect due to TRU materials is the most important temperature coefficient from the point of view of reactor safety. Here we report calculations of energy group-averaged capture and fission cross sections as function of temperature and dilution for higher actinides in the resolved and unresolved resonance regions. The calculations were done with the codes SAMMY in the resolved region and URR in the unresolved regions and compared with an independent calculation.

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References

  1. T. Mukaiyama, H. Tanako, T. Hakizuka, T. Ogawa, Y. Gunjian, and S. Okajima, “Higher Actinides Transmutation Using Higher Actinides Burner Reactors,” International Conference on the Physics of Reactors: Operation, Design and Computation, Marseilles, April 1990, Vol. 1, p. 1–97.

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  2. N. M. Larson, “Updated Users’ Guide for SAMMY: Multilevel R-Matrix Fits to Neutron Data Using Bayes’ Equations,” ORNL/TM-9179/R2 (1989).

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  3. L. C. Leal, G. deSaussure and R. B. Perez, “URR Computer Code: A Code to Calculate Resonance Neutrons Cross Section Probability Tables, Bondarenko Self Shielding Factors, and Self-Indication Ratios for Fissile and Fertile Nuclides,” ORNL/TM-11297 (1989).

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  4. N. M. Greene, J. L. Lucius, L. M. Petrie, W. E. Ford, J. E. White and R. Q. Wright, “AMPX: A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF /B,” ORNL/TM-3706 (1976).

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Author information

Authors and Affiliations

  1. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN, 37831-6363, USA

    Felix C. Difilippo

Authors
  1. Felix C. Difilippo
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Editor information

Editors and Affiliations

  1. Forschungszentrum Jülich GmbH, Institut für Nuklearchemie, Postfach 1913, W-5170, Jülich, Fed. Rep. of Germany

    Syed M. Qaim Ph. D., D. Sc.

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© 1992 Springer-Verlag Berlin Heidelberg

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Difilippo, F.C. (1992). Cross Sections for Actinide Burner Reactors. In: Qaim, S.M. (eds) Nuclear Data for Science and Technology. Research Reports in Physics. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-58113-7_27

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  • DOI: https://doi.org/10.1007/978-3-642-58113-7_27

  • Publisher Name: Springer, Berlin, Heidelberg

  • Print ISBN: 978-3-642-63473-4

  • Online ISBN: 978-3-642-58113-7

  • eBook Packages: Springer Book Archive

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