CSNI0029: TLTA/6431, Two-Loop-Test-Apparatus, BWR/6 Simulator, Small-Break LOCA

OECD Nuclear Energy Agency / L'Agence pour l'énergie nucléaire

OECD-OCDE

[Program Service | Recent programs]

CSNI0029 TLTA/6431. (Abstract last modified 22-MAY-1992)

TLTA/6431, Two-Loop-Test-Apparatus, BWR/6 Simulator, Small-Break LOCA

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION - TLTA/6431.

2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name Package-ID Status TLTA/6431 CSNI0029/01 Arrived

Machines used: Package-ID Orig.Computer Test Computer CSNI0029/01 Many Computers

3. DESCRIPTION OF TEST FACILITY - The Two-Loop-Test-Apparatus (TLTA) is a 1:624 volume scaled BWR/6 simulator. It was the predecessor of the better-scaled FIST facility. The facility is capable of full BWR system pressure and has a simulated core with a full size 8 x 8, full power single bundle of indirect electrically heated rods. All major BWR systems are simulated including lower plenum, guide tube, core region (bundle and bypass), upper plenum, steam separator, steam dome, annular downcomer, recirculation loops and ECC injection systems. The fundamental scaling consideration was to achieve real-time response. A number of the scaling compromises present in TLTA were corrected in the FIST configuration. These compromises include a number of regional volumes and component elevations.

4. DESCRIPTION OF TEST - 64.45 sqcm small break LOCA with activation of the full emergency core cooling system, but without activation of the automatic decompression system.

5. EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS -

6. PHENOMENA TESTED - Channel bypass axial flow and void distribution; ore heat transfer; quench front propagation for both fuel rods and channel walls; guide tube and lower plenum flashing; mixture level in core.

7. SPECIAL FEATURES OF EXPERIMENT -

8. COUNTERPART EXPERIMENTS -

9. STATUS
CSNI0029/01: 22-MAY-1992 Arrived, no report

10. REFERENCES -
CSNI0029/01:

11. TEST DESIGNATION - 6431

12. PROGRAMMING LANGUAGE(S) USED -
CSNI0029/01:

15. ESTABLISHMENT -
Idaho National Engineering Laboratory
Idaho Falls, Idaho, U.S.A.

16. MATERIAL AVAILABLE -
CSNI0029/01:
Directory         TOTAL: 20,229,120
Current                      66,400
Density                   1,693,200
Energy                      265,600
Mass flow                   697,200
Levels                      365,200
Mass                        265,600
Differential pressure     2,290,800
Pressure                    265,600
Peak clad temperature        70,720
Power                        66,400
RHOF                      1,294,800
RHOG                      1,261,600
RHOL                      1,261,600
Pump rpm                     99,600
Temperature               3,604,000
Saturation temperature    1,261,600
Voltage                      66,400
Valve position              199,200

17. CATEGORIES -

- Y. Integral Experiments Data, Databases, Benchmarks

Keywords: DATA, LOSS-OF-COOLANT ACCIDENT, TRANSIENTS

Home - About Us - Work Areas - Data Bank - Publications - Press Room - List of acronyms - Search