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Activation cross sections of some neutron-induced reactions in the energy range of 13.82–14.71 MeV

  • Md Shuza Uddin EMAIL logo
Veröffentlicht/Copyright: 1. November 2021
Radiochimica Acta
Aus der Zeitschrift Radiochimica Acta Band 110 Heft 1

Abstract

The cross sections of the reactions 70Zn(n,2n)69mZn,74Ge(n,α)71mZn and 90Zr(n,2n)89m,gZr in the energy range of 13.82–14.71 MeV were measured by the activation technique in combination with HPGe detector γ-ray spectroscopy. The measured results were compared with other experimental data and with the data given in the library TENDL-2019. A nuclear model calculation based on the code TALYS-1.8 was also performed after adjustment of an input parameter for the spin distribution of level density. The results of this work strengthen the database and could be useful in further evaluation of the data.

Keywords: 13.82–14.71 MeV energy; cross section; HPGe detector γ-ray spectroscopy; neutron activation; neutron generator; TALYS-1.8 code
Corresponding author: Md Shuza Uddin, Tandem Accelerator Facilities, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Savar, Dhaka, Bangladesh, E-mail:

Acknowledgements

The author thanks Dr. N.I. Molla, Ex-member of BAEC and Prof. M.R. Zaman of Rajshahi University for their guidance to conduct experiment at J-25 Neutron Generator, INST, Savar, Dhaka. The author thanks the operational crews of the J-25 Neutron Generator, particularly M. Ahad Ali and M. Ali Azam, for their help in performing the irradiations. He is particularly grateful to Prof. S.M. Qaim for critical comments on this work and helpful suggestions to improve the presentation.

  1. Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.

  2. Research funding: None declared.

  3. Conflict of interest statement: The authors declare no conflicts of interest regarding this article.

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Received: 2021-07-28
Accepted: 2021-10-14
Published Online: 2021-11-01
Published in Print: 2022-01-27

© 2021 Walter de Gruyter GmbH, Berlin/Boston

Artikel in diesem Heft

  1. Frontmatter
  2. Original Papers
  3. Activation cross sections of some neutron-induced reactions in the energy range of 13.82–14.71 MeV
  4. New reference materials for trace-levels of actinide elements in plutonium
  5. Adsorption properties and mechanism of uranium by three biomass materials
  6. Synthesis of “(aminomethyl)phosphonic acid-functionalized graphene oxide”, and comparison of its adsorption properties for thorium(IV) ion, with plain graphene oxide
  7. Review
  8. Application of response surface method in the separation of radioactive material: a review
  9. Original Paper
  10. Preparation, characterization, and bioevaluation of 99mTc-famotidine as a selective radiotracer for peptic ulcer disorder detection in mice
https://doi.org/10.1515/ract-2021-1085
Schlagwörter für diesen Artikel
13.82–14.71 MeV energy; cross section; HPGe detector γ-ray spectroscopy; neutron activation; neutron generator; TALYS-1.8 code

Artikel in diesem Heft

  1. Frontmatter
  2. Original Papers
  3. Activation cross sections of some neutron-induced reactions in the energy range of 13.82–14.71 MeV
  4. New reference materials for trace-levels of actinide elements in plutonium
  5. Adsorption properties and mechanism of uranium by three biomass materials
  6. Synthesis of “(aminomethyl)phosphonic acid-functionalized graphene oxide”, and comparison of its adsorption properties for thorium(IV) ion, with plain graphene oxide
  7. Review
  8. Application of response surface method in the separation of radioactive material: a review
  9. Original Paper
  10. Preparation, characterization, and bioevaluation of 99mTc-famotidine as a selective radiotracer for peptic ulcer disorder detection in mice
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