Forthcoming and Online First Articles

International Journal of Nuclear Energy Science and Technology

International Journal of Nuclear Energy Science and Technology (IJNEST)

Forthcoming articles have been peer-reviewed and accepted for publication but are pending final changes, are not yet published and may not appear here in their final order of publication until they are assigned to issues. Therefore, the content conforms to our standards but the presentation (e.g. typesetting and proof-reading) is not necessarily up to the Inderscience standard. Additionally, titles, authors, abstracts and keywords may change before publication. Articles will not be published until the final proofs are validated by their authors.

Forthcoming articles must be purchased for the purposes of research, teaching and private study only. These articles can be cited using the expression "in press". For example: Smith, J. (in press). Article Title. Journal Title.

Articles marked with this shopping trolley icon are available for purchase - click on the icon to send an email request to purchase.

Online First articles are published online here, before they appear in a journal issue. Online First articles are fully citeable, complete with a DOI. They can be cited, read, and downloaded. Online First articles are published as Open Access (OA) articles to make the latest research available as early as possible.

Open AccessArticles marked with this Open Access icon are Online First articles. They are freely available and openly accessible to all without any restriction except the ones stated in their respective CC licenses.

Register for our alerting service, which notifies you by email when new issues are published online.

International Journal of Nuclear Energy Science and Technology (3 papers in press)

Regular Issues

  • Comparison of TRIGA reactor steady-state thermal-hydraulic predictions by COMSOL multiphysics with experimental data   Order a copy of this article
    by Ahmed K. Alkaabi, Jeffrey King 
    Abstract: This paper presents United States Geological Survey TRIGA one- and multiple-channel thermal hydraulic (TH) models developed using the COMSOL code to examine the effects of coolant cross-flow on coolant, cladding, and fuel temperatures. There are considerable variations in the profiles of the coolant axial temperatures and outlet temperatures as predicted by multiple-channel model from those predicted by the one-channel model. The one-channel model forecasts that the temperature of the coolant within the fuel rings increases axially with the height of the core, whereas the temperature of the coolant predicted by the multiple-channel model increases as a function of core height in the B-, C-, and D-rings, peaks and then reduces within the E-, F-, and G-rings. Within the multiple-channel model, the coolant appears to flow from the cores outermost opening at the lower side to the centre of the core. Finally, predictions of all models are benchmarked with the experimental data.
    Keywords: TRIGA reactors; multiple-channel models; thermal hydraulic analysis.

  • Effect of nanovoids on the displacement cascades and mechanical properties in INCOLOY-800H: A molecular dynamics study   Order a copy of this article
    by M. Mustafa Azeem 
    Abstract: Nickel-based alloys are candidate materials for high-temperature applications due to their excellent corrosion resistance and mechanical properties than zirconium alloys. However, they are susceptible to the formation of voids and defects at the interfaces between two metallic layers. We have used molecular dynamics simulation to study the interaction of nanovoids created at the multi-layered metallic composite (MMLC) interfaces. We considered the INCOLOY 800H-Ni MMLC as the model material and investigated the effect of nanovoid of different sizes (r~1-4nm) at the interfaces under simulated at 1000K. The collision cascade is simulated by performing 1, 5, and 10 keV randomly selected primary knock-on atoms (PKA) in the Incoloy part. We investigated the evolution of damage cascades at the interface, revealing the presence of a critical nanovoid size below which the nanovoids are not stable under irradiation, i.e., rcritical 2 nm. The damage cascade profile is independent of the incident energy of PKA. The presence of nanovoids at the interface act as a sink for radiation defects.
    Keywords: molecular dynamics; nanovoids; irradiation; mechanical properties.
    DOI: 10.1504/IJNEST.2023.10059803
  • Safety analysis of spent fuel storage facility for BAEC TRIGA research reactor using MCNP5   Order a copy of this article
    by Md. Abdul Malek Soner, Hasan Rakibul, Abdullah Al Mahmud, Nusrat Jahan, Mohammad Mezbah Uddin, Ashraful Haque, Mohamad Hairie Bin Rabir 
    Abstract: Storage of spent nuclear fuel of research reactor is a challenge as storage could be needed for more than 50 years until a decision about the disposal The paper describes the research work to analyze safety features of the wet type spent fuel storage facility for BAEC TRIGA Research Reactor (BTRR) MCNP5 code was used to design 7
    Keywords: BTRR; criticality; spent fuel; wet storage.
    DOI: 10.1504/IJNEST.2024.10064588