タイトル | Preliminary Evaluation of Convective Heat Transfer in a Water Shield for a Surface Power Reactor |
本文(外部サイト) | http://hdl.handle.net/2060/20070013778 |
著者(英) | Pearson J. Boise; Reid, Robert S. |
著者所属(英) | NASA Marshall Space Flight Center |
発行日 | 2007-01-01 |
言語 | eng |
内容記述 | As part of the Vision for Space Exploration, the end of the next decade will bring man back to the surface of the moon. A crucial issue for the establishment of human presence on the moon will be the availability of compact power sources. This presence could require greater than 10's of kWt's in follow on years. Nuclear reactors are well suited to meet the needs for power generation on the lunar or Martian surface. Radiation shielding is a key component of any surface power reactor system. Several competing concepts exist for lightweight, safe, robust shielding systems such as a water shield, lithium hydride (LiH), and boron carbide. Water offers several potential advantages, including reduced cost, reduced technical risk, and reduced mass. Water has not typically been considered for space reactor applications because of the need for gravity to fix the location of any vapor that could form radiation streaming paths. The water shield concept relies on the predictions of passive circulation of the shield water by natural convection to adequately cool the shield. This prediction needs to be experimentally evaluated, especially for shields with complex geometries. NASA Marshall Space Flight Center has developed the experience and facilities necessary to do this evaluation in its Early Flight Fission - Test Facility (EFF-TF). |
NASA分類 | Lunar and Planetary Science and Exploration |
権利 | Copyright, Distribution as joint owner in the copyright |
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