PSA Level 2 Source Term Approach in the Loviisa NPP - PowerPoint PPT Presentation

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PSA Level 2 Source Term Approach in the Loviisa NPP

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PSA Level 2 Source Term Approach in the Loviisa NPP T. Routamo, S. Siltanen, P. Lundstr m Fortum Nuclear Services, Finland OECD/CSNI International Workshop on Level ... – PowerPoint PPT presentation

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Title: PSA Level 2 Source Term Approach in the Loviisa NPP


1
PSA Level 2 Source Term Approach in the Loviisa
NPP
  • T. Routamo, S. Siltanen, P. Lundström
  • Fortum Nuclear Services, Finland
  • OECD/CSNI International Workshop on Level 2 PSA
    and Severe Accident Management
  • Köln, Germany, 29-31 March 2004

2
Outline
  • SAM approach of the Loviisa NPP
  • Tool for source term calculation in PSA 2 (SaTu)
  • Sample results
  • Uncertainty calculation
  • Conclusions

3
Loviisa NPP
  • Specific features
  • Ice condenser containment (volume 58 000 m3,
    design pressure of 1.7 bar)
  • Horizontal SGs
  • Low decay power level
  • Narrow reactor cavity
  • No penetration in the RPV lower head

4
SAM Mitigation in the Loviisa NPP
  • Successful containment isolation
  • Primary system depressurisation
  • Mitigation of hydrogen combustion
  • Reactor pressure vessel lower head coolability
    and melt retention
  • Long-term containment cooling

5
SaTu - Introduction
  • Update of Loviisa PSA level 2 for internal events
    in at-power states due in 2004 - SaTu as a new
    source term model
  • Initially built as a support system for radiation
    experts (two modes radiation level mode and PSA
    2 ST mode)
  • Calculations are based on user input and fixed
    parameters modelling the processes and phenomena
    during severe accidents
  • Approach to describe the release from core and
    transport with simple models (implemented in
    Excel)

6
SaTu - Transport solution (basic idea)
  • Constant source (S) and removal rate (k)
  • Source formed as a combination of the release
    from the core and fission product flows from
    consecutive compartments, and averaged in each
    time step
  • Calculation of one compartment at a time
  • Mass loss in the containment loop flow avoided by
    special treatment of the returning mass flow
  • Mathematical solution considered adequate

7
SaTu - System Description (Flow Chart)
8
SaTu - System Description (1)
  • Modelled processes
  • FP and hydrogen release from the core
  • Effect of ECCS injection recovery
  • Deposition in the primary and secondary circuits
    and in the auxiliary system piping
  • Transport along with gas and water flows
  • Deposition in the containment
  • diffusiophoresis
  • sedimentation
  • effect of ice condensers
  • containment spray system
  • containment external spray

9
SaTu - System Description (2)
  • Modelled processes (cont'd)
  • Hydrogen recombination
  • Iodine chemistry (formation of gaseous and
    organic iodine)
  • Leakage out of the containment
  • Transport and deposition in the areas outside the
    containment
  • Release to the environment
  • Parameters affecting the fission product
    behaviour are based on experimental data and code
    calculations.

10
SaTu - Input Data
  • Essential input information
  • LOCA type (used for defining the leak location)
  • Openings through the main deck (containment loop
    flow mode)
  • Time of core uncovery (FP release from degrading
    core)
  • SAM measures (depressurisation, IC doors,
    containment external spray)
  • Possible time of ECCS injection recovery
  • Emergency water resources and sump water level
    (amount of ice in ICs)
  • Containment internal spray flow rate (FP washout)
  • Containment pressure and leakages (FP release out
    of the containment)
  • Ventilation system flow rates (FP transport in
    areas outside the cont.)
  • Status of stack filters (FP retention from stack
    release)

11
SaTu - User Interface
  • Built on several workbooks
  • PSA 2 ST calculation mode
  • User input and FP transport calculation
  • Limited amount of input information
  • Input mainly based on plant measurements
  • Results in a graphical form
  • Additional workbooks in the radiation level mode
  • Activity of radionuclides
  • Coefficients for activity conversion to radiation
    levels
  • Dose rates at control centres and at some
    additional areas
  • Dose rates at a selected time in plant layout
    drawings
  • Pre-calculated accident sequences

12
(No Transcript)
13
SaTu - User Interface (Sample Output)
14
SaTu - User Interface (Sample Output)
15
SaTu - Uncertainty Environment
  • Parameters of the FP modelling not accurately
    known
  • Uncertainty calculation environment was
    implemented
  • Monte Carlo simulation used to study the overall
    effect of the fixed parameter variations
    (sequence uncertainties e.g. timing of events not
    included)
  • A single case runs in SaTu in some seconds
    (immediate result)
  • A thousand case simulation in less than two hours
  • Results shown as percentiles of the FP release
    behaviour
  • Possibility to find out the modelling
    deficiencies

16
SaTu - Uncertainty Calculation Example
17
SaTu - Conclusions
  • Capabilities of SaTu seem adequate, some models
    still need revising though.
  • Issues specifically important (e.g. SAM measures)
    for the Loviisa NPP are included in the system.
  • SaTu is fast-running and easy to use compared
    with integral codes.
  • Uncertainty environment help in justification of
    the reliability of the results.
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