Overview Water Cooled Reactors Group

Transcription

1 Overview Water Cooled Reactors Group Mark Harper, Matt Krause, Katsumi Yamada, Chad Painter 25 November 2014 Nuclear Power Technology Development Section Division of Nuclear Power Nuclear Energy Department

2

3

4 Department of Nuclear Energy Water Cooled Reactors Non-Electric Applications Nuclear Power Technology Development Section Gas Cooled Reactors Small and Medium Sized Reactors Fast Reactors

5 NPTDS 5

6 IAEA 350M MT NE NA 39.1 TC NS SG

7 NE 40M NS 5.7 DDG NEFW NENP

8 NENP 12.1M NPTDS NPES INPRO NIDS

9 NPTDS 2.7M NPTDS Non Electric SMR WCR FR & GCR

10

11 Water Cooled Reactors Group 1.1 Million

12 Monitor worldwide activities on technology development for WCRs Facilitate exchange of information among IAEA Member States on technology development for WCRs Foster international collaboration on technology development for WCRs Support near term development and deployment for both emerging and existing countries in WCR technology Provide technology training in WCR technology

13 Water Cooled Reactors Group 1.1 M CRPs ICSPs Simulators RTA, TC Projects Courses, Schools Technical/Consultants Meetings Nuclear Safety Action Plan International Meetings Publications Data Bases

14 Water Cooled Reactors Group CRPs ICSPs Simulators RTA, TC Projects Courses, Schools Technical/Consultants Meetings Nuclear Safety Action Plan International Meetings Publications Data Bases

15 New CRP on Thermal-hydraulics of SCWRs The 1 st RCM held on October Participating Institutes from 10 Member States CNL, Canada UOIT, Canada CIAE, China SJTU, China KIT, Germany BME, Hungary BARC, India U. of Pisa, Italy Gidropress, Russia NTUU KPI, Ukraine U. of Sheffield, UK U. of Wisconsin, USA OECD/NEA More application-oriented CRP than the previous one for SCWR development.

16 CRP on Computational Fluid Dynamics 1 st RCM held on July Participating Institutes from 10 Member States; Canada USA (2) China Germany India Italy Russia (2) France (2) Algeria Switzerland

17 CRP on Prediction of Axial and Radial Creep in HWR Pressure Tubes 1 st RCM in Vienna July 2013, 2 nd RCM in Ottawa July Participating Institutes from 5 Member States CNEA Argentina CIAE (China) cancelled CNL, COG, Candu Energy Canada BARC India KAERI Korea INR Romania PHOTO HERE

18 CRP on Prediction of Axial and Radial Creep in HWR Pressure Tubes

19 Water Cooled Reactors Group CRPs ICSPs Simulators RTA, TC Projects Courses, Schools Technical/Consultants Meetings Nuclear Safety Action Plan International Meetings Publications Data Bases

20 International Collaborative Standard Problems (ICSPs) Ongoing: HWR Moderator SubcoolingRequirements to Demonstrate Backup Heat Sink Capabilities of Moderator during Accidents ( ) Prediction of Hydro-Mechanical Behaviour in Reactor Core with Plate-Type Fuel Assembly ( ) Recently completed: IAEA-TECDOC-1733 Evaluation of Advanced Thermohydraulic System Codes for Design and Safety analysis of Integral Type Reactors, 2014 (ICSP). IAEA-TECDOC-1727 Benchmarking Severe Accident Computer Codes for Heavy-Water Reactor Applications, 2013 (CRP).

21 ICSP on HWR Moderator Subcooling Requirements to Demonstrate Backup Heat Sink Capabilities of Moderator during Accidents (8 Institutes from 4 Member States) Experiment conducted in June 2013 at CRL 2 nd CSP workshop in July 2014 at VIC test results and blind calcs Last workshop (TM) planned for January 2015 at VIC open calcs Voltage Leadwire Tap Thermocouple Support Insulation Buss Bar 900 mm Graphite Heater 950 mm Buss Bar Seal Ring Pressure Tube 1750 mm Calandria Tube 1700 mm Subcooled Water 21

