Hualong One's nuclear reactor core design and relative safety issues research
Creators
- 1. Nuclear Power Inst. of China, Design and Research Sub-Inst., Chengdu, Sichuan (China)
Description
'Full text:' Hualong One, a third generation 1000MWe-class pressurized water reactor, is developed by China National Nuclear Cooperation (CNNC), based on the self-reliant technologies and experiences from China 40 years designing, construction, operation and maintenance of NPPs. In China, it has been approved to construct at Fuqing 5&6 and Fangchenggang 3&4. The Hualong One adopts advanced design features to dramatically enhance plant safety, economic efficiency and convenience of operation and maintenance. It consists of three loops with nominal thermal power output 3060 MWt and a 60-year design life. Its reactor core has 177 fuel assemblies, 18 month refueling interval (after initial cycle), and more than 15% thermal margin. It adopts low leakage loading pattern which can achieve better economy of the neutron, higher reactivity and lower radiation damage of pressure vessel. For the safety design, incorporating the feedback of Fukushima accident, the Hualong One has a combination of active and passive safety systems, a single station layout, double containment structure, and comprehensive implementation of defence-in-depth design principles. The new design features has been successfully evaluated to ensure that they enhance the performance and safety of Hualong One. Several experimental activates have been conducted, such as cavity injection and cooling system testing, passive containment heat removal system testing, and passive residual heat removal system of secondary side testing. The future improvements of Hualong reactor will focus on better economic core design and more reliable safety system. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 978-1-926773-20-9
- Imprint Title
- Seventh International conference on modelling and simulation in nuclear science and engineering
- Imprint Pagination
- 48.3 Megabytes
- Journal Page Range
- [1 p.]
Conference
- Title
- 7. International Conference on Modelling and Simulation in Nuclear Science and Engineering
- Dates
- 18-21 Oct 2015
- Place
- Ottawa, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 49003442
- Subject category
- SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Quality check status
- Yes
- Descriptors DEI
- CHINA; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; REACTOR CORES; REACTOR DESIGN; REACTOR SAFETY;
- Descriptors DEC
- ASIA; DESIGN; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTORS; SAFETY; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS;
Optional Information
- Lead record
- 2bb5w-zd889
- Notes
- Paper 7ICMSNSE-Plenary1-3. Short communication. Abstract available only, full text entered in this record.