Fusion Nuclear Science Pathways Assessment | |
C.E. Kessel, et. al. | |
关键词: Diagnostics; Blankets; Computer Simulation; Fusion Power; Fusion Reactors; Design; Materials; Effect of Radiation On; Metals and Metallurgy; Next Step Fusion Devices; Research Devices; Spherical Tokamaks; Steady State Fusion Reactors; Superconducting Magnets; Tokamaks; | |
DOI : 10.2172/1074359 RP-ID : PPPL-4736 PID : OSTI ID: 1074359 |
|
学科分类:原子、分子光学和等离子物理 | |
美国|英语 | |
来源: SciTech Connect | |
【 摘 要 】
With the strong commitment of the US to the success of the ITER burning plasma mission, and the project overall, it is prudent to consider how to take the most advantage of this investment. The production of energy from fusion has been a long sought goal, and the subject of several programmatic investigations and time line proposals [1]. The nuclear aspects of fusion research have largely been avoided experimentally for practical reasons, resulting in a strong emphasis on plasma science. Meanwhile, ITER has brought into focus how the interface between the plasma and engineering/technology, presents the most challenging problems for design. In fact, this situation is becoming the rule and no longer the exception. ITER will demonstrate the deposition of 0.5 GW of neutron heating to the blanket, deliver a heat load of 10-20 MW/m2 or more on the divertor, inject 50-100 MW of heating power to the plasma, all at the expected size scale of a power plant. However, in spite of this, and a number of other technologies relevant power plant, ITER will provide a low neutron exposure compared to the levels expected to a fusion power plant, and will purchase its tritium entirely from world reserves accumulated from decades of CANDU reactor operations. Such a decision for ITER is technically well founded, allowing the use of conventional materials and water coolant, avoiding the thick tritium breeding blankets required for tritium self-sufficiency, and allowing the concentration on burning plasma and plasma-engineering interface issues. The neutron fluence experienced in ITER over its entire lifetime will be ~ 0.3 MW-yr/m2, while a fusion power plant is expected to experience 120-180 MW-yr/m2 over its lifetime. ITER utilizes shielding blanket modules, with no tritium breeding, except in test blanket modules (TBM) located in 3 ports on the midplane [2], which will provide early tests of the fusion nuclear environment with very low tritium production (a few g per year).
【 预 览 】
Files | Size | Format | View |
---|---|---|---|
RO201704190004075LZ | 17973KB | download |