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EDF energy advanced gas-cooled reactor (AGR) flux detector programme - Presentation to the Nuclear Engineering for Safety, Control and Security Institute of Engineering and Technology Conference

机译：EDF能源先进气冷堆（AGR）通量检测器计划-向安全，控制和安保核工程技术研究所会议介绍

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《2015 Nuclear Engineering for Safety, Control and Security》|2015年|1-25|共25页
会议地点 Bristol(GB)
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1. Discussion on ????????The application of digital computers to nuclear-reactor design????????, ????????Temperature transients in gas-cooled thermal nuclear reactors????????, ????????The design, performance and use of fission counters???????? and ????????Boron trifluoride proportional counters???????? before the meeting of the Measurement and Control Section held in conjunction with the British Nuclear Energy Conference, 4th February, 1958 [J] . Proceedings of the IEE - Part B: Radio and Electronic Engineering . 1958,第22期

机译：关于数字计算机在核反应堆设计中的应用的讨论气冷热核反应堆中的温度瞬变裂变计数器的设计，性能和使用和????????三氟化硼比例计数器????????在1958年2月4日与英国核能大会联合举行的测量与控制部门会议之前
2. Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Using British Advanced Gas-Cooled Reactor (AGR) Refueling Technology and Decay Heat Removal Systems That Prevent Salt Freezing [J] . Forsberg Charles, Wang Dean, Shwageraus Eugene, Nuclear Technology . 2019,第9期

机译：采用英国先进的气冷反应堆（AGR）加油技术和防止盐冻结的衰变除热系统的氟化物盐冷高温反应堆（FHR）
3. Development of a Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Using Advanced Gas-Cooled Reactor (AGR) Technology [J] . Charles Forsberg, Joshua Richard, Justin Pounders, Transactions of the American nuclear society . 2015,第juna期

机译：使用先进的气冷反应堆（AGR）技术开发氟化物盐冷的高温反应堆（FHR）
4. EDF energy advanced gas-cooled reactor (AGR) flux detector programme - Presentation to the Nuclear Engineering for Safety, Control and Security Institute of Engineering and Technology Conference [C] . Nuclear Engineering for Safety, Control and Security . 2015

机译：EDF能源先进的气体冷却反应器（AGR）助焊剂探测器程序 - 介绍安全，控制和技术会议安全，控制和安全研究所的核工程
5. Retracted: “Benchmark Thermodynamic Modelling Comparison of a Novel Modular Air-Cooled Condenser With Current Dry-Cooling Methodologies” ASME 2016 Power Conference collocated with the ASME 2016 10th International Conference on Energy Sustainability and the ASME 2016 14th International Conference on Fuel Cell Science, Engineering and Technology, ASME 2016 Power Conference, Charlotte, North Carolina, USA, June 26–30, 2016, Conference Sponsors: Power Division, Advanced Energy Systems Division, Solar Energy Division, Nuclear Engineering Division, ISBN: 978-0-7918-5021-3. Paper No. POWER2016-59589, pp. V001T04A010; 9 pages; doi:10.1115/POWER2016-59589 [O] . 2016

机译：缩回：“具有当前干式冷却方法的新型模块化空气冷凝器的基准热力学建模比较”ASME 2016电力会议与ASME 2016年第10届能源可持续性国际会议和ASME 2016年第14届燃料细胞科学会议。工程和技术，ASME 2016 Power会议，夏洛特，北卡罗来纳州，2016年6月26日，2016年6月26日，会议赞助商：电力部门，高级能源系统师，太阳能师，核工程师，ISBN：978-0-7918- 5021-3。纸质号POWE116-59589，PP。V001T04A010; 9页; DOI：10.1115 / power2016-59589
6. Proceedings of the U.S. Nuclear Regulatory Commission Water Reactor Safety Information Meeting (19th). Volume 3. Structural Engineering, Advanced Reactor Research, Advanced Passive Reactors, Human Factors Research, Human Factors Issues Related to Advanced Passive LWRs, Thermal Hydraulics, Earth Sciences. Held in Bethesda, Maryland on October 28-30, 1991 [R] . Weiss, A J 1992

机译：美国核管理委员会水反应堆安全信息会议记录（第19期）。第3卷。结构工程，先进反应堆研究，先进被动反应堆，人为因素研究，与先进被动轻水堆相关的人为因素问题，热工水力学，地球科学。 1991年10月28日至30日在马里兰州贝塞斯达举行

EDF energy advanced gas-cooled reactor (AGR) flux detector programme - Presentation to the Nuclear Engineering for Safety, Control and Security Institute of Engineering and Technology Conference

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