22 ICSP on Prediction of Hydro-Mechanical Behaviour in Reactor Core with Plate-Type Fuel Assembly (9 Institutes from 7 Member States) Experiment conducted in October 2013 at Oregon State University 1 st TM in July 2014 at OSU planning of test and blind calcs 2 nd TM planned for next week at VIC test results and open calcs 2xBulkFlowRate[gpm] 3 x Bulk Fluid Temperature [ F] 4 x Strain [%] 1xPressure Drop[psid] 7 x Static Pressure [psig] 7 x Total Pressure [psig] 1 x Static Pressure [psig] 3 x Bulk Fluid Temperature [ F] 22

23 Water Cooled Reactors Group CRPs ICSPs Simulators RTA, TC Projects Courses, Schools Technical/Consultants Meetings Nuclear Safety Action Plan International Meetings Publications Data Bases

24 PC-Based Simulators Simulators provided free of charge to MSs Educational purposes Collection of 8 simulators Conventional PWR Passive PWR Russian-type VVER Korean-type Large PWR Conventional BWR Passive BWR Conventional PHWR Advanced PHWR

25 Course on PC-Based Simulators Organized and hosted by TECNATOM, Madrid, Spain, 4-15 November 2013, in cooperation with the IAEA 2-week Course on "Physics and Technology of WCR through the Use of PC-Based Simulators" Attended by 12 participants from 8 Member States

26 Technical Meeting on Effective Utilization of Nuclear Power Plant Simulators as Introductory Educational Tools Held in Vienna, May 2014 Attended by 25 participants from 16 countries Objective Learn how basic principle simulators are being used in educational and training programmes, and Discuss how improvements in these tools can enhance future learning experience.

27 Future Simulator Training Courses December 2014 Malaysia Nuclear Agency Funded by Technical Cooperation February 2015 International Centre for Theoretical Physics Jointly funded by ICTP & IAEA NIDS May 2015 Korea Atomic Energy Research Institute (KAERI) IAEA will be a co-sponsor

28 Water Cooled Reactors Group CRPs ICSPs Simulators RTA, TC Projects Courses, Schools Technical/Consultants Meetings Nuclear Safety Action Plan International Meetings Publications Data Bases

29 Vietnam 06/13

30 Saudi Arabia 11/13

31 Bangladesh 03/14

32 Republic of Korea 04/14

33 Algeria 10/14

34 TC Project Romania (2014/15) Improve methods and tools used in nuclear knowledge management for assuring the safe and economical operation of nuclear facilities in Romania. Capacity building, human resource development and knowledge management

35 Water Cooled Reactors Group CRPs ICSPs Simulators RTA, TC Projects Courses, Schools Technical/Consultants Meetings Nuclear Safety Action Plan International Meetings Publications Data Bases

36 3 rd Course on Science and Technology of SCWRs Organized and hosted by Shanghai Jiao Tong University (SJTU), Shanghai, China, August 2013, in cooperation with the IAEA; Attended by 22 participants from 6 Member States; 21 lectures and Team Activities; and Excellent feedback 36

37 10th Course on Natural Circulation and Passive Safety Systems Organized and hosted by BARC, Mumbai, India October 2014 Attended by 49 participants from 9 Member States;

38 3 rd Inter-Regional Workshop on Good Practices in HWR Operation Under TC Project INT November 2013, Argentina

39 IAEA Inter-Regional Training Course on Heavy Water Reactors Available for Near-term Deployment Planned Under TC Project INT2014 Local Organizers UOIT and Candu Energy Toronto, Ontario, Canada, April 2015

40 Water Cooled Reactors Group CRPs ICSPs Simulators RTA, TC Projects Courses, Schools Technical/Consultants Meetings Nuclear Safety Action Plan International Meetings Publications Data Bases

41 TWG-LWR & TWG-HWR Meeting June 2013 Vienna, Austria

42 2 nd Technical Meeting on Materials and Chemistry for SCWRs Held in Chengdu, China, July 2013 Hosted by Nuclear Power Institute of China (NPIC), China National Nuclear Corporation (CNNC) Attended by 22 participants from 6 Member States 12 presentations and and technical talks

43 Technology Assessment for Embarking Countries June 2013

44 Water Cooled Reactors Group CRPs ICSPs Simulators RTA, TC Projects Courses, Schools Technical/Consultants Meetings Nuclear Safety Action Plan International Meetings Publications Data Bases

