The erosion of a divertor target of beryllium in a fusion reactor is discussed. 讨论了偏滤器铍靶在聚变堆工况下的腐蚀问题。
Results show that the new divertor system can satisfy the plasma discharge for an advanced divertor configuration with some elongation and triangle. 结果表明，新的偏滤器系统新的偏滤器系统能够满足具有一定拉长比和三角形变的等离子体放电要求。
The erosion of a divertor target of beryllium in a fusion reactor is discussed. 讨论了偏滤器铍靶在聚变堆工况下的腐蚀问题。
Results show that the new divertor system can satisfy the plasma discharge for an advanced divertor configuration with some elongation and triangle. 结果表明，新的偏滤器系统新的偏滤器系统能够满足具有一定拉长比和三角形变的等离子体放电要求。
