Experiments were performed on Nova at Lawrence Livermore National Laboratory to study the ablation and condensation process of National Ignition Facility (NIF) first wall materials. Plates of candidate first wall materials (SiO{sub 2}, B{sub 4}, and ...
Energy Citations Database
A plasma disruption within a fusion device the size of INTOR can create extensive first wall surface ablation. This paper discusses various first wall ablation models proposed by INTOR participants for the Phase I Design Study, particularly the nonequilib...
National Technical Information Service (NTIS)
We have used the ABLATOR code to analyze the effect of the x-ray emission from direct drive targets on the optics and the first wall of a conceptual laser Inertial Fusion Energy (IFE) power plant. For this purpose, the ABLATOR code has been modified to incorporate the predicted x-ray spectrum from a generic direct ...
The purpose of this paper is to discuss a new plasma disruption model that has been developed for analyzing the consequences to the limiter/first wall structures. This model accounts for: nonequilibrium surface vaporization for the ablating structure, nonequilibrium ionization of and radiation emitted from the ...
Modeling of inertial confinement fusion (ICF) target chamber phenomena presents researchers with various technical problems requiring creative solutions. In particular, the wide ranging physical and time scales of the problem give special difficulty when modeling one shot cycle of an ICF target chamber. Ultimately, the goal of the modeling effort is a unified model beginning with target injection ...
NASA Astrophysics Data System (ADS)
The expected high energy fluxes on the first wall during plasma disruption make it necessary to evaluate the thermal response of the first wall material. A model to predict material evaporation and melting, even considering the vapour shielding effect, wa...
The first wall of a fusion reactor must withstand the impact of energetic charged particles and photons escaping from the plasma as well as intense neutron flux. The design and materials selection for the first wall of a fusion reactor represents one of t...
... WALL MATERIALS IN INERTIAL CONFINEMENT FUSION REACTORS,. ... Report Date : MAR 1978. ... of inertial confinement fusion reactor first walls ...
DTIC Science & Technology
This paper parametrically investigates the effects of microexplosion energy on the first wall costs of a 4000 MW/sub t/ ion-beam initiated, inertially confined fusion reactor for several first wall materials. The thermodynamic models and the results for m...
A key to the successful design of a fusion blanket is the distribution of the amount of structural material in the first wall and the blanket enclosing structure. The first wall must support dynamic and static mechanical loads and at the same time sustain...
This paper describes studies on first wall and plasma wall interaction in JT-60. Main results are as follows; (1) To select JT-60 first wall material, various RandD were done in FY1975 (similar to) 1976. Mo was selected as first wall ...
The National Ignition Facility target chamber interior materials and target designs themselves have to be compatible with survival of the final-optics debris shields. To meet the planned maintenance and refinishing rate, the contamination of the debris shields cannot exceed about 1 nm equivalent thickness per shot of total material. This implies that the ...
This report concerns problems involved in recondensing first-wall materials vaporized by x rays and pellet debris in the Cascade inertial confinement fusion reactor. It examines three proposed first-wall materials, beryllium oxide (BeO), silicon carbide (SiO), and pyrolytic graphite (C), paying particular attention ...
The major parameters and properties that impact materials selection and design criteria for the development of the reference first-wall/blanket design of a Tokamak reactor are reviewed. Tradeoffs in the materials selection process for the breeding material, coolant structure, neutron multiplier, and reflector are ...
A summary is given of the status of the tokamak as a reactor concept and the relationship between first wall and blanket materials behavior and reactor design.
The design of a first wall for a 20 MW thermonuclear power laser fusion hybrid reactor is presented. The 20 mm thick graphite first wall is located 3.5 m from the DT microexplosion with a thermonuclear yield of 10 MJ. Estimates of the energy deposition, temperature, stresses, and material ...
DOE Information Bridge
... PERFORMANCE OF THREE ABLATION MATERIALS DURING ... NASA TM X-1330 PERFORMANCE OF THREE ABLATION MATERIALS DURING ...
During the ITER conceptual design study, a property data base was assembled, the key issues were identified, and a comprehensive R D plan was formulated to resolve these issues. The desired properties of candidate ITER divertor, first wall, and blanket materials are briefly reviewed, and the major materials issues ...
During the ITER conceptual design study, a property data base was assembled, the key issues were identified, and a comprehensive R&D plan was formulated to resolve these issues. The desired properties of candidate ITER divertor, first wall, and blanket materials are briefly reviewed, and the major materials ...
This report consists of the following chapters: Chapter A: LIFE Requirements for Materials. Part 1: The structure of the First Wall--Basic requirements; A qualitative view of the challenge; The candidate materials; and Base-line material's properties. Cha...
Resistance to thermal shock fracture of limiter and first wall surface material candidates during plasma disruption heating conditions is evaluated. A simple, figure-of-merit type thermal shock parameter which provides a mechanism to rank material candida...
