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Summary: In March 2015, the Kingdom of Saudi Arabia signed an agreement with South Korea to build the system‐integrated modular advanced reactor (SMART) originally developed by the Korean Atomic Energy Research Institute. The SMART is a structurally contained safe dual‐purpose power plant reactor that produces both electricity and desalination. This study aims to design a double‐containment structure with a pool‐type concept to enhance the SMART safety and develop a robust design for future modular reactors. For that purpose, a theoretical model is developed herein, which leads to the modeling of a double‐containment structural design of a water pool. The model calculates various parameters (ie, temperature, pressure, phasic velocities, and condensable gases) and is used to develop a simulation program for use in a computational assessment. Moreover, two best‐estimate thermal hydraulic engineering programs, namely THEATRe and RELAP5, are used to simulate the original SMART with the double‐containment water pool structure. The differences in the modeling strategies of the two simulation techniques are discussed to accurately measure various technical parameters. Accordingly, a nodalization diagram of the reactor and the pool‐type concept are developed and simulated. The results obtained from the computational models yield the error of >2%, depicting accuracy. A small‐break loss of coolant accident is also simulated to mitigate the transient conditions. The result verifies the adoptability of this reactor concept in any other small modular reactor. [ABSTRACT FROM AUTHOR]

In this paper, a novel system has been developed for plasma disruption conditions followed by downward vertical displacement. During the disruption, size and orientation of plasma decreases, which gives the halo current circulated around each contacting point in radial as well as in poloidal directions. Therefore, a new mathematical model has been developed, which gives the interaction forces of halo current, vertical, and radial plasma dynamical behavior (linear and nonlinear). This theoretical approach showed that the tokamak plasma has two connecting points in order to distinguish between the stable and unstable position. This model can particularly give the magnetic field change points and changing of flux, which are more convenient in order to discuss the static and tilting position of plasma behavior. Numerical techniques have been calculated in terms of plasma dynamical behavior, that is, Electromagnetic/plasma, Vertical Displacement Event (VDE) stages, and initial interaction between the forces under specific time interval. The objective of the research is to developed theoretical and computational model in order to investigate the dynamical behavior of plasma under disruption conditions. This is the novel method, and no work has been reported so far. Copyright © 2015 John Wiley & Sons, Ltd. [ABSTRACT FROM AUTHOR]

In this paper, research has been conducting on calculating full plasma energy and magnetic field cross sections in static as well as in tilting position for analyzing plasma vertical displacement event behavior. Consequently, the main concern of the research is to developed plasma energy and shape model. First, the developed 3D shape model allows an effective way to study the shape of plasma behavior of main plasma characteristics under controlled conditions including sensitive dependent on initial condition based on isolated points. Secondly, the developed 3D plasma energy model denotes every calculated point and analyze magnetic field of each cross section under different values of α and β according to magnetic field produced by a circular current loop. This theoretical approach showed that the individual points (( a, b) & ( r, z)) with static and tilting moments are able to develop the three-dimension coordinates system, based on R0 = 1.7 ∼ 1.8, B0 = 3.5 T and plasma current I P ≤ 1 MA. Furthermore, 195 × 12 (both states) circle current loop of magnetic field has been calculated as well. The 'sinβ cross section' for every 30° in both states (static and tilt with alpha variations) calculates the total plasma energy. Therefore, we have developed computational codes in Matlab program to calculate the values of full plasma energy in EAST. Energy from initial to final state, VDE and external force behavior, poloidal and toroidal fix degree of every cross section that depends on each current loop of magnetic field have been analyzed based on whole plasma energy data. Copyright © 2015 John Wiley & Sons, Ltd. [ABSTRACT FROM AUTHOR]

SUMMARY In this paper, three-dimensional (3D) power distribution of newly designed small nuclear reactor core has been achieved by using neutron kinetic/thermal hydraulic (NK/TH) coupling. This is pressurized water reactor-based small nuclear reactor in which plate type fuel element has been used and the core of the reactor has hexagonal type geometry. This paper depicts the design of the reactor core by using coupling approach of neutronics(Neutron Kinetic) and thermal hydraulic studies. For this purpose, neutronic analysis has been obtained by using lattice physics code, i.e. HELIOS and neutron kinetic code, i.e. REMARK. HELIOS code gives the cross-section data which is being used as input to the REMARK code. At the same time, THEATRe code was used for the thermal hydraulic analysis of the reactor core. In the coupling process, some data (fuel temperature, moderator temperature, void fraction, etc.) from THEATRe code has been used in conjunction with HELIOS and REMARK codes. After finalizing the NK/TH coupling, 3D evaluation of the power distribution of the reactor core has been achieved and is included in the paper. The purpose of this paper is to evaluate the design and get the normal operational behavior of the reactor core by NK/TH coupling approach. Copyright © 2012 John Wiley & Sons, Ltd. [ABSTRACT FROM AUTHOR]