This paper briefly presents the origin and release of tritium in Heavy Water Reactor(HWR) and the design modification and operating control methods in TQNPP to minimize tritium release.
本文简要介绍了重水堆核电站氚的产生和释放,以及秦山三期为降低氚排放所采取的设计改进和运行控制措施。
Status and Technology of Interim Spent Fuel Dry Storage Facility for PHWR Nuclear Power Plant;
重水堆核电厂乏燃料干式中间贮存现状和技术
Establishment of fire protection plan in Qinshan Phase III PHWR Nuclear Power Plant;
秦山三期(重水堆)核电站消防行动预案体系的建立
Analysis of a small break loss of coolant accident(SB-LOCA) for the latest design of ACR-700 PHWR nuclear power plant(NPP) developed by Atomic Energy of Canada Limited has been per-formed with CATHENA MOD 3.
针对加拿大AECL最新推出的ACR-700先进重水堆核电厂设计,建立CATHENA MOD3。
Manufacturing process of CANDU-6 fuel Bundle for HWR nuclear power station;
重水堆核电站用CANDU-6型燃料棒束的制造工艺
Research on using depleted uranium as nuclear fuel for HWR;
在重水堆中用贫铀作为核燃料的应用研究
Qinshan Phase Ⅲ (CANDU) Nuclear Power Porject Quality Assurance
秦山三期(重水堆)核电站工程质量保证
A Progress Survey of Qinshan Phase Ⅲ (CANDU) Nuclear Power Plant Project
秦山三期(重水堆)核电站工程进展概况
Research of the Improvement of Adjuster Control of Heavy Water Reactor Power Plant;
重水堆核电站调节棒控制改进的研究
Technical improvement in Qinshan Phase Ⅲ nuclear power plant after commercial operation
秦山三期(重水堆)核电站的技术改进
light water cooled heavy water reactor
轻水冷却重水反应堆
heavy-water-moderated water-cooled reactor
重水慢化水冷反应堆
boiling heavy water cooled and moderated reactor
沸腾重水冷却慢化堆
CANDU (Canadian deuterium uranium)
加拿大重水铀反应堆
thorium uranium deuterium zero power reactor
重水零功率钍 铀反应堆
enriched uranium heavy water moderated reactor
浓缩铀重水慢化反应堆
deuterium moderated pile low energy
低功率重水慢化反应堆
heavy-water-moderated gas-cooled reactor
重水慢化气冷反应堆
SCHWR (Steam-Cooled Heavy Water Reactor)
蒸汽冷却式重水反应堆
Canadian Deuterium-Uranium Reactor
加拿大重水铀反应堆(坎杜型反应堆)
heavy water moderated pressurized heavy water cooled reactor
重水慢化加压重水冷却反应堆
candu pressurized heavy water cooled
加拿大重水慢化加压重水冷却反应堆
External Reactor Vessel Cooling Measure in Severe Accident for Pressurized Water Reactor Nuclear Power Plant
压水堆核电厂严重事故下堆腔注水措施研究
heavy water moderated boiling light water cooled reactor
重水慢化沸腾轻水冷却反应堆
