Evaluation of LLTR Series II test A-2 results
Description
Series II Test A-2 employed a double-ended (DEG) tube rupture 122'' above the lower end of the LLTI shroud under typical evaporator startup conditions. The leak site was located 2'' below Spacer No. 4 at the same location as Test A-lb which employed nitrogen as the inert non-reactive injection fluid. The test yielded peak pressures of 375 psig in the leak site region and 485 psig at the upper tubesheet approximately 10 ms and 12 ms, respectively, after tube rupture. Higher peak temperatures (approx. 22000F) were measured in this test than during Series I sodium-water reaction testing (peak temperatures measured during Series were about 19000F maximum). These high peak temperatures occurred in Test A-2 long after the tube rupture (approx. 8 seconds) and did not contribute to the acoustic peak pressures produced in the first few milliseconds
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A99/MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- Large Leak Test Rig
Publishing Information
- Imprint Pagination
- 733 p.
- Report number
- DOE/SF/70030--T31
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13664678
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CLINCH RIVER BREEDER REACTOR; LEAKS; MOLTEN METAL-WATER REACTIONS; SODIUM; STEAM GENERATORS; VALVES
- Descriptors