Development of HPR1000 Reactor Core and Primary Circuit
- 1. Nuclear Power Institute of China, Chengdu (China)
Description
HPR1000 reactor core and primary loop is a third generation PWR system designed by Nuclear Power Institute of China (NPIC) based on the experiences of research, design, manufacture, construction and operation of existing pressurized water reactor power plants, and the experience feedback from Fukushima nuclear accident, and considering the preeminent design concept of world-wide advanced nuclear power plants. The reactor core and primary circuit is the core system and engine of HPR1000. This paper presents the design process of HPR1000 reactor core and primary circuit in NPIC based on '177 core'. The design of reactor core, primary circuit and equipment, and experimental verification are introduced to show the advancement, economy, and safety of HPR1000. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 40
- Journal Issue
- S1
- Journal Page Range
- p. 1-7
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 54087830
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CHINA; CONSTRUCTION; DESIGN; EARTH PLANET; ENGINES; EQUIPMENT; FEEDBACK; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; GLOBAL ASPECTS; NUCLEAR POWER; NUCLEAR POWER PLANTS; OPERATION; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; SAFETY; VERIFICATION
- Descriptors DEC
- ACCIDENTS; ASIA; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; PLANETS; POWER; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SITES; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 1 tab., 5 refs.; http://dx.doi.org/10.13832/j.jnpe.2019.S1.0001