45 Fukushima Actions CM on Research and Development to Cope with Fukushima-type Accidents at the IAEA Headquarters, Vienna, Austria, 9-12 December 2013 IEM on Strengthening Research and Development Effectiveness in the Light of the Accident at the Fukushima Daiichi Nuclear Power Plant approved and to be held next February, 2015 Proposal for Reliable Containment Cooling & Filtered Venting (RCCFV) Received funding from Russian Federation to support related Consultancy and Technical Meetings

46 Reliable Containment Cooling & Filtered Venting Previous TWG meeting report concluded, More widespread use of filtered containment venting systems was recommended. NPTDS will host a Consultancy Meeting next week Severe Accident Mitigation through Improvements of Reliable Containment Cooling & Filtered Venting for a DBA and BDBA Purpose: To plan a 2015 Technical Meeting focused on filtered vents and containment cooling systems Goal: Possibly a new TECDOC

47 Water Cooled Reactors Group CRPs ICSPs Simulators RTA, TC Projects Courses, Schools Technical/Consultants Meetings Nuclear Safety Action Plan International Meetings Publications Data Bases

48 International Meetings ICAPP ICONE-21 FISA 2013 Platts SMR International Congress on Advances in Nuclear Power Charlotte, NC USA April 2013 International Conference on Nuclear Engineering Chengdu, China August 2013 Euratom Research and Training in Reactor Systems Vilnius, Lithuania October 2013 Small Modular Reactors Conference Washington, DC USA May 2014 PHWR Safety/ Enhancing safety of PHWR post-fukushima CANSAS-2014 Ottawa, Canada June 2014 ICONE-22 Prague, Czech Republic July 2014 NUSSA Nuclear Safety and Severe Accidents Conference Chiba, Japan September 2014

49 Water Cooled Reactors Group CRPs ICSPs Simulators RTA, TC Projects Courses, Schools Technical/Consultants Meetings Nuclear Safety Action Plan International Meetings Publications Data Bases

50 TECDOC on Evaluation of TH System Codes for Integrated PWRs Published in February 2014; Synthesizing the results from the ICSP on Integral PWR Design, Natural Circulation Flow Stability and TH Coupling of PHTS and Containment during Accidents from 2008 to 2013; with Collaboration among 16 institutes from 6 Member States; Based on two integral tests in OSU MASLWR Test Facility.

51 TECDOC on Heat Transfer Behaviour and Thermo-hydraulics Code Testing for SCWRs Published in August 2014; Synthesizing the results from the CRP on Heat Transfer Behaviour and Thermo-hydraulics Code Testing for SCWRs from 2008 to 2012; Collaboration among 16 institutes from 9 Member States and 2 International Organizations; and Providing most reliable database for thermal-hydraulics of supercritical fluids.

52 Nuclear Reactor Technology Assessment for Near Term Deployment

53 2014 Edition 31 Designs Water & Gas Cooled Sorted by Country General Conference

54 Water Cooled Reactors Group CRPs ICSPs Simulators RTA, TC Projects Courses, Schools Technical/Consultants Meetings Nuclear Safety Action Plan International Meetings Publications Data Bases

55 ARIS: Advanced Reactors Information System IAEA open database of Advanced NPP Design Descriptions All types: LWRs, HWRs, FRs, GCRs (large reactors & SMRs) balanced & objective technical information Design Descriptions: Submitted by Vendors/Design Organizations according to ARIS s Design Description template Reviewed / edited by IAEA For technical clarity (questions are resolved with vendor) Safety levels, costs, schedules etc. are presented as vendor claims or goals Overly commercial statements are removed & English is improved (if necessary) Uploaded after agreement by vendor to the editing Allows sorting and filtering Presently contains 42Design Descriptions (35 are WCRs)

56

57 THERPRO DB Database of Thermo-physical Properties of Materials for Advanced Nuclear Reactors ( THERPRO includes thermo-physical properties for; nuclear fuel materials, cladding and pressure tube materials, absorber materials and their oxides, structural materials coolants (light and heavy water) corium under severe accident conditions THERPRO DB was updated recently July 2014: Consultancy with Professor Yong-soo Kim of Hanyang University in Seoul, Republic of Korea Future Work Verification of upgraded version Establishment of Expert Working Group to provide continued advice on THERPRO and review of new data

58

59

60 Backup Slides

61 Water Cooled Reactors Group 1.1 M