1
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Tilman Drath,Ingo D. Kleinhietpaß, Marco K. Koch
Lehrstuhl für Energiesysteme und Energiewirtschaft (LEE)Ruhr-Universität Bochum (RUB)
11th International QUENCH Workshop Forschungszentrum Karlsruhe, October 25-27, 2005
Analysis of the TMI-2 AccidentUsing ATHLET-CD
(RUB)(LEE)
2
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Outline
TMI-2 Accident
ATHLET-CD Short Description
Modelling with ATHLET-CD
Calculational Results
Conclusions
3
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
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
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
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
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
TMI-2 Accident
Sequence of Events and Primary Pressure History
PORV Failure!
6
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
TMI-2 Accident
Postulated Configurations of the TMI-2 Core
Before Reflood(174 min)
After Refloodand beforeRelocation(224 min)
EndstateConfiguration
7
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
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
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
ATHLET-CD Short Description
Gesellschaft für Anlagen und Reaktorsicherheit (GRS) mbH
Modular Structure of ATHLET-CD
9
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Modelling of the TMI-2 Accident
ATHLET-CD Nodalisation of the Plant
Loop ALoop B
10
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Modelling of the TMI-2 Accident
ATHLET-CD Nodalisation of the Core
ROD1(InnerRing)
ROD2ROD3ROD4(OuterRing)
CoreReflectorBypass
BypassCross
Connections
11
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Results of the TMI-2 Calculations
Calculated and Measured Primary Pressure History
B-Pump Transient
High Pressure Injection
End of run using MESOCO!
Heat transfer to the coolant is over-predicted due to the under-estimation of core degradation because of still missing late phase models.
12
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Results of the TMI-2 Calculations
Calculated and Measured Leakage Mass (PORV)
The mass flow rate is calculated with the critical discharge model and shows a qualitative good result of the accumulated leakage mass.
Measuring inaccuracy during the trip due to the operation beyond design limits.
13
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Results of the TMI-2 Calculations
Calculated and Measured Pressuriser Water Level
Calculated mixture and water level only differ, if the PORV (block valve) is opened, which means a good reproduction of the pressuriser behaviour.
Measuring inaccuracy during the trip due to the operation beyond design limits.
14
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Results of the TMI-2 Calculations
Calculated Water-/Steam Distribution History
15
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Results of the TMI-2 Calculations
Calculated and Postulated Core Configurationbefore Reflood (174 min)
16
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
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
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Results of the TMI-2 Calculations
Calculated History of the Core Configuration
18
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
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
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Results of the TMI-2 Calculations
Calculated Outer Oxide Layer Thickness (240 min)Fuel rod failure:ROD1 and ROD2!
Permanent water level!
20
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Results of the TMI-2 Calculations
Calculated Fission Product and Structure Material Transportinto the Primary System (240 min)
Transport Rate[%] of Initial Inventory
Group of SpeciesATHLET-CD
2.0A/1.1KEstimation of Akers et al.(Nuclear Technology, Vol. 87, pp. 205-213)
I, Cs, Xe 53 % 50 %
Te, Sb 5 %1.6 %
(available for Sb only)
Sr 3 % 3.5 %
U, Ag-St 0.4 % -
21
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
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
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
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
Lehrstuhl fürEnergiesystemeund EnergiewirtschaftProf. Dr.-Ing. H.-J. WagnerLEE
Ruh r -Un iver sit ä t Bo ch um
Tilman Drath,Ingo D. Kleinhietpaß, Marco K. Koch
Lehrstuhl für Energiesysteme und Energiewirtschaft (LEE)Ruhr-Universität Bochum (RUB)
11th International QUENCH Workshop Forschungszentrum Karlsruhe, October 25-27, 2005
Analysis of the TMI-2 AccidentUsing ATHLET-CD
(RUB)(LEE)
Top Related