17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
Xi’an, Shaanxi, China, Sept. 3-8, 2017

Past NURETH Meeting

  • 2015 16th
  • Chicago, USA
  • 2013 15th
  • Pisa, Italy
  • 2011 14th
  • Toronto, CANADA
  • 2009 13th
  • Kanazawa, JAPAN
  • 2007 12th
  • Pittsburgh, USA
  • 2005 11th
  • Avignon, FRANCE
  • 2003 10th
  • Seoul, KOREA
  • 1999 9th
  • San Francisco, USA
  • 1997 8th
  • Kyoto, JAPAN
  • 1995 7th
  • Saratoga Springs, USA
  • 1993 6th
  • Grenoble, FRANCE
  • 1992 5th
  • Salt Lake City, USA
  • 1989 4th
  • Karlsruhe, Germany
  • 1985 3rd
  • Newport, USA
  • 1983 2nd
  • Santa Barbara, USA
  • 1980 1st
  • Saratoga Springs, USA

Important Date

  • Abstract Submission Deadline: Nov. 15, 2016 Dec. 31, 2016
  • Abstract Acceptance Notification: Dec. 15-Dec. 31, 2016
  • Full‐Length Paper Submission: Jan. 9, 2017 - Mar. 31, 2017
  • Full Paper Acceptance Notification: May 26, 2017
  • Final Paper submission: Jun. 23, 2017

The proceeding materials will be distributed in a flash drive. The limit for NURETH‐17 paper submissions is 14 pages and supplemented with a file size less than 10MB.Selected papers will be published on the Special issues of NED, NT, etc.
 
Click here to download the full paper template. Please access to the our meeting system and submit your full paper via:http://epsr.ans.org/meeting/?m=237

 

News & Notice

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Paper Submission Link

Please access to the our meeting system and submit your abstract to preferred track and session

-----------------Call For Papers-----------------

Workshop & Symposium

 

Special Topic

Mini-Symposium: SMR

BEPU workshop: Call for Paper









 
  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
10. OECD R&D Status Report
11. CFD Modeling and Validation for Multi-phase Flows in Nuclear Reactor Systems
12. Space Reactor Thermal Hydraulics
13.  Status of EASY Program 
14. Fukushima Related Topics
15. RELAP Codes: Past, Present, and future

 

 






September 3 - 8, 2017
Qujiang Int’l Conference Center,
Xi’an, China

  • Honorary Chair
  • S. G. Wang (President, XJTU)
  • Honorary Co-Chair
  • N. E. Todreas (MIT)
  • General Chair
  • G. X. Li (President, CNS)
  • General Co-Chairs
  • F. B. Cheung (PSU)
  • J. H. Kim (KAIST)
  • Technical Program Chair
  • B. W. Yang (XJTU)
  • Technical Program Co-Chairs
  • Y. A. Hassan (TAMU)
  • H. Ninokata (POLIMI)

Organisers

Sponsor

Copyright © 2016 Xi'an Jiao Tong University