Showing papers in "Nuclear Engineering and Design. Fusion in 1985"

TL;DR: In this article, structural failure modes of low-ductility ceramics are by immediate fracture when a critical stress is applied or by slow crack growth eventually propagating to fracture, both failure modes follow a statistical distribution with a finite probability of failure with low applied loads.

TL;DR: In this paper, the effects of helium on the high temperature mechanical properties of austenitic stainless steel, also known as high temperature helium embrittlement, are reviewed and some suggestions for future work are made.

TL;DR: In this paper, Tungsten is proposed as an appropriate substitution for molybdenum, and the procedures for developing CrW steels analogous to the CrMo steels are discussed.

TL;DR: In this article, a comparison of the tensile properties determined with these different specimens was made by testing cold-worked and solution-annealed Type 316 stainless steel sheet and rod at room temperature, 300°C and 600°C.

TL;DR: In this article, the authors focus on lifetime limitations and capital costs of tokamak subsystems in an attempt to quantify sensitivity to pulsed operation and make a comparison of different operating cycles.

TL;DR: In this article, a study of tensile properties over a wide temperature range (293-1173 K) and at different strain rates between 4 × 10−5 to 4× 10−2s−1 for a high manganese content austenitic steel (Fe-17Mn-10Cr-0.1C) is reported.

TL;DR: In this paper, the lifetime limitations associated with fluctuating thermal loads on the first wall, limiter or divertor plates, and in the breeding blanket of a tokamak were investigated.

TL;DR: In this paper, the microstructural evolution of a fusion neutron radiation effect is discussed from the viewpoint of microstructures evolution, and the implication of these micro-structural studies to the radiation effects relevant to fusion reactor design is discussed.

TL;DR: In this paper, the effects of the eddy currents in the conductive components, such as the first wall, blanket, shield and coil vacuum chamber, on the vertical position control in tokamak reactors are presented.

TL;DR: Several methods for developing design correlations for ferritic steels are discussed in this paper, where the authors develop design equations for use in inelastic structural mechanics applications, for the most important thermal creep parameters.

TL;DR: In this paper, the potential net energy gain from deuterium-tritium-fueled fusion power plants on the basis of tokamak reactors of present-day design is treated in four main sections.

TL;DR: In this paper, the authors describe a general philosophy for such correlation methodologies, provide a brief overview of small specimen test techniques and data characteristics, and demonstrate with several examples how correlations can be developed and applied.

TL;DR: In this paper, the effect of plasma motion on a vacuum vessel and its support structure was analyzed using a code system, MATEX, which was developed for this purpose. And the results indicated that the analysis of the plasma motion is very important to the design of the vacuum vessel.

TL;DR: In this article, a facility for generating engineering data on the nuclear technologies needed to build an engineering test reactor (ETR) is described, based on a tandem mirror operating in the Kelley mode, which can produce a high neutron flux (1.4 MW/m2) on an 8 m2 test area for testing fusion blankets.

TL;DR: In this paper, the influence of primary blanket coolant leaks through flaws in the first wall on Tokamak fusion plasma performance is investigated and a one-dimensional, three region radial diffusion model of impurity transport in the plasma is developed.

TL;DR: In this article, the key features of four recent designs of tandem mirror test facilities (TASKA, TDF, TASKA-M and MFTF-B Upgrade) are compared.

TL;DR: In this article, the effect of the electromagnetic force on fracture phenomena by the electromagnetic forces was analyzed and compared with both numerical analyses and experiments on dynamic fracture caused by the magnetic force.

TL;DR: In this article, a computer code, RAPTOR, was developed to estimate the transport of this activated material throughout a fusion heat transfer and/or tritium breeding material loop.

TL;DR: In this paper, the importance of resonance self-shielding in soft spectrum blankets is confirmed and the resignation of use of moderators in fissile breeding systems is suggested and the necessity of consideration of the resonance selfshielding effects is proven.

TL;DR: In this article, it was shown that this time is short enough to allow a 5 Hz repetition rate for a wide range of parameters for the HIBALL heavy ion beam fusion reactor design, and that the repetition rate is determined by the time required to reestablish this pressure after a shot.

TL;DR: TASKA-M as mentioned in this paper is a conceptual design of a technology test tandem mirror, which utilizes an axisymmetric central cell with hot, mirror-confined ions, and yin-yang MHD anchors.

TL;DR: In this article, a simple comparative study of fissile breeding economics of fusion-fission hybrids, spallators, and also of fast breeder reactors, has been carried out.

TL;DR: TASKA-M as discussed by the authors is a study for a mirror-based D-T plasma device for fusion technology tests, where the axial confinement time is relatively short, resulting in a large gas throughput compared to the fusion power level of 6.8 MW.

TL;DR: In this paper, an analytic method is proposed to determine the startup scenario with the RF current drive, which is obtained from the viewpoint of minimizing the RF injection energy by means of the calculus of variations.

TL;DR: In this article, a finite element code is made to consider an axisymmetric structure loaded by nonsymmetric forces, including the diamagnetic electromagnetic force, toroidal-current-induced-electromagnetic forces, the electromagnetic forces due to toroidal coil current change and saddle shaped electromagnetic forces.

TL;DR: In this paper, the authors describe a new computer code, STAIRE, based on standard beam theory for pipe-bends, which is modified in two areas: (1) consideration of the pipes' cross-section deformation as the radius of curvature changes; and (2) inclusion of inelastic radiation and thermal strains (swelling and creep).

TL;DR: A deuterium-tritium (DT) burning upgrade to the MFTF-B tandem mirror that incorporates a high neutron flux test section in the central cell is described in this article.

TL;DR: The materials test module design for TASKA-M is presented in this article, where a representative 23000 specimen test matrix that utilizes two-thirds of the volume in a single module is described.

TL;DR: In this article, the lifetime prediction of non-cavitating and ideally plastic materials is derived from the solution of the tensile test equation for the particular loading conditions considered, and the corresponding constitutive equation containing the loading conditions as well as the damage function is derived.

TL;DR: TASKA-M as mentioned in this paper is a conceptual design of a low power, low cost test reactor based on a tandem mirror without thermal barriers utilizing physics which is presently in hand, or which should be available by 1985.