Hybrid journal (It can contain Open Access articles) ISSN (Print) 1741-6361 - ISSN (Online) 1741-637X Published by Inderscience Publishers[449 journals]

Authors:Abdessamad Didi, Hassane Dekhissi Pages: 216 - 225 Abstract: Accelerator-Driven Subcritical (ADS) reactors are one of the pathways considered for the incineration of minor actinides. They use a proton beam accelerator up to a GeV energy, bombarding a spallation target, usually made of a material of high atomic number (W, Pb, Ta or U). The neutrons generated during the spallation reactions are then multiplied. The main goal of this study is to make a comparison between two models of physical packages via the Monte Carlo code MCNP6. The first package is the INCL4-ABLA and the second one is the CEM03.01, and we have deduced the best package according to the neutron production rate. In this study, we are interested in two cylindrical targets of natural mercury and xenon 20cm in height and 20 in diameter and a proton beam varies from 0.1 to 1.5 GeV. Keywords: spallation; neutron flux; yield neutron; accelerator; high energy; MCNP Citation: International Journal of Nuclear Energy Science and Technology, Vol. 13, No. 3 (2019) pp. 216 - 225 PubDate: 2019-10-22T23:20:50-05:00 DOI: 10.1504/IJNEST.2019.103229 Issue No:Vol. 13, No. 3 (2019)

Authors:Fouad A. Majeed, Fatima M. Hussain, Yousif A. Abdul-Hussien Pages: 226 - 241 Abstract: The effects of coupled-channels in heavy-ion fusion reaction for the system <SUP align=right>40</SUP>Ca + <SUP align=right>192</SUP>Os, <SUP align=right>40</SUP>Ca + <SUP align=right>194</SUP>Pt, and <SUP align=right>48</SUP>Ca + <SUP align=right>197</SUP>Au are discussed. The fusion cross-section σ<SUB align=right>fus, the fusion barrier distribution D<SUB align=right>fus and fusion probability P<SUB align=right>fus are also discussed. The fusion barrier distribution is calculated using numerical three point, five point and Wong methods. Full quantum coupled-channels calculations are performed using CCFULL code with all order coupling to compare and with available experimental data. The χ² values for the case of no-coupling and coupling effects included shows clearly that the present calculations are in agreement with the experimental. Keywords: Wong formula; coupled-channel; CCFULL code; heavy-ion Citation: International Journal of Nuclear Energy Science and Technology, Vol. 13, No. 3 (2019) pp. 226 - 241 PubDate: 2019-10-22T23:20:50-05:00 DOI: 10.1504/IJNEST.2019.103237 Issue No:Vol. 13, No. 3 (2019)

Authors:R. Akbari, D.R. Ochbelagh, A. Gharib Pages: 242 - 260 Abstract: The main purpose of this study is a core neutronic parameter evaluation via the Monte Carlo method, for the SMART reactor which is a certified design Small Modular Reactor (SMR). The SMART neutronic parameters such as axial and radial distributions of neutron fluxes, Power Peaking Factors (PPFs), effective delayed neutron fraction, xenon and samarium effects, burnup calculation and neutron flux energy spectrum have been assessed. Daily load follow operation in soluble-boron-free with control regulating banks is one of the best SMART reactor core advantages. Accordingly, the effects of main regulating bank insertion in SMART core have been evaluated. For developed model verification, some of the neutronic parameters have been compared with the SMART Standard Safety Analysis (SSAR) and show proper match. Then other neutronic parameters of the SMART core as a pioneer SMR have been calculated and evaluated. Keywords: small modular reactor; SMART; neutronic assessment; Monte Carlo method Citation: International Journal of Nuclear Energy Science and Technology, Vol. 13, No. 3 (2019) pp. 242 - 260 PubDate: 2019-10-22T23:20:50-05:00 DOI: 10.1504/IJNEST.2019.103238 Issue No:Vol. 13, No. 3 (2019)

Authors:Khalid S. Jassim, Aqeel I. Faris Pages: 261 - 273 Abstract: The nuclear structure of <SUP align=right>58,62</SUP>Ni nuclei has been calculated using F5PVH as effective interaction for 1f<SUB align=right>5/2 2p<SUB align=right>3/2 2p<SUB align=right>1/2 shell model wave functions. Skyrme-Hartree Fock (SKX), Harmonic Oscillator (HO) and Woods-Saxon (WS) potentials were used to calculate the single particle wave function. The core-polarisation effects have been adopted using the shape of Tassie model. The level schemes are compared with the experimental data up to 3.42 MeV and 4.018 MeV for <SUP align=right>58</SUP>Ni and <SUP align=right>62</SUP>Ni, respectively. In this study, very good agreements are obtained for all nuclei. Results from C2 form factor and Charge Density Distribution (CDD) calculations give good agreement with the experimental data with no adjustable parameters. Keywords: shell model; electron scattering; elastic and inelastic scattering Citation: International Journal of Nuclear Energy Science and Technology, Vol. 13, No. 3 (2019) pp. 261 - 273 PubDate: 2019-10-22T23:20:50-05:00 DOI: 10.1504/IJNEST.2019.103239 Issue No:Vol. 13, No. 3 (2019)

Authors:Zahra Tabadar, Gholam Reza Ansarifar, Kamal Hadad, Masoud Jabbari Pages: 274 - 294 Abstract: Global core calculations use the diffusion equation to predict theoretically the nuclear reactor behaviour. However, this equation is not valid in strong absorbing media where the neutron spectrum is a rapidly varying function of the position, such as control rods or burnable poisons. In this paper, to overcome this misleading, the Monte Carlo simulation has been performed and the VVER-1000 reactor core in the MCL (Reactor Minimally Controlled Power Level) condition is modelled using the MCNPX code to calculate the reactivity worth of the control rod groups. The calculations in this model are divided into four steps. At first, the integral and differential worth are calculated for control groups 8, 9 and 10 with 50% overlapping and shadowing effect is considered. And in three other steps the integral and differential reactivity worths of control groups 8, 9 and 10 are calculated separately (without overlapping). In each step, the core is maintained critical by variation of the boron concentration. In these processes, the boric acid coefficient is achieved while the core is critical. The results are compared with experimental values and are in good agreement with them. Keywords: control rod group; VVER-1000 nuclear reactor; Monte Carlo; reactivity worth calculation; MCNPX code; shadowing effect Citation: International Journal of Nuclear Energy Science and Technology, Vol. 13, No. 3 (2019) pp. 274 - 294 PubDate: 2019-10-22T23:20:50-05:00 DOI: 10.1504/IJNEST.2019.103240 Issue No:Vol. 13, No. 3 (2019)