Showing papers in "Fusion Engineering and Design in 1988"

TL;DR: The specific activity limits for shallow land waste disposal of all long-lived radionuclides with atomic number less than 88 have been calculated using the 10 CFR 61 methodology as mentioned in this paper.

TL;DR: In this article, a scaling law of neutron yield from the repetitive dense plasma focus (RPF) powered by inductively stored energy from a slow capacitor bank as a large fluence neutron source was discussed.

TL;DR: A critical review and analysis of the important FNT testing requirements have been performed and recommendations have been developed for reducing the size of the test matrix and for focusing the testing program on important areas of emphasis.

TL;DR: In this article, the chemical form of tritium release from Li 2 O powder under neutron irradiation at high temperatures ( Φ = 10 8 n/cm 2 · s, 400-700 ° C) were conducted using the research reactor YAYOI at the University of Tokyo to study the chemical forms of the released trittium and the tritiametric release kinetics.

TL;DR: In this article, the 6-phase intermetallic compound, UZr 2.3, was studied at temperatures ranging from room temperature to 973 K at a hydrogen pressure of 10 to 10 5 Pa.

TL;DR: The simulation of disruptions in tokamak devices by electron beams has become a frequently used technique as mentioned in this paper, which has been studied on specimens of stainless steel AISI 316L by optical microscopy, scanning electron microscopy (SEM) and electron microprobe analysis (EMPA).

TL;DR: In this article, a simulation study of air detritiation systems has been performed by bench-scale experiments and computer modeling, and the authors have shown that the overall efficiency of air disentritiation operations in the fusion reactor containment is affected by several factors, which include conversion of gaseous tritium to tritiated water vapor, sorption by materials such as wall and floor, and consequent desorption from these materials back into the reactor containment.

TL;DR: In this article, two structural materials, martensitic steel X18 CrMoVNb 121 and vanadium alloy V3Ti1Si, were studied in respect to their mechanical properties in the Pb 17Li eutectic.

TL;DR: In this article, the structural integrity of the first wall of a fusion reactor after a plasma disruption is evaluated. And the authors focus on the following issues: (1) electromagnetics, (2) heat conduction with melting, (3) structural mechanics when material melts and resolidifies, (4) magnetohydrodynamics of liquid metal with free surface, (5) simple evaluation of coupled problem, (6) lifetime evaluation of first wall and (7) a new concept of thermal-stress-free.

TL;DR: In this article, preliminary temperature transients after plasma shut-down have been assessed assuming one year of nominal running and 100% of load factor, and the results show that no major hazard will arise from a loss of flow accident on a single circuit, while reactor melting could happen in the case of a LOFA in the whole reactor.

TL;DR: In this article, the safety and economic characteristics of the deuterium-tritium (DT), deuteria-deuterium (DD), and deuterion-helium-3 (DHe) fusion fuel cycles have been compared.

TL;DR: In this article, the fusion reaction rate and the fusion neutron yield have been investigated taking into account the effect of fast ions, and the mutual relation of fusion reactivity and QB for each reaction is clarified.

TL;DR: In this article, the authors considered the electromagneto-elastic problem of an electrically conducting finite strip with a finite crack under a uniform electric current flow and a constant magnetic field.

TL;DR: In this paper, an edge-cracked ferritic steel is supported by a steady magnetic field, which deforms the whole body of the steel to fracture in the opening mode of cracking, and the skin effects on the electric current distribution around the crack are discussed in detail.

TL;DR: In this paper, an experimental program was carried out on metals and carbon materials using the 10 MW Neutral Beam Injection Test Stand of the Institute of Plasma Physics of Nagoya University.

TL;DR: In this paper, the response of the first wall and the water-cooled blanket to coolant tube blockage, loss of pumping power and loss of heat sink events has been evaluated.

TL;DR: In this article, a formulation of elastoplastic stress analysis of the laminated structure is shown on the basis of the finite element method using the assumptions of Voigt and Reuss.

TL;DR: A review of the breeding blankets under study in Europe for testing in the Next European Torus is presented in this paper, where the main design features are shown and the thermomechanical problems are discussed.

TL;DR: In this paper, the authors proposed a simple model for enhancing the fusion power multiplication factor (Q) through local thermal instability near the plasma center using a simple transport simulation, in which the profile of the plasma density does not change during the simulation and only the thermal conduction loss is considered.

TL;DR: In this article, the authors investigated the structural response of a NET breeding blanket, consisting of canister type elements, to the rupture of a helium coolant pipe within an element.

TL;DR: In this article, a conceptual design study on a compact reversed field pinch fusion (RFP) core with a solid breeder blanket is presented, which is composed of SiC reinforced blocks which form a stable arch and the stresses in SiC are basically compressive.

TL;DR: In this article, a dimensional analysis is performed to rate metallic and ceramic materials for inertial heat dumps and a detailed analysis is made of the calorimeter of the neutral beams of the Doublet III Big Dee fusion device for long pulse operation.

TL;DR: Based on simple physics, engineering, and economic models among various design parameters of reversed-field pinch (RFP) fusion reactors, a parametric system study program has been developed giving cost of electricity (COE) for a given set of design parameters or a set of parameters giving the minimum COE as mentioned in this paper.

TL;DR: In this article, the impact of uncertainties in neutron cross section data on design parameters such as tritium breeding ratio was analyzed including the uncertainties of the secondary angular and energy distribution of neutrons.

TL;DR: In this article, a new concept is explored in the design of high field, compact aspect-ratio toroidal magnets for tokamak applications, and a new magnet design appears to be particularly well suited to cope with both the centripetal and vertical loads on the magnet, is compatible with the fitting of cooling ducts in the volume of the conductor, and directly provides enough of a poloidal flux swing to drive the bulk of the toroidal plasma current required by the TOKAMAK configuration.

TL;DR: Fusion materials research has been one of the major research areas in the UTBLT Project of the University of Tokyo as mentioned in this paper, which has been focused on heavy radiation effects in metallic first wall materials.

TL;DR: In this article, a liquid metal cooled RFP fusion core is designed in order to attain high cooling ability of the first wall without an excessive MHD pressure drop, the return paths of eddy currents induced in the coolant are minimized.

TL;DR: In this paper, eddy current and stress analysis of a Reversed Field Pinch (RFP) device was carried out and it was confirmed that the one-turn eddy currents flow in the vacuum vessel just after the plasma decays.

TL;DR: In this article, the authors apply particle collector scoops in front of the pumping ducts of axisymmetric divertor/magnetic limiter configurations to enclose a significant fraction of recycling particles.