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活动简介

The 12th International Topical Meeting on Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-12) will take place in Qingdao City, Shandong Province, China, on October 14-18, 2018, organized by Chinese Nuclear Society (CNS) and jointly co-sponsored by International Atomic Energy Agency (IAEA), American Nuclear Society (ANS), Atomic Energy Society ofJapan (AESJ), Korea Nuclear Society (KNS), German Nuclear Society (KTG) and other societies. It’s hosted by State Power Investment Corporation Research Institute (SPICRI) served as the innovation platform, strategic decision support institution for SPIC which is devoted to nuclear power development and provide green energy in China.

NUTHOS aims to provide an international nuclear communication platform for information and technology exchange in engineering experience, latest research results and future demands on reactor thermal-hydraulics, operation, and safety. Thermal-hydraulics is considered as an important cross-cutting subject in the development, operation and safety assessment of advanced nuclear systems. Operation and Safety of nuclear power plants are two key issues in thesustainable development. 

The first NUTHOS was held in Taipei in 1984 followed by Tokyo (1986), Seoul (1988), Taipei (1994), Beijing (1997), Nara (2004), Seoul (2008), Shanghai (2010), Kaohsiung (2012), Okinawa (2014) and Gyeongju (2016). NUTHOS has attracted high interests of the international nuclear community in nuclear thermal-hydraulics, operation and safety and has become one of the major international conferencesin these fields.

We sincerely invite you to contribute and come for NUTHOS-12. Your gracious presence will be our great honor.

征稿信息

重要日期

2017-11-30
摘要截稿日期
2017-12-31
摘要录用日期

征稿范围

1. Fundamental Thermal-Hydraulics
1.1 Liquid Metal Thermal-Hydraulics
1.2 Two-Phase Flow
1.3 Boiling and Condensation Thermal-Hydraulics
1.4 Turbulence Modeling
1.5 Other Fundamental Issues

2. Computational Thermal-Hydraulics
2.1 Advances in Numerical Methods
2.2 Code Development and V&V
2.3 CFD Method and CFD Applicationto Nuclear Engineering
2.4 Multi-Scale and Multi Physics Coupling Simulation

3. Experimental Thermal-Hydraulics
3.1 Fundamental Thermal-Hydraulics Phenomena
3.2 Advanced Measurement Techniques
3.3 Separate Effects Experiments
3.4 Integral Effect Experiments

4. Safety and Severe Accidents
4.1 Design Base Accidents
4.2 Severe Accidents Analysis, Mitigation and Management
4.3 In-Vessel Related Phenomena
4.4 Ex-Vessel Related Phenomena
4.5 Containment Thermal-Hydraulics and Source Term
4.6 Safety Culture

5. Thermal-Hydraulics and safety of advanced reactors
5.1 Water cooled reactors
5.2 Liquid metal cooled reactors
5.3 Gas cooled reactors
5.4 Molten Salt Reactors
5.5 Small Module Reactors
5.6 Reactors for Other Applications
5.7 Research Reactors

6. Plant Operation and Maintenance
6.1 Plant Transients Behavior and System Improvement
6.2 Operation, I&C and Inspection
6.3 Risk Informed and Performance Based Regulation
6.4 Big Data Application and Related Challenges
6.5 Plant Licensing Renewal and Life Extension

7. Plant Diagnostics and Monitoring
7.1 Plant Simulators, Analyzers and Operator Training
7.2 PRA Application to Design, Operation and Maintenance
7.3 Components Diagnostics and Maintenance
7.4 Fuel Management, Wastemanagement and Radiation Protection on Site
7.5 Environmental Nuclear Safety

8. Special sessions

9. Panel sessions

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重要日期
  • 会议日期

    10月14日

    2018

    10月18日

    2018

  • 11月30日 2017

    摘要截稿日期

  • 12月31日 2017

    摘要录用通知日期

  • 10月18日 2018

    注册截止日期

主办单位
theorem conferences
承办单位
Chinese Nuclear Society (CNS)
International Atomic Energy Agency (IAEA)
American Nuclear Society (ANS)
Atomic Energy Society ofJapan (AESJ)
Korea Nuclear Society (KNS)
German Nuclear Society (KTG) and other societies
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