last modified: 22-MAY-1992 | catalog | categories | new | search |

CSNI0023 SEMISCALE/S-IB-3.

SEMISCALE/S-IB-3, Semiscale MOD-2A, 21.7% Communication Cold Leg Break LOCA Experiment

top ]
1. NAME OR DESIGNATION:  SEMISCALE/S-IB-3.
top ]
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
SEMISCALE/S-IB-3 CSNI0023/01 Arrived 22-MAY-1992

Machines used:

Package ID Orig. computer Test computer
CSNI0023/01 Many Computers
top ]
3. DESCRIPTION OF TEST FACILITY

The Semiscale Mod-2A system used for this test was designed as a smallscale model of the primary system of four loop PWR nuclear generating plant. consists of a pressure v  internals, including a 25-rod core with electrically powered rods and an external downcomer assembly; an intact loop with pressurizer, steam generator, pump, and rupture disc assembly. It is scaled to simulate the three intact loops in a PWR. The broken loop simulates the single loop in which a break is postulated to occur in a PWR. The system also has emergency core cooling for the intact loop from high- and low-pressure injection pumps, a coolant injection accumulator for the intact loop, and a pressure suppression system with steam supply and pressure suppression tank. Twenty-three rods of the 25-rod core were powered equally with a power density of 26.51 kW/m. The total core power for Test S-IB-3 was 1.45 MW.
top ]
4. DESCRIPTION OF TEST

This test was a 21.7%, communicative, cold leg break loss-of-coolant experiment with ECC injection. The test was intended to provide reference data for comparison of Semiscale test results to result from LOBI test B-R1M. The test was also intended to provide reference data for evaluation and assessment of reactor safety code capabilities to predict integral blowdown, refill/reflood experiments for intermediate break sizes, and particularly for providing data to extend the code into the reflood regime. Particular emphasis was placed on providing extensive core fluid and heater rod measurements to facilitate this development.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM: EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS
top ]
6. PHENOMENA TESTED

Natural circulation in 1- and 2-phase flow; core thermohydraulics; 1- and 2-phase pump behaviour.
top ]
7. UNUSUAL FEATURES: SPECIAL FEATURES OF EXPERIMENT
top ]
8. COUNTERPART EXPERIMENTS:  LOBI test B-R1M.
top ]
9. STATUS
Package ID Status date Status
CSNI0023/01 22-MAY-1992 Arrived at NEADB
top ]
10. REFERENCES
CSNI0023/01, included references:
- G.G. Loomis:
  Summary Report Semiscale Mod-2A Heat Loss Characterization Test Series
  EGG-SEMI-5448 (May 1981)
- E.M. Feldman and D.J. Olson:
  Semiscale Mod-1 Program and System Description for the Blowdown
  Heat Transfer Tests (ANCR-1230, August 1975)
- R.T. French:
  An Evaluation of Piping Heat Transfer Piping Flow Regimes,
  and Steam Generator Heat Transfer for the Semiscale Mod-1
  Isothermal Tests (ANCR-1229, August 1975)
- M.T. Leonard:
  RELAP5 Standard Model Description for the Semiscale Mod-2A System
  EGG-SEMI-5692 (December 1981)
- D.W. Golden:
  Steady State Control Model for the Standard RELAP5 Semiscale
  Mod-2A System Model
  RE-A-82-023 (April 1982)
- G.G. Loomis:
  Summary of the Semiscale Program (1965-1986)
  NUREG/CR-4945 - EGG-2509 (July 1987)
- John S. Martinelli:
  "Semiscale Loss-of-Power Test Results"
  11th Water Reactor Safety Research Information Meeting,
  October 24-28, 1983
  ECC-M-22283 Preprint
- L.J. Ball et al.:
  Semiscale Program Description (TREE-NUREG-1210, May 1987)
- T.J. Boucher and M.T. Leonard:
  "Quick Look Report for Semiscale Intermediate Break Test S-IB-3"
  EGG-SEMI-6013, August 1982
- K.E. Sackett and L/B/ Clegg:
  "Experiment Data Report for Semiscale MOD-2A Intermediate Break Test Series
(Test S-IB-3)"   NUREG/CR-2738 and EGG-2198, June 1982
- T.J. Boucher:
  "Experiment Operating Specification for Semiscale MOD-2A Experiment S-IB-3"
  EGG-SEMI-5787, February 1982
top ]
11. TEST DESIGNATION:  S-IB-3
top ]
12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
top ]
15. ESTABLISHMENT

      T.J. Boucher, M.T. Leonard
      Idaho National Engineering Laboratory
      Idaho Falls, Idaho, U.S.A.
top ]
16. MATERIAL AVAILABLE
CSNI0023/01
CCVM data        mag tapeDirectory          TOTAL: 5,025,120        CVMTP
CCVM data        mag tapeCurrent                      45,120        CVMTP
CCVM data        mag tapeComputed parameters         553,440        CVMTP
CCVM data        mag tapeDensity                     486,080        CVMTP
CCVM data        mag tapeForce                       180,480        CVMTP
CCVM data        mag tapeFlows                       240,640        CVMTP
CCVM data        mag tapeDifferential pressure       812,160        CVMTP
CCVM data        mag tapePressure                    315,680        CVMTP
CCVM data        mag tapePower                        60,320        CVMTP
CCVM data        mag tapeRotational speed             30,080        CVMTP
CCVM data        mag tapeTemperature               2,256,000        CVMTP
CCVM data        mag tapeVoltage                      45,120        CVMTP
CCVM data        mag tapeValve position               45,600        CVMTP
top ]
17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: data, loss-of-coolant accident, transients.