last modified: 18-JAN-1993 | catalog | categories | new | search |

CSNI0054 FIST/6MSB1.

FIST/6MSB1, BWR/6 Main Steamline Double-Ended Break Test

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1. NAME OR DESIGNATION:  FIST/6MSB1
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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
FIST/6MSB1 CSNI0054/01 Arrived 18-JAN-1993

Machines used:

Package ID Orig. computer Test computer
CSNI0054/01 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 for steady state operation.
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4. DESCRIPTION OF TEST

The main steamline break test 6MSB1 simulates a BWR/6 response with a double ended break upstream of the flow limiter in one of the four main steamlines. The effective break area consists of one main steamline flow area and one steam line flow limiter, due to back flow via the bypass header. The turbine bypass opens at about 1 second and the effective break flow area at this time also includes the bypass line area. By about 5.5 seconds, the main steam isolation valve is closed and the break is limited to one main steamline. For simplifying the test operation, and having a bounding simulation, the test was performed with full turbine bypass flow are from 0 to 5.5 seconds and one steamline flow area beyond 5.5 seconds.
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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
CSNI0054/01 18-JAN-1993 Arrived at NEADB
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10. REFERENCES
CSNI0054/01, included references:
- W.S. Hwang, Md.Alamgir and W.A. Sutherland:
BWR Fulle 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
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11. TEST DESIGNATION:  6MSB1
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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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
CSNI0054/01
CCVM data        mag tapeDirectory                    33.2 MB       CVMTP
CCVM data        mag tapeComputed Parameters          13.5 MB       CVMTP
CCVM data        mag tapeLevels                        2.1 MB       CVMTP
CCVM data        mag tapeDifferential Pressures        6.2 MB       CVMTP
CCVM data        mag tapePressures                     0.6 MB       CVMTP
CCVM data        mag tapePowers                        0.2 MB       CVMTP
CCVM data        mag tapeRotational Speeds (Pump)      0.2 MB       CVMTP
CCVM data        mag tapeTemperatures                  9.8 MB       CVMTP
CCVM data        mag tapeValve Positions               0.5 MB       CVMTP
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: data.