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CSNI0000 I.T.D.

I.T.D., CSNI Integral Test Facility Validation Matrix

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1. NAME OR DESIGNATION:  Integral Test Data.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
I.T.D. CSNI0000/01 Report 05-NOV-1997

Machines used:

No specified machine
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3. DESCRIPTION OF TEST FACILITY

The Integral Experiments are designed to follow the behaviour of a reactor system in various off-normal or accident conditions. The ITD matrix data is suitable for the validation of best estimate thermal-hydraulic computer codes: it consists of phenomenologically well founded experiments, for which comparison of the measured and calculated parameters forms a basis for establishing the accuracy of the test predictions.
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4. DESCRIPTION OF TEST


- TEST TYPES FOR PWRS

    . Test types related to large break LOCAs:
      Blowdown phase,
      Refill phase,
      Reflood phase.

    . Test types related to small break LOCAs:
      Stationary test addressing energy transport on primary side,
      Stationary test addressing energy transport on secondary side,
      Small break overfeed by HPIS, secondary side necessary,
      Small break w/o HPIS overfeeding, secondary side necessary,
      Intermediate break, secondary side not necessary,
      Pressurizer leaks,
      Steam generator tube rupture (SGTR).

    . Test types related to small and intermediate breaks in PWRs
      with OTSGs

    . Test types related to transients:
      Anticipated Transient Without Scram (ATWS),
      Loss of feedwater, non ATWS,
      Loss of heat sink, non ATWS,
      Station blackout,
      Steam line break,
      Feed line break,
      Reactivity disturbance,
      Overcooling.

    . Test types related to transients at shutdown conditions:
      Loss of RHR at mid-loop operation with no or small openings,
      Loss of RHR at mid-loop operation with large openings,
      Loss of RHR at mid-loop operation with a dam in a hot leg,
      Boron dilution at shutdown,
      Cold overpressure transients at shutdown.

    . Test types related to Accident Management:
      High pressure primary side feed and bleed,
      Low pressure primary side feed and bleed,
      Secondary side feed and bleed,
      RCP restart in a highly voided primary system,
      Primary to secondary leak with multiple failures.

- TEST TYPES RELATED TO BWRS

    . Test types for LOCA:
      Large steam line break with fast depressurisation,
      Large break below water level with fast depressurisation,
      Small break without depressurisation before ADS Actuation,
      Intermediate break with slow depressurisation,
      Spray line break,
      Refill - reflood.

    . Test types for transients:
    Stationary test measuring power flow map,
      Recirculation pump trip,
      Core stability,
      Loss of main heat sink,
      Feedwater flow or temperature disturbance, e.g. LOFW,
      Loss of feedwater (LOFW) up to time of constant pressure,
      Inadvertent increase in steam flow,
      ATWS,
      Station blackout (Loss of offsite power).
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6. PHENOMENA TESTED

For the ITD the following classes of accidents are considered:

PWR:

(1) large breaks (rupture area greater than 25 per cent of the maximum pipe area connected with the pressure vessel Amax);

(2) small and intermediate breaks (rupture area less than or equal to 25 per cent Amax);

(3) small and intermediate breaks in PWRs with once through steam generators (OTSG);

(4) transients, where upset conditions are created by single or multiple failures of one or more systems in the plant.

(5) transients at shutdown.

(6) accident management for a non-degraded core.

BWR:

(1) LOCA;

(2) Transients: start uptests, frequent operational transients and anticipated transients without scram (ATWS).
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9. STATUS
Package ID Status date Status
CSNI0000/01 05-NOV-1997 Report Only
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10. REFERENCES
CSNI0000/01, included references:
- CSNI Integral Test Facility Validation Matrix
For The Assessment Of Thermal-Hydraulic Codes For Lwr Loca And Transients
Prepared by a Writing Group Committee of the PWG 2
"Task Group on Thermal-Hydraulic System Behaviour"
OCDE/GD(97)12, NEA/CSNI/R(96)17 (July 1996)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS: ESTABLISHMENT
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16. MATERIAL AVAILABLE
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: benchmarks, database, safety.