Modeling, analysis and experiments for fusion nuclear technology
Creators
- 1. California Univ., Los Angeles (USA). Dept. of Mechanical, Aerospace and Nuclear Engineering
- 2. Canadian Fusion Fuels Technology Project, Mississauga, Ontario
- 3. Westinghouse Hanford Co., Richland, WA (USA). Hanford Engineering Development Lab.
- 4. Argonne National Lab., IL (USA)
Description
Selected issues in the development of fusion nuclear technology (FNT) have been studied. These relate to (1) near-term experiments, modeling, and analysis for several key FNT issues, and (2) FNT testing in future fusion facilities. A key concern for solid breeder blankets is to reduce the number of candidate materials and configurations for advanced experiments to emphasize those with the highest potential. Based on technical analysis, recommendations have been developed for reducing the size of the test matrix and for focusing the testing program on important areas of emphasis. The characteristics of an advanced liquid metal MHD experiment have also been studied. This facility is required in addition to existing facilities in order to address critical uncertainties in MHD fluid flow and heat transfer. In addition to experiments, successful development of FNT will require models for interpreting experimental data, for planning experiments, and for use as a design tool for fusion components. Modeling of liquid metal fluid flows is a particular area of need in which substantial progress is expected, and initial efforts are reported here. Preliminary results on the modeling of tritium transport and inventory in solid breeders are also summarized. Finally, the thermo-mechanical behavior of liquid-metal-cooled limiters is analyzed and the parameter space for feasible designs is explored. Because of the renewed strong interest in a fusion engineering facility, a critical review and analysis of the important FNT testing requirements have been performed. Several areas have been emphasized due to their strong impact on the design and cost of the test facility. These include (1) the length of the plasma burn and the mode of operation (pulsed vs. steady-state), and (2) the need for a tritium-producing blanket and its impact on the availability of the device. (orig.)
Additional details
Publishing Information
- Journal Title
- Fusion Eng. Des.
- Journal Volume
- 6
- Journal Issue
- 1
- Series
- Fusion Eng. Des.
- Journal Page Range
- 3-64
- ISSN
- 0920-3796
- CODEN
- FEDEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 19070424
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BREEDING BLANKETS; LIQUID METALS; MAGNETOHYDRODYNAMICS; NUCLEAR ENGINEERING; PLANNING; SIMULATION; SPECIFICATIONS; SYSTEMS ANALYSIS; THERMONUCLEAR REACTOR MATERIAL; THERMONUCLEAR REACTORS; TRITIUM RECOVERY
- Descriptors DEC
- ELEMENTS; ENGINEERING; FLUID MECHANICS; FLUIDS; HYDRODYNAMICS; LIQUIDS; MATERIALS; MECHANICS; METALS
Optional Information
- Contract/Grant/Project number
- Contract DE-FG03-86ER52123