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Introduction

Nuclear Reactor Thermal Hydraulics (NURETH) represents a series of international forums organized and sponsored to assemble expertise in the field of reactor thermal‐hydraulics and related topical areas. The Chinese Nuclear Society (CNS) and Xi’an Jiaotong University (XJTU) are pleased to host the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH‐17) in Xi’an, Shaanxi, China, on September 3–8, 2017.
Xi’an held the title as China’s capital city for 13 dynasties. The city contains world renowned cultural heritages, which include the Terracotta Warriors and Horses, the Mausoleum of Emperor Qin Shi Huang, City Wall of Ming Dynasty, Forest of Stone Steles, Tang Dynasty Cultural Theme Park, Shannxi History Museum, Big Wild Goose Pagoda, just to name a few. Participants will have unlimited access to enjoy China's splendid ancient civilization in this beautiful city while attending the meeting.
Out of all countries, China has the largest number of nuclear power plants under construction. Following the successes of past meetings, including NURETH‐16 in Chicago, USA, NURETH‐17 aims to provide a forum for international experts and researchers in the field of nuclear reactor thermal hydraulics to share their research and discuss future developments. It will also,be a venue for organizations to showcase their expertise in nuclear reactor technology and exhibit their products and services to the nuclear reactor thermal‐hydraulicscommunity.
World‐class hotels located within walking distance from the Conference Center will hold blocked rooms on the reserve, specifically for the NURETH‐17 participants. Ground transportation from the airport to these selected hotels will be provided complimentary.

Call for paper

Important date

2016-11-15
Abstract submission deadline

Submission Topics

Special Topics

1.Heat Transfer and Other Potential Thermal-Hydraulic Issues Involving ATF
2.CFD Model and Benchmarking in Subchannel Systems
3.Rod Bundle CHF and Mixing Experiments
4.Thermal-Hydraulic Issues Related to Reactor Aging and Life Extension
5.Post Accident Rod Bundle Thermal- Hydraulic Behaviors
6.FHR & MSR
7.Containment Safety Experiments
8.Ocean Condition Thermal-Hydraulic
9.Measurement and Instrumentation for Thermal-Hydraulic Experiments

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Important Date
  • Conference Date

    Sep 03

    2017

    to

    Sep 08

    2017

  • Nov 15 2016

    Abstract Submission Deadline

  • Sep 08 2017

    Registration deadline

Contact Information