Nuclear reactor safetyStation blackoutAPR1400Advanced Power Reactor (APR-1400) is a Generation III+ Pressurized Water Reactor (PWRs) and has gained popularity among energy mix community. APR-1400 features enhanced safety limits to prevent a "Fukushima-type" accident scenario for a duration up to ...
Shin Hanul 2 received an operating licence from the Nuclear Safety and Security Commission on 7 September last year, after which it completed a preliminary inspection by the regulator. The loading of 241 fuel assemblies into the reactor's core was carried out between 11 and 18 September. High-...
The US Nuclear Regulatory Commission has decided not to accept Korea Hydro & Nuclear Power's application for certification of its APR-1400 reactor design, as it contains insufficient information in some areas.[近日,因韩国水电与核电有限公司(KHNP)提交的APR1400堆型设计认证的材料信息不全,美国核管会决...
5. Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors [D] . Galvez, Cristhian 2011 机译:先进核反应堆被动安全冷却系统的设计和瞬态分析 6. Simultaneous Investigation of Three Effective Parameters of Substrate Microorganism T...
A series of sparger tests have been conducted to investigate the performance of a steam sparger, which will be used in a Korean Advanced Power Reactor, APR1400. The tests have been conducted at the Blowdown and Condensation Loop in the Korea Atomic Energy Research Institute using a prototypic ...
- . , .\nFor last 10 years, the standard design of Advanced Power Reactor 1400(AP... Sang-Man,Park,Kwang-Jae,... - 《Journal of the Korea Entertainment Industry Association》 被引量: 0发表: 2010年 Commissioning of the ATLAS thermal-hydraulic integral test facility The ATLAS will mainly...
Monte Carlo Modeling of Isotopic Changes of Actinides in Nuclear Fuel of APR1400 Pressurized Water Reactor The aim of this paper is to present the isotopic changes in nuclear fuel during the first reactor cycle of the Korean Advanced Power Reactor 1400 (APR1400)... J Kim - 《Energies》 被...
Introduction The advanced nuclear power plant, Advanced Power Reactor 1400 MWe (APR1400), has many specific features, such as passive safety facilities, digital instrumentation and control (I&C), and digitalized main control room (MCR). The design concepts of new human-system interfaces (HSIs) ...
If cooling is inadequate during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor... Knudson,D.,L.,... - 《Proceedings of the .international Conference on Nuclear Engineering.book of Abstracts Icone》 被引量: 4发表:...
Multi-dimensional thermal-hydraulic phenomena in advanced nuclear reactor systems: current status and perspectives of the R&D program at KAERI It includes the ECC bypass phenomena in a RPV downcomer during a LBLOCA reflood phase, steam venting through a DVI line break in a upper downcomer of the...