1 / 23

Tilman Drath, Ingo D. Kleinhietpaß, Marco K. Koch

Analysis of the TMI-2 Accident Using ATHLET-CD. Tilman Drath, Ingo D. Kleinhietpaß, Marco K. Koch Lehrstuhl für Energiesysteme und Energiewirtschaft ( LEE ) Ruhr-Universität Bochum ( RUB ) 11 th International QUENCH Workshop Forschungszentrum Karlsruhe , October 25-27, 2005. Outline.

bruno
Download Presentation

Tilman Drath, Ingo D. Kleinhietpaß, Marco K. Koch

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript

  1. Analysis of the TMI-2 AccidentUsing ATHLET-CD Tilman Drath,Ingo D. Kleinhietpaß, Marco K. Koch Lehrstuhl für Energiesysteme und Energiewirtschaft (LEE)Ruhr-Universität Bochum(RUB) 11th International QUENCH WorkshopForschungszentrum Karlsruhe, October 25-27, 2005

  2. Outline • TMI-2 Accident • ATHLET-CD Short Description • Modelling with ATHLET-CD • Calculational Results • Conclusions

  3. TMI-2 Accident • Three Mile Island Unit 2 (TMI-2): • was planned by a number of organisations(i.e. Babcock & Wilcox Inc.), • is banked on the named-giving island in the midst of the Susquehanna River near Harrisburg, USA, beside Unit 1 being still in commercial operation since September 1974, • was completed as 2-Loop American PWR, and • started operation in the end of 1978 with an electrical power of 0.9 GWel and a thermal power of 2.7 GWth. Google Earth

  4. TMI-2 Accident • The TMI-2 accident was initiated by problems on the secondary side of the plant. • These problems finally led to: • the loss of the main feed water pumps and the turbine, • an insufficient low heat dissipation in the steam generators, as well as • a rise of the primary pressure, and finally • the reactor shutdown on the 28th of March 1979 at 04:00:37 h local time.

  5. TMI-2 Accident Sequence of Events and Primary Pressure History PORV Failure!

  6. TMI-2 Accident Postulated Configurations of the TMI-2 Core Before Reflood(174 min) EndstateConfiguration After Refloodand beforeRelocation(224 min)

  7. ATHLET-CD Short Description • ATHLET-CD: Analysis of THermal-hydraulics of LEaks and Transients – Core Degradation • The code is being developed by the Gesellschaft für Anlagen und Reaktorsicherheit (GRS) mbH in Germany. • It deals with the analysis of anticipated and abnormal plant transients, small and intermediate leaks, as well as large breaks in LWRs. • The ATHLET code covers the spectrum of design basis and beyond design basis accidents (without core degradation) for PWRs and BWRs. • The CD part represents an add-on to ATHLET with modules describing core melting, fission product release, as well as fission product and aerosol transport processes in the primary system. Modular structured Code ATHLET-CD

  8. ATHLET-CD Short Description Modular Structure of ATHLET-CD Gesellschaft für Anlagen und Reaktorsicherheit (GRS) mbH

  9. Modelling of the TMI-2 Accident ATHLET-CD Nodalisation of the Plant Loop A Loop B

  10. Modelling of the TMI-2 Accident ATHLET-CD Nodalisation of the Core Cross Connections Bypass CoreReflectorBypass ROD4(OuterRing) ROD2 ROD3 ROD1(InnerRing)

  11. Results of the TMI-2 Calculations Calculated and Measured Primary Pressure History B-Pump Transient High Pressure Injection Heat transfer to the coolant is over-predicted due to the under-estimation of core degradation because of still missing late phase models. End of run using MESOCO!

  12. Results of the TMI-2 Calculations Calculated and Measured Leakage Mass (PORV) Measuring inaccuracy during the trip due to the operation beyond design limits. The mass flow rate is calculated with the critical discharge model and shows a qualitative good result of the accumulated leakage mass.

  13. Results of the TMI-2 Calculations Calculated and Measured Pressuriser Water Level Measuring inaccuracy during the trip due to the operation beyond design limits. Calculated mixture and water level only differ, if the PORV (block valve) is opened, which means a good reproduction of the pressuriser behaviour.

  14. Results of the TMI-2 Calculations Calculated Water-/Steam Distribution History

  15. Results of the TMI-2 Calculations Calculated and Postulated Core Configurationbefore Reflood (174 min)

  16. Results of the TMI-2 Calculations Calculated and Postulated Core Configurationafter Reflood and before Relocation (224 min) Debris bed and molten pool behaviour are not calculable at present!

  17. Results of the TMI-2 Calculations Calculated History of the Core Configuration

  18. Results of the TMI-2 Calculations Calculated and Measured Hydrogen Production The H2 generation is under-predicted during the reflood due to:1.) fuel rod failure and material relocation into deeper core sections,2.) temperatures being too low to contribute significantly to the oxidation rate in the lower core regions,3.) no access of the coolant to the melt because of blockage formation.

  19. Results of the TMI-2 Calculations Calculated Outer Oxide Layer Thickness (240 min) Fuel rod failure:ROD1 and ROD2! Permanent water level!

  20. Results of the TMI-2 Calculations Calculated Fission Product and Structure Material Transportinto the Primary System (240 min)

  21. Conclusions • The thermal-hydraulics are predicted quite well compared to the TMI-2 data, especially if the measuring inaccuracy during the trip due to the operation beyond design limits is taken into account. • The core configurations are calculated in good agreement compared to the postulated status of the core at ascertained times of the sequence. • The H2 generation is under-predicted during the reflood because of fuel rod failure and material relocation into deeper core sections, where the temperatures are too low to contribute significantly to the oxidation rate. Additionally, no access of the coolant to the melt exists because of blockage formation. • The calculated fission product and structure material release as well as their transport in the primary system represent plausible results. • The calculation of the TMI-2 accident using ATHLET-CD in the current program version 2.0A/1.1K shows a good overall code performance. • But the code has, of course, still a potential of improvements in modelling physical phenomena especially concerning the late phase of core degradation and the behaviour and coolability in the lower head.

  22. Acknowledgement • This work is sponsored by the German Federal Ministry of Economics and Labour (BMWA 150 1241). • The authors thank for support and interpretational hints from Dr. Klaus Trambauer (GRS mbH). • Special thanks to all colleagues from the FZK for hosting the QUENCH Workshop.

  23. Analysis of the TMI-2 AccidentUsing ATHLET-CD Tilman Drath,Ingo D. Kleinhietpaß, Marco K. Koch Lehrstuhl für Energiesysteme und Energiewirtschaft (LEE)Ruhr-Universität Bochum(RUB) 11th International QUENCH WorkshopForschungszentrum Karlsruhe, October 25-27, 2005

More Related