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CSNI0048 PIPER-1/PO-SB-7.

PIPER-1/PO-SB-7, SBLOCA Simulation of Break in BWR-6 Plant at PIPER1 GE BWR Simulator

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1. NAME OR DESIGNATION:  PIPER-1/PO-SB-7.
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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
PIPER-1/PO-SB-7 CSNI0048/01 Report 13-APR-1989

Machines used:

No specified machine
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3. DESCRIPTION OF TEST FACILITY

The PIPER-ONE facility simulates a General Electric BWR-6 plant. It is characterized by volume and height scaling ratios of 1/2200 and 1/1, respectively. The available core rod electrical power (20% of the nominal value) is sufficient to simulate the nuclear heat decay. No circulation loops are included in the facility, considering their low importance in a small break LOCA and the willingness to achieve the maximum simplicity of the loop operation.
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4. DESCRIPTION OF TEST

Test PO-SB-7 simulates a SB-LOCA in a GE BWR-6 plant with the 2.6% break located in the downcomer. Recirculation pump trip, closure of feedwater and of steam lines and scram are assumed to occur at the time of break detection. HPCS and RCIC systems are assumed to be unavailable during the transient, while the actuation of ADS and of low pressure injection systems (LPCI and LPCS) is foreseen, following the signals of low level in the downcomer and of low pressure in the RPV, respectively. The SRV system is assumed to operate in the early part of the transient to limit primary system pressure excursion.
  
The main objectives of the test are:
- the evaluation of the facility behavior in relation to the most significant thermalhydraulic quantities (pressure, temperatures of heating rods, mass and energy overall balances, etc.);
- the demonstration that ADS intervention allows the injection of coolant by low pressure ECCS before the mass depletion in the loop causes important dry-out of heating rods;
- the demonstration of the facility capability to correctly simulate the complex accident scenario in the reference BWR-6, considering its limitations.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM: EXPERIMENTAL LIMITATIONS OF SHORTCOMINGS
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6. PHENOMENA TESTED

Almost 250 measurement points are provided including thermocouples, differential and absolute pressure transducers, turbines, gamma-densitometer, distributed thermoresistances, special devices to measure the energy and mass balance of the loop.
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8. COUNTERPART EXPERIMENTS:  FIST/6SB2C and ROSA-III/984.
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9. STATUS
Package ID Status date Status
CSNI0048/01 13-APR-1989 Report Only
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10. REFERENCES
CSNI0048/01, included references:
- F. D'Auria, M. Mazzini, F. Oriolo and S. Paci:
Comparison report OECD/CSNI International Standard Problem 21
PIPER-ONE Experiment PO-SB-7 (Volume 1)
CSNI Report No. 162 (November 1989)
- W. Ambrosini et al.:
Comparison report OECD/CSNI International Standard Problem 21,
PIPER-ONE Experiment PO-SB-7, Evaluation of Code Accuracy in the
Prediction of ISP 21 (Volume 2), CSNI Report No.162 (November 1989)
- R. Bovalini et al.:
PIPER-ONE Research: Experimental Data Report of Test PO-SB-7
(2.6% break at DC bottom)
OECD/CSNI Final Worskhop on ISP 21 PISA (1), April 13-14, 1989
- F. D'Auria and G. Fruttuoso:
OECD/CSNI ISP 21, PIPER-ONE Test PO-SB-7: Post Test Analysis
performed at Pisa University by RELAP5/MOD2 Code
OECD/CSNI Final Worskhop on ISP 21 PISA (1), April 13-14, 1989
- R. Bovalini et al.:
Analysis of Counterpart Tests performed in BWR Experimental Simulators
OECD/CSNI Final Worskhop on ISP 21 PISA (1), April 13-14, 1989
- M.P. Breghi et al.:
PIPER-ONE Research: Analysis and Evaluation of Instrumentation
Accuracy
OECD/CSNI Final Worskhop on ISP 21 PISA (1), April 13-14, 1989
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11. TEST DESIGNATION:  PO-SB-7.
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. ESTABLISHMENT

Comitato Nazionale per lo Sviluppo
Dell'Energia Nucleare e delle Energie Alternative (ENEA)

Dipartimento di Costruzioni Meccaniche e Nucleari (DCMN) Universita di Pisa
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16. MATERIAL AVAILABLE
CSNI0048/01
POSB7_R1.PDF Report PDF format
POSB7_R2.PDF Report PDF format
POSB7_R3.PDF Report PDF format
POSB7_R4.PDF Report PDF format
POSB7_R5.PDF Report PDF format
POSB7_R6.PDF Report PDF format
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: BWR reactors, experimental data, simulation.