Author: O. K. KvetonPublisher:
ISBN:
Category :
Languages : en
Pages : 38
Book Description
ITER Fuel Cycle Systems Layout
Author: O. K. KvetonIter fuel cycle systems layout - conceptual design
Author: O. K. KvetonPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Zircaloy-4 fuel sheath specimens 15.2 mm diameter by 0.42 mm wall thickness with beryllium-brazed appendages have been laboratory tested at high temperature with internal gas pressurization and inert gas shielding of the outer surfaces. with sufficient hoop stress at temperatures less than 1073 k cracks, which were due to a beryllium assisted crack penetration mechanism, were found to occur at the appendages. formulae to predict the beryllium penetration and rupture have been derived by westinghouse canada ltd. based on data from direct resistance-heated specimens. the formulae are thought to be able to predict the phenomenon in fuel sheaths with changing temperature/pressure histories. a series of tests was done by canadian general electric to determine the formulae ability to predict the occurrence of beryllium assisted crack penetration in specimens heated indirectly with internal heaters. the tests showed: 1) there is an incubation period before any beryllium assisted crack penetration occurs. 2) at sheath temperatures below approximately equal to 1073 k sheath rupture by excessive mechanical strain will preclude rupture by beryllium assisted crack penetration. 3) the formulae predicted rupture times above and below the braze alloy melting temperature within the previously determined confidence limits. 4) predictions of beryllium assisted crack penetration rupture for specimens with changing temperature/pressure histories were of similar accuracy to predictions of isothermal tests. 5) specimens with an appendage plane of one bearing pad and three spacer pads behaved similarly to the specimens with four spacer pads on which the formulae were based.
Possible Design Modifications of ITER Fuel Cycle
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 8
Book Description
During the ITER design phase, the conceptual design of the fuel processing cycle has been established. The fuel processing cycle is designed to be able to handle all the tritium containing streams of the ITER. These streams include plasma exhaust, blanket tritium recovery, pellet propellant, neutron beam exhaust, water coolant detritiation, waste water from the room air detritiation system. The design is very conservative, i.e., the flow rate of each stream is high and the detritiation factor required is very high. A preliminary optimization study has been carried out to simplify the ITER fuel cycle design. We investigated: The throughput and composition of the input tritium containing streams from various components to the fuel processing cycle. The fraction of those streams needed to be detritiated. The required detritiation factors required for each of the streams. The results of the investigation determined that the major input tritium containing steams can be reduced by at least a factor of 10. The required detritiation factor can be reduced from a factor of 100 to 106. The size of the fuel processing cycle, the tritium inventory and the complexity of this system can, therefore, also be reduced.
ITER Fuel Cycle Systems
Author: O. K. KvetonITER Fuel Cycle Systems
Author: O. K. KvetonFusion Reactor Design
Author: Takashi OkazakiPublisher: John Wiley & Sons
ISBN: 3527414037
Category : Science
Languages : en
Pages : 644
Book Description
Fusion Reactor Design Provides a detailed overview of fusion reactor design, written by an international leader in the field Nuclear fusion—generating four times as much energy from the same mass of fuel as nuclear fission—is regarded by its proponents as a viable, eco-friendly alternative to gas-fired, coal-fired, and conventional power plants. Although the physics of nuclear fusion is essentially understood, the construction of prototype reactors currently presents significant technical challenges. Fusion Reactor Design: Plasma Physics, Fuel Cycle System, Operation and Maintenance provides a systematic, reader-friendly introduction to the characteristics, components, and critical systems of fusion reactors. Focusing on the experimental Tokamak reactor, this up-to-date resource covers relevant plasma physics, necessary technology, analysis methods, and the other aspects of fusion reactors. In-depth chapters include derivations of key formulas, figures highlighting physical and structural characteristics of fusion reactors, illustrative numerical calculations, practical design examples, and more. Designed to help researchers and engineers understand and overcome the technological difficulties in making fusion power a reality, this volume: Provides in-depth knowledge on controlled thermonuclear fusion and its large-scale application in both current fusion reactors and future test reactors Covers plasma analysis, plasma equilibrium and stability, and plasma transport and confinement, and safety considerations Explains each component of fusion reactors, including divertors, superconducting coils, plasma heating and current drive systems, and vacuum vessels Discusses safety aspects of fusion reactors as well as computational approaches to safety aspects of fusion reactors Fusion Reactor Design: Plasma Physics, Fuel Cycle System, Operation and Maintenance is required reading for undergraduate and graduate students studying plasma physics and fusion reactor technology, and an important reference for nuclear physicists, nuclear reactor manufacturers, and power engineers involved in fusion reactor research and advanced technology development.
Energy Research Abstracts
Author: Iter fuel cycle systems - cost estimation review
Author: O. K. KvetonPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Stress corrosion cracking can potentially cause fuel failures at circumferential ridges in the sheath. finite element computer codes elestres and feast are used to calculate two-dimensional, axisymmetric, elastic-plastic sheath stresses at and near the circumferential ridges. the level of stresses is given by the fuel design (such as pellet/sheath diameters, pellet length, pellet density) and by the operating conditions (such as power history). the accuracy, convergence, and cost of the stress calculations, however, are determined by the discretization used in the calculations: the number of nodes in the finite element mesh; the shape of the individual finite elements; the pattern into which the finite elements are arranged; and the size of the calculation-steps into which the power history is subdivided. in this study, we determined the discretization that gives a reasonable compromise of accuracy, convergence, and cost for the stress calculations. the highest accuracy is obtained by using triangular finite elements of aspect ratios close to one, and assembling them into hexagonal patterns. to caputure the stress gradients, five nodes are required across the sheath wall at the ridge, but two nodes are sufficient near the midplane of the pellet. the resulting mesh contains about 200 nodes and about 300 finite elements. calculation-steps of 6 kw/m provide a convergent solution, with a factor of two margin against numerical divergence. with the above arrangement, feast needs about 2.4 seconds on a cdc/cyber 175 computer to calculate sheath stresses per calculation-step. six radial nodes at the ridge would double the computing cost. decreasing the size of the calculation-steps means more calculations are needed to analyze a given power history, giving a linear increase in computing cost.
ITER Fuel Cycle
Author: D. LegerSafe Handling of Tritium
Author: International Atomic Energy AgencyPublisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 148
Book Description
This publication contains information on the dosimetry and monitoring of tritium, the use of protective clothing for work with tritium, safe practices in tritium handling laboratories and details of tritium compatible materials. The information has been compiled from experience in the various applications of tritium and should represent valuable source material to all users of tritium, including those involved in fusion R&D.