Forthcoming articles

International Journal of Nuclear Energy Science and Technology

International Journal of Nuclear Energy Science and Technology (IJNEST)

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International Journal of Nuclear Energy Science and Technology (5 papers in press)

Regular Issues

  • Burn/breed: a wavelet-based nuclear fuel burnup and decay heat code   Order a copy of this article
    by Hesham Nasif 
    Abstract: Burn/breed is a code designed to aid in the analysis, prediction and optimisation of fuel burnup performance and decay heat calculation in a nuclear reactor. The code uses the output parameters generated by the Monte Carlo neutronics codes to determine the isotopic inventory as a function of time and power density. Burn/breed directly uses the neutron absorption tally/reaction information generated by Monte Carlo code for each nuclide of interest to determine the nuclide inventory. When the isotope inventories have been calculated for a specific reactor operation and cooling period, the decay heat can be derived. Beside the U-235 and Pu-239 decay chains, the code includes the U-233 decay chain to manage the possible scenarios for using thorium in a nuclear fuel cycle. This paper describes the theoretical basis of this code, and shows the results of the code for two test cases. The results show good agreement with other codes for the first test case and with the experimental results for the second test case.
    Keywords: burn/breed; burnup; decay heat; nuclear reactor; Monte Carlo; isotopic inventory; wavelet; U-233 decay chain.

  • Neutronics design study of an advanced lead-cooled modular nuclear reactor   Order a copy of this article
    by Donny Hartanto, Safa Alhamad, Khadijah Mahmoud, Nirmin Kurdi, Muhammad Zubair 
    Abstract: A design of an advanced small modular reactor with long-life core is studied in this paper. The core is designed to produce 45 MWth power with a lifetime of 20 years without refuelling. In order to achieve a compact design and have a good neutron economy, lead is considered as the coolant owing to its excellent neutronics and thermophysical properties. However, the lead coolant speed in the core is limited to 2 m/s to minimise the corrosion and erosion of the structural materials. On the other hand, U15N is used as the fuel which reflects excellent thermophysical properties and compatibility with lead. In this study, the neutronics properties of the core including the reactivity evolution during its lifetime, the control rod worth, and the fuel and coolant reactivity feedbacks are evaluated. It was found that ALMANAR could achieve a long-life core of about 22 effective full power years with excellent inherent safety features. Monte Carlo Serpent code is used to perform the calculations in conjunction with the latest nuclear data library ENDF/B-VIII.0.
    Keywords: ALMANAR; long-life core; lead coolant; U15N; Serpent; ENDF/B-VIII.0.

  • Radioactivity Levels of 238U, 234Th, 40K and 137C in the surface soil of selected regions from Baghdad Governorate   Order a copy of this article
    by Noor Adil, Sameera Ahmed Ebrahiem 
    Abstract: Eighteen soil samples were taken from different locations of Baghdad, the capital of Iraq, with a depth of (0-15) cm, and analysed using HPGe detector gamma-ray spectroscopy to determine the specific activity of 238U, 232Th, 40K, and 137Cs as well as the hazard indicators of gamma radiation. According to the values on UNSCEAR, the results presented that the average of specific activity for 238U and 232Th was (15.692
    Keywords: exposure; HPGe detector; hazard indicators.

  • A systematic investigation on grain size enrichment of radionuclides and assessment of radiation hazards along the southern coastal environment of Kerala, India   Order a copy of this article
    by P.V. Divya, C.S. Kaliprasad, V. Prakash 
    Abstract: The concentration of natural radionuclides, viz. 40K, 226Ra and 232Th, in sand samples collected from southern coastal parts of Kerala were determined by NaI(Tl) detector. The activities obtained for various grain sizes were compared in order to understand the enrichment pattern. Sand with a grain size of 63-125 μm showed enhanced level of radionuclide concentrations. The dose to the populace was also calculated from the activities of radionuclides in order to assess the radiation hazards. The calculated values of risk assessment parameters were not within the safe limits, which indicates the radiation hazards to the population due to these radionuclides are significant. However, the observed dose rates were well below the reported average values for other high background radiation areas. The results of the systematic investigation are presented and discussed here in detail.
    Keywords: grain size; radionuclides; NaI(Tl); enrichment.

  • Light water reactor nuclear power plant commodity cost driver analysis   Order a copy of this article
    by Karen Dawson, Piyush Sabharwall 
    Abstract: Construction costs constitute the largest outlay of a nuclear power plant. Direct costs, such as the cost of materials and installation of materials and equipment, make up the majority of construction expenditures. The purpose of this study is to quantify the cost of the two most abundant materials: concrete and steel. This study shows that a 1% reduction in concrete installation rate results in a 0.6% reduction in concrete costs, and a 1% reduction in the steel installation rate creates a 0.3% reduction in steel costs. The additional cost paid for nuclear-quality concrete is shown to be 23% of total concrete budget. The additional cost paid for nuclear-quality steel is shown to be 41% of the total steel expenditures. These results show that focus on decreasing commodity expenditures (through increasing installation rate) can improve the cost of constructing nuclear power plants.
    Keywords: nuclear energy; construction; concrete; steel; PWR; commodities; nuclear power plant; fission; light water reactors; cost drivers; direct cost.