Design of a delayed neutron detection system for the ASTRID Sodium-cooled fast reactor

机译：青硅酸钠冷却快速反应器的延迟中子检测系统设计

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Delayed neutron detection systems are key apparati in Sodium cooled Fast Reactors to prevent safety accidents. Based on the feedbacks from Phenix and Superphenix, DND systems are studied by means of the Monte-Carlo particles transport code MCNP6. Promising designs are proposed and investigated as a result of the simulation study.

机译：延迟中子检测系统是钠冷却的快电反应器中的关键型助剂，以防止安全事故。基于来自Phenix和Superhenix的反馈，通过Monte-Carlo粒子传输代码MCNP6研究了DND系统。由于模拟研究，提出并调查了有希望的设计。

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《International Conference on Advancements in Nuclear Instrumentation Measurement Methods and Their Applications》|2018年|494p|共3页
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Romain Coulon; Emmanuel Rohee; Jonathan Dumazert; Sara Garti; Philippe Filliatre; Christian Jammes;
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专利

1. Design of a delayed neutron detection system for the ASTRID Sodium-cooled fast reactor [J] . Romain Coulon, Emmanuel Rohée, Jonathan Dumazert, EPJ Web of Conferences . 2018,第2期

机译：ASTRID钠冷快堆的延迟中子探测系统设计
2. Delayed Neutron Detection with graphite moderator for clad failure detection in Sodium-Cooled Fast Reactors [J] . Rohee E., Coulon R., Jammes C., Annals of nuclear energy . 2016,第juna期

机译：带石墨减速器的延迟中子检测，用于钠冷快堆中复合故障的检测
3. NUMERICAL MODELING OF DELAYED-NEUTRON PRECURSOR TRANSPORT IN A SODIUM-COOLED FAST REACTOR [J] . Rogozhkin S. A., Osipov S. L., Salyaev A. V., Atomic Energy . 2020,第4期

机译：钠冷却快速反应器中延迟中子前体转运的数值模拟
4. Design of a delayed neutron detection system for the ASTRID Sodium-cooled fast reactor [C] . Romain Coulon, Emmanuel Rohee, Jonathan Dumazert, International Conference on Advancements in Nuclear Instrumentation Measurement Methods and Their Applications . 2018

机译：青硅酸钠冷却快速反应器的延迟中子检测系统设计
5. Design and Analysis of Sodium-cooled Fast Reactor Systems for Nuclear Waste Minimization [D] . Lin, Ching-Sheng. 2018

机译：用于最小化核废料的钠冷快堆系统的设计与分析
6. Investigation of the Cs2(MoTe)O4 Solid Solution and Implications on the Joint Oxyde-Gaine System in Fast Neutron Reactors [O] . Enrica Epifano, Andrea Volfi, Maas Abbink, -1

机译：快速中子反应堆中Cs2（MoTe）O4固溶体的研究及其对氧-盖因联合体系的影响
7. Liquid salt - very high temperature reactor : survey of sodium-cooled fast reactor fuel handling systems for relevant design and operating characteristics. [O] . Cahalan, J. E., Taiwo, T. A., Division, Nuclear Engineering 2006

机译：液体盐 - 极高温反应堆：调查钠冷却快堆燃料处理系统的相关设计和操作特性。
8. Liquid salt - very high temperature reactor : survey of sodium-cooled fast reactor fuel handling systems for relevant design and operating characteristics. [R] . 2006

机译：液体盐 - 极高温反应堆：调查钠冷却快堆燃料处理系统的相关设计和操作特性。

Design of a delayed neutron detection system for the ASTRID Sodium-cooled fast reactor

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