Journals / Eskişehir Technical University Journal of Science and Technology A - Applied Sciences and Engineering / 2021 / Cilt: 22 - Sayı: 2

INVESTIGATION OF NEUTRON-INDUCED REACTION CROSS SECTIONS FOR SEVERAL NUCLEAR REACTOR STRUCTURAL MATERIALS

Pages
215–238
Publication Date
2021-06-29
DOI
—
🏛️Bibliographic metadata and full text access for this article are provided via DergiPark.
DergiPark Record ↗
✨

AI Summary & Key Takeaways

AI Insight
⚡ TL;DR(Too Long; Didn't Read)

The obtained results are compared with the experimental data taken from the literature.

📌 3 Key Takeaways

🎯
Objective & Hypothesis:Selection of the appropriate materials as a structural components of nuclear reactor are of key importance to implement the highest efficiency and security.
📊
Key Findings & Data:The presented result of neutron-induced reaction cross section calculations for Cr50-52-53-54, Fe54-56-57, Nb93, Sn117-119-124, Zr90-91-92 have been computed using Constant Temperature Model, Back Shifted Fermi Gas Model, Generalised Super Fluid Model and Microscopic level densities presented in TALYS 1.9 nuclear code.
💡
Conclusion & Impact:The obtained results are compared with the experimental data taken from the literature.
🔬Design:Modeling & Simulation
📍Scope:Comprehensive Sample
⚙️Variables:Level density models · Level density parameter · TALYS 1.9

Abstract

Selection of the appropriate materials as a structural components of nuclear reactor are of key importance to implement the highest efficiency and security. Zr, Fe, Cr, Sn and Nb are commonly used materials involved in structural alloy inside the reactor. The presented result of neutron-induced reaction cross section calculations for Cr50-52-53-54, Fe54-56-57, Nb93, Sn117-119-124, Zr90-91-92 have been computed using Constant Temperature Model, Back Shifted Fermi Gas Model, Generalised Super Fluid Model and Microscopic level densities presented in TALYS 1.9 nuclear code. The calculations have been repeated by changing the level density parameter a for each isotope and model to observe changes in the model assumption. The obtained results are compared with the experimental data taken from the literature.

🔖

Cite This Article

DAĞ, M. (2021). INVESTIGATION OF NEUTRON-INDUCED REACTION CROSS SECTIONS FOR SEVERAL NUCLEAR REACTOR STRUCTURAL MATERIALS. Eskişehir Technical University Journal of Science and Technology A - Applied Sciences and Engineering, Cilt: 22 - Sayı: 2, 215–238. https://ajindex.com/articles/214892

📄 Full Text PDF Viewer

📄

PDF görüntüleyici hazırlanıyor...

References (12)

  1. Zinkle SJ and Busby JT. Structural materials for fission & fusion energy, Materials Today, vol. 12, Nov. 2009, no. 11. pp. 12–19,, doi: 10.1016/S1369-7021(09)70294-9
  2. Motta AT, Couet A and Comstock RJ. Corrosion of Zirconium Alloys used for Nuclear Fuel Cladding, Annu. Rev. Mater. Res. 2015, vol. 45, no. 1, pp. 311–343, doi: 10.1146/annurev-matsci-070214-020951
  3. Kakiuchi K, Ohira K, Itagaki N, Otsuka Y, Ishii Y and Miyazaki A. Irradiated behavior at high burnup for hifi alloy. J. Nucl. Sci. Technol., 2006; vol. 43, no. 9, pp. 1031–1036, doi: 10.1080/18811248.2006.9711192
  4. Parashari S, Mukherjee S, Vansola V, Makwana R, Singh NL and Pandey B. Investigation of (n, p), (n, 2n) reaction cross sections for Sn isotopes for fusion reactor applications. Appl. Radiat. Isot., 2018; vol. 133, pp. 31–37, doi: 10.1016/j.apradiso.2017.12.003
  5. Sarpün IH, Aydln A and Pekdoǧan H. Determination of the effects of nuclear level density parameters on photofission cross sections of 235U up to 20 MeV. EPJ Web Conf., vol. 146, pp. 2016–2018, 2017, doi: 10.1051/epjconf/201714605015
  6. Aydin A, Pekdogan H, Kaplan A, Sarpün IH, Tel E and Demir B. Comparison of Level Density Models for the 60,61,62,64Ni(p, n) Reactions of Structural Fusion Material Nickel from Threshold to 30 MeV. J. Fusion Energy, Oct. 2015; vol. 34, no. 5, pp. 1105–1108, doi: 10.1007/s10894-015-9927-2
  7. Özdoğan H, Şekerci M, Sarpün H and Kaplan A. Investigation of level density parameter effects on (p,n) and (p,2n) reaction cross–sections for the fusion structural materials 48Ti, 63Cu and 90Zr. Appl. Radiat. Isot., Oct. 2018; vol. 140, pp. 29–34, doi: 10.1016/j.apradiso.2018.06.013
  8. Koning A, Hilaire S and Goriely S. Talys-1.9: A nuclear reaction program manual, p. 781, 2017
  9. Koning AJ, Hilaire S and Goriely S. Global and local level density models. Nucl. Phys. A, 2008; vol. 810, no. 1–4, pp. 13–76, doi: 10.1016/j.nuclphysa.2008.06.005
  10. Gilbert A and Cameron AGW. A Composite Nuclear-Level Density Formula with Shell Corrections. Can J Phys, Aug. 1965; vol. 43, no. 8, pp. 1446–1496, doi: 10.1139/p65-139
  11. Grossjean MK and Feldmeier H. Level density of a Fermi gas with pairing interactions. Nucl. Phys. A, Oct. 1985; vol. 444, no. 1, pp. 113–132, doi: 10.1016/0375-9474(85)90294-5
  12. Demetriou P and Goriely S. Microscopic nuclear level densities for practical applications. Nucl. Phys. A, Dec. 2001; vol. 695, no. 1–4, pp. 95–108, doi: 10.1016/S0375-9474(01)01095-8