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Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor coolant system and systems decontamination. Summary status report. Volume 1

机译：评估核设施退役项目。三英里岛单元2反应器冷却剂系统和系统净化。摘要状态报告。第1卷

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D.H. Doerge; R.L. Miller; K.S. Scotti;
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年度 1986
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1. Re-evaluation of spent nuclear fuel assay data for the Three Mile Island unit 1 reactor and application to code validation [J] . Gauld I. C., Giaquinto J. M., Delashmitt J. S., Annals of nuclear energy . 2016,第JANaPTa2期

机译：三英里岛1号反应堆乏核燃料测定数据的重新评估及其在代码验证中的应用
2. Vibration Monitoring System for Elements of the Primary Coolant Circuit of Power Generating Units at Nuclear Power Stations Equipped with VVER-440 Reactors [J] . V. G. Petrosyan, S. V. Shakhverdyan Thermal engineering . 2005,第12期

机译：装有VVER-440反应堆的核电站发电机组一次冷却回路元件的振动监测系统
3. The safety assessment system based on virtual networked environment for evaluation on the hazards from human errors during decommissioning of nuclear facilities [J] . Jeong Kwan Seong, Choi Byung Seon, Moon Jei Kwon, Reliability Engineering & System Safety . 2016,第deca期

机译：基于虚拟网络环境的安全评估系统，用于评估核设施退役期间人为错误的危害
4. IMPACT OF RECENT DEVELOPMENTS ON THE STATUS OF COMMERCIAL NUCLEAR POWER AND REACTOR DECOMMISSIONING IN THE UNITED STATES [C] . Jas S. Devgun ASME international conference on environmental remediation and radioactive waste management . 2014

机译：最新动态对美国商业核能和反应堆退役状态的影响
5. Development of an automatedchemistry control system forsecondary coolant circuits inCANDU nuclear power reactors [O] . J. R. Dean, R. B. Stewart 1979

机译：开发自动化化学控制系统二次冷却液回路坎杜核电反应堆
6. Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor building decontamination. Summary status report. Volume 2 [O] . D.H. Doerge, R.L. Miller, K.S. Scotti 1986

机译：评估核设施退役项目。三英里岛单位2反应堆建筑净化。摘要状态报告。第2卷

Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor coolant system and systems decontamination. Summary status report. Volume 1

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