The 9Cr and 12Cr martensitic/ferritic steels are candidate first wall and blanket materials for application in magnetic fusion energy systems. This paper contains viewgraphs reviewing the attractive properties and the problems associated with using these steels as first wall ...
Operational conditions of the first wall determined with plasma radiations and operational regime of thermonuclear reactor-tokamak have been considered. Basic phenomena determining structural serviceability of materials in different projects of thermonucl...
Thermal, mechanical, and lifetime performance of various first wall and divertor plate materials were examined over a broad range of conditions, representative of those considered for next-generation tokamaks such as FER. Candidate plasma side materials i...
A comparison has been made of the induced radioactivities in the first wall and structural materials of the breeder blanket in the high-flux region for two different fusion-reactor types. One system is the STARFIRE, a tokamak reactor with PCA, a modified stainless steel, as a first wall and a ...
A comparison has been made of the induced radioactivities in the first wall and structural materials of the breeder blanket in the high flux region for two different fusion reactor types. One system is the STARFIRE, a tokamak reactor with PCA, a modified stainless steel, as a first wall and a ...
... Title : APPLICATIONS OF LOW ATOMIC NUMBER CERAMIC MATERIALS TO FUSION REACTOR FIRST WALLS,. Descriptive Note : Final Rept.,. ...
... Title : Ablative Materials. 3. Molding Compounds. Report on Ablative Properties of Materials Molded at Autoclave Pressures,. Corporate Author : ...
An investigation was made of several commercially available ablation mate- ... been conducted to evaluate several ablation materials on the basis of the ...
NASA Website
This paper discusses results of modeling and experiments on the x-ray response of selected materials relevant to NIF target chamber design. X-ray energy deposition occurs in such small characteristic depths (on the order of a micron) that thermal conduction and hydrodynamic motion significantly affect the material response, even during the typical 10-ns ...
This report discusses the materials physics related to D-T operation in TFTR. Research activities are described pertaining to basic studies of hydrogenic retention in graphite, hydrogen recycling phenomena, first-wall and limiter conditioning, surface analysis of TFTR first-wall components, and estimates of the tritium inventory.
A major challenge facing magnetic fusion as a viable, alternative energy source is finding an acceptable reactor first wall material. One solution may come in the form of lithium as a liquid metal. Liquid metal could act as a self-replenishing first wall,...
Information about first walls in existing fusion reactor conceptual designs has been gathered, organized, and tabulated. The information includes geometrical arrangements, material selections, and operating conditions (temperature, pressure, radiation, an...
Graphite is the most extensively used first-wall material in tokamaks. Drawbacks of graphite are its erosion and its hydrogen retention capacity under plasma exposure. This study investigated these phenomena by performing controlled plasma simulation expe...
This report summarizes the results of the thermal and hydraulic analysis on a magnetic fusion power reactor first-wall design that will be tolerant to minor coolant leaks. The design uses stainless steel as a structural material, liquid lithium as a heat ...
The high temperature design rules of the ITER Structural Design Criteria (ISDC), are applied to first wall designs with high heat flux. The maximum coolant pressure and surface heat flux capabilities are shown to be determined not only by the mechanical properties of the first wall material but ...
A key to the successful design of a fusion blanket is the distribution of the amount of structural material in the first wall and the blanket enclosing structure. The first wall must support dynamic and static mechanical loads and at the same time sustain the thermal gradients and erosion ...
The National Ignition Facility (NIF) will consist of 192 laser beams that have a total energy of up to 1.8 MJ in the 3rd harmonic ({lambda} = 0.35 {micro}m) with the amount of 2nd harmonic and fundamental light depending on the pulse shape. Material near best focus of the 3rd harmonic light will be vaporized/ablated very rapidly, with a significant ...
A brief description of the plasma disruption problem and potential thermal consequences to the first wall is given. Thermal models reviewed include: a) melting of a solid with melt layer in place; b) melting of a solid with complete removal of melt (ablation); c) melting/vaporization of a solid; and d) vaporization of a solid but no ...
An impurity pellet injector is being developed for the RFX reversed field pinch (RFP) with three aims: measurement of the pitch of the magnetic field lines, transport studies, and first wall conditioning. The injector uses pneumatically accelerated metal sabots to launch the pellets. In this way the same barrel can be used for pellets of different sizes, ...
The performance of the ITER first wall and divertor plate is analyzed using a 1-D life-time code which includes the effects of radiation damage and surface erosion. The materials considered for the first wall are solution annealed and 20% cold-worked Type...
In the development of magnetically confined fusion reactors, the ability to cool the first wall, i.e., the first material surface interfacing the plasma, appears to be a critical factor involved in establishing the wall load limit. In order to understand the thermal behavior of the first wall ...
Predictions for NIF ICF target x-ray emission are presented. Validation experiments confirm the key features of the x-ray emissions and their effects on the NIF chamber B{sub 4}C first wall. Predictions of a possible first wall 0.35-{mu}m laser radiation compared to more experimental results conducted to determine ...
