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Neutron Capture Cross Sections of Radioactive Nuclei

  • Nuclear Physics
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Abstract

Alternative methods to calculate neutron capture cross sections on radioactive nuclei are reported using the theory of inclusive non-elastic breakup (INEB) developed by Hussein and McVoy (Nucl. Phys. A. 445, p. 124, 1985). The statistical coupled-channels theory proposed in Bertulani et al. (Eur. Phys. J. Web Conf. 69, 00020, 2014) is further extended in the realm of random matrices. The case of reactions with the projectile and the target being two-cluster nuclei is also analyzed and applications are made for scattering from a deuteron target (Hussein et al. 2020). An extension of the theory to a three-cluster projectile incident on a two-cluster target is also discussed. The theoretical developments described here should open new possibilities to obtain information on the neutron capture cross sections of radioactive nuclei using indirect methods.

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Acknowledgments

BVC thanks P. Descouvemont for discussions and his hospitality at the Université Libre de Bruxelles where part of this work was developed.

Funding

CAB received support from U.S. DOE Grant No. DE-FG02-08ER41533as well as funding contributed through the LANL Collaborative Research Program by the Texas A&M System National Laboratory Office and Los Alamos National Laboratory. BVC received support from grant 2017/05660-0 of the São Paulo Research Foundation (FAPESP), grant 306433/2017-6 of the CNPq, and the INCT-FNA project 464898/2014-5.

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Authors and Affiliations

  1. Department of Physics and Astronomy, Texas A&M University-Commerce, Commerce, TX, USA

    C. A. Bertulani

  2. Departamento de Física, Instituto Tecnológico de Aeronáutica-CTA, 12228-900, São José dos Campos, Brazil

    B. V. Carlson

Authors
  1. C. A. Bertulani
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  2. B. V. Carlson
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Corresponding author

Correspondence to C. A. Bertulani.

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To the Memory of Mahir Hussein

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Bertulani, C.A., Carlson, B.V. Neutron Capture Cross Sections of Radioactive Nuclei. Braz J Phys 51, 212–222 (2021). https://doi.org/10.1007/s13538-020-00824-0

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