【24h】

Performance test of HTTR

机译:HTTR性能测试

获取原文
获取原文并翻译 | 示例
           

摘要

The high temperature gas-cooled reactor (HTGR) is particularly attractive due to its capability of producing high temperature helium gas and due to its inherent safety characteristics. The high temperature engineering test reactor (HTTR), which is the first HTGR in Japan, was successfully constructed at the Oarai Research Establishment of the Japan Atomic Energy Research Institute. The HTTR achieved full power of 30 MW at a reactor outlet coolant temperature of about 850 ℃ on 7 December 2001 during the 'rise-to-power tests'. Two kinds of tests were carried out during the 'rise-to-power tests'. One is commissioning test to get operation permit by the government and another is test to confirm a performance of the reactor, heat exchanger, and control system. From the test results of the 'rise-to-power tests' up to 30 MW, the functionality of the reactor and the cooling system were confirmed, and it was also confirmed that an operation of reactor facility could be performed safely.
机译:高温气冷堆(HTGR)尤其具有吸引力,因为它具有产生高温氦气的能力以及其固有的安全特性。日本首个高温气冷堆(HTGR)是日本原子能研究所大洗研究所成功建造的高温工程试验堆(HTTR)。在“功率上升试验”期间,HTTR于2001年12月7日在反应堆出口冷却液温度约为850℃的情况下达到了30 MW的全功率。在“功率上升测试”中进行了两种测试。一种是试运行测试,以获得政府的运行许可;另一种是测试,以确认反应堆,热交换器和控制系统的性能。从高达30 MW的“升功率测试”的测试结果中,可以确定反应堆和冷却系统的功能,还可以确保反应堆设施的运行安全。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号