... HEAT RESISTANT PLASTICS, *ABLATION), (*REINFORCED PLASTICS, ABLATION), (*THERMOGRAVIMETRIC ANALYSIS, HEAT RESISTANT ...
... AND ABLATION PROGRAM (CMA) FOR CARBON ABLATION ANALYSIS C. CH AN DTIC LECTE ... I AND ABLATION PROGRAM (CMA) FOR ...
Phenolic Impregnated Carbon Ablator was the heatshield material for the Stardust probe and is also a
NASA Technical Reports Server (NTRS)
To accommodate the high heat flux and neutron and gamma heat generation in the first wall of a fusion reactor, an array of tubes or tube-bank forms a first wall shield of the blanket. A series solution to the two-dimensional (in r,theta coordinates), time-dependent heat conduction equation has been found in terms ...
X-ray ablation of material from the first wall and other components of an ICF (Inertial Confinement Fusion) chamber is a major threat to the laser final optics. Material condensing on these optics after a shot may cause damage with subsequent laser shots. To ensure the successful operation of ...
... Title : Analytical and Experimental Study of Ablation Material for Rocket Engine Application. ... materials in liquid-propellant rocket engines. ...
... Title : THE THERMOPHYSICAL PROPERTIES OF ABLATIVE PLASTIC MATERIALS FROM ROOM TEMPERATURE TO DECOMPOSITION. ...
The Reaction kinetics ablation program /REKAP/, developed to simulate ablation of various materials,
... THRUSTERS, STEADY STATE, ABLATION, MATERIALS, SCALING ... NUMERICAL MATHEMATICS RADIOFREQUENCY WAVE PROPAGATION ...
... Accession Number : AD0716825. Title : A Computer Method for the Thermogravimetry of Ablative Plastic Materials. Empirical ...
The choice of material for the first wall of the Light Ion Beam Target Development Facility is discussed. Materials considered are A1 6061, A1 5086, 304 stainless steel, HT-9 (ferritic steel), Ti-6A1-4V, Cu-Be C17200, and Cu-Be C17600. The thermal response, mechanical response and induced radioactivity in ...
The development of the reference STARFIRE first-wall/blanket design involved numerous trade-offs in the materials selection process for the breeding material, coolant structure, neutron multiplier, and reflector. The major parameters and properties that impact materials selection and design criteria are reviewed.
... Abstract : From the standpoint of plasma contamination, Low Z material coating on the first wall of Tokamak is thought to be very effective and one of ...
This paper consists of viewgraphs on the development of structural materials for first wall and blanket applications for both near-term and long-term thermonuclear fusion devices. (LSP)
A thermal/mechanical study has been performed which illustrates the behavior of a fusion reactor first wall and blanket module during a loss of coolant flow event. The relative safety advantages of various material and design options were determined. A generalized first wall-blanket concept was ...
... MATERIALS, POLYMERS, GRAPHITE, REENTRY VEHICLES, CERAMIC MATERIALS, ORGANIC MATERIALS, POROUS MATERIALS, COATINGS ...
Subject Terms: ABLATING MATERIAL; ABLATION; ABLATIVE MATERIALS; APOLLO SPACECRAFT; BOROSILICATE GLASS; COMBUSTION; FORMATION HEAT; HEAT MEASUREMENT; ...
... Accession Number : ADD401770. Title : Vacuum outgassing of ablative heat shield materials for planetary spacecraft. Corporate ...
... Accession Number : AD0180479. Title : The Ablation of Graphitic Materials in the Sublimation Regime,. Corporate Author ...
Procedure for chemical analysis of specimens of silicone-based ablative thermal-insulation materials
... Photographs of ablation materials which experienced reentry on the afterbody of the spacecraft of the Project Mercury mission MA-8 are shown. ...
... Title : PROPERTIES OF ABLATION AND INSULATION MATERIALS-VOLUME II: THERMAL PROPERTIES OF THREE RIGIDIZED FIBROUS ...
Ablation is a process by which the heat shield material is consumed by burning ... Materials that use passive transpiration cooling - ablation - were then ...
... Title : Modifications to the Aerotherm Charring Material Thermal Response and Ablation Program (CMA) for Carbon Ablation Analysis. ...
... Title : Material Performance of Carbon Phenolic Ablators and Pyrolytic Graphite Coatings in Nozzles Subjected to Multiple Pulse Duty Cycles. ...
... of Process and Material Parameters on Ablation Phenomena and Mechanical Properties of Ceramics and Composites for Excimer Laser Treatment. ...
... of laminated materials positioned between ... the conducting material's ablation threshold ... PATENTS, ABLATION, GUN BARRELS, ACCELERATION ...
... Accession Number : AD0751270. Title : Combustion Kinetics of Reentry Vehicle Ablation Materials,. Corporate Author : DREXEL ...
Thermochemical and mechanical ablation mechanisms for Apollo heat shield material, comparing surface
The results of an experimental evaluation of ablative materials suitable for the production of light
