Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
CSNI0043 ROSA-III/952.
last modified: 17-SEP-2010 | catalog | new | search |

CSNI0043 ROSA-III/952.

ROSA-III/952, BWR Rig of Safety Assessment for LOCA, Reference MSL Break Test

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1. NAME OR DESIGNATION:  ROSA-III/952.
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2. COMPUTERS
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Program name Package id Status Status date
ROSA-III/952 CSNI0043/02 Tested 17-SEP-2010

Machines used:

Package ID Orig. computer Test computer
CSNI0043/02 Many Computers PC Windows
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3. DESCRIPTION OF TEST FACILITY

ROSA-III is a 1/124 scaled down test facility with electrically heated core designed to study the response of engineered safety features to loss-of-coolant accidents in in commercial BWR. It consists of the following, fully instrumented subsystems:
(a) the pressure vessel with a core simulating four half-length fuel assemblies and control rod;
(b) steam line and feed water line, which are independent open loops;
(c) coolant recirculation system, which consists of two loops provided with a recirculation pump and two jet pumps in each loop;
(d) emergency cooling system, including HPCS, LPCS, LPCI, and ADS.
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4. DESCRIPTION OF TEST

Run 952 is a reference MSL break test
performed with a 100% break upstream of the main steam isolation
valve and with full ECCS actuation logic. The MSL break is
characterized by a system depressurization due to a break flow of
high mass quality, which is slower than with a recirculation line
break. Continuous flashing of the fluid in the pressure vessel was
observed. A slow decrease in the downcomer water level eventually
led to actuation of HPCS, but not LPCS or LPCI. About 2/3 of the
core was uncovered, but the coolant level recovered quickly
following HPCS injection. A peak cladding temperature of 752K was
reached.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM: EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS
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6. PHENOMENA TESTED

Core thermal hydraulics; parallel channel effects and instabilities; void collapse and temperature distribution during pressurization; critical power ratio.
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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
CSNI0043/02 17-SEP-2010 Tested at NEADB
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10. REFERENCES
CSNI0043/02, included references:
- Y. ANODA, K. TASAKA, H. KUMAMARU, M. SHIBA:
ROSA-III System Description for Fuel Assembly No. 4, JAERI-M 9363, February 1981
- M. Kawaji et al.:
A Main Steam Line Break Experiment at ROSA-III Run 952 (Standart Run with full
ECCS), JAERI-M 84-229, December 1984
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11. TEST DESIGNATION:  952
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. ESTABLISHMENT

     Japan Atomic Energy Research Institute
     TOKAI-MURA
     Naka-gun, Ibaraki-ken 319-11
     JAPAN
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16. MATERIAL AVAILABLE
CSNI0043/02
Data in ASCII and report
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

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