Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
CSNI0055 FIST/6SB1.
last modified: 18-JAN-1993 | catalog | new | search |

CSNI0055 FIST/6SB1.

FIST/6SB1, BWR/6 Simulated Recirculation Line Break

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1. NAME OR DESIGNATION:  FIST/6SB1.
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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.

Program name Package id Status Status date
FIST/6SB1 CSNI0055/01 Arrived 18-JAN-1993

Machines used:

Package ID Orig. computer Test computer
CSNI0055/01 Many Computers
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3. DESCRIPTION OF TEST FACILITY

The FIST facility is scaled to a BWR/6-218 standard plant. A full size bundle with electrically heated rods is used to simulate the reactor core. A scaling ratio of 1/624 is applied in the design of the system components. Key features of the FIST facility include:
(1) Full height test vessel and internals;
(2) correctly scaled fluid volume distribution;
(3) simulation of ECCS, S/RV, and ADS;
(4) level trip capability;
(5) heated feedwater supply system, which provides the capability fo steady state operation.
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4. DESCRIPTION OF TEST

This test simulates a BWR/6 recirculation line break of 0.05 squ.ft. with a stuck open safety relief valve. In addition, similar to test 6SB2C, HPCS is assumed to be unavailable. Test 6SB1 is performed with a BWR/6 core average power of 4.64 MW.
A nominal ADS time delay of 105 seconds is used. ECC water temperature is 120 deg.F. The system pressure does not reach the SRV opening setpoint during the period between MSIV closure and ADS activation.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM: EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS
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6. PHENOMENA TESTED

Channel and bypass axial flow and void distribution; core heat transfer including DNB, dryout, RNB, surface to surface radiation; quench front propagation for both fuel rods and channel walls; separator behaviour including flooding, steam penetration and carryover; phase separation and mixture level behaviour; guide tube and lower plenum flashing; natural circulation in core and downcomer; mixture level in core.
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7. UNUSUAL FEATURES: SPECIAL FEATURES OF EXPERIMENT
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8. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS
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9. STATUS
Package ID Status date Status
CSNI0055/01 18-JAN-1993 Arrived at NEADB
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10. REFERENCES
CSNI0055/01, included references:
- A. G. Stephens:
BWR Full Integral Simulation Test (FIST) Program Facility Description Report
NUREG/CR-2576 December, 1982
- W.S. Hwang, Md.Alamgir and W.A. Sutherland:
BWR Full Integral Simulation Test (FIST) Phase I Test Results
NUREG/CR-3711, November 1983
- W.A. Sutherland, Md.Alamgir, J.A. Findlay, W.S. Hwang:
BWR Full Integral Simulation Test (FIST) Phase II Test Results and
TRAC-BWR Model Qualification
NUREG/CR-4128, June 1985
- Jae H. Jo and H. Connell:
Simulation of FIST Tests using TRAC-BD1/MOD1
BNL-NUREG--37616, Paper submitted to the ANS Annual Meeting Reno, NV, June
15-19, 1986
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11. TEST DESIGNATION:  6SB1.
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. ESTABLISHMENT

Work sponsored by: U.S. Nuclear Regulatory Commission
                   Electric Power Research Institute
                   General Electric Company
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16. MATERIAL AVAILABLE
CSNI0055/01
CCVM data        mag tapeDirectory             (TOTAL: 37.2 MB)     CVMTP
CCVM data        mag tapeComputed Parameters           12.5 MB      CVMTP
CCVM data        mag tapeLevels                         2.9 MB      CVMTP
CCVM data        mag tapeDifferential Pressures         7.6 MB      CVMTP
CCVM data        mag tapePressures                      0.7 MB      CVMTP
CCVM data        mag tapePowers                         0.3 MB      CVMTP
CCVM data        mag tapeRotational Speeds (Pump)       0.2 MB      CVMTP
CCVM data        mag tapeTemperatures                  12.4 MB      CVMTP
CCVM data        mag tapeValve Positions                0.7 MB      CVMTP
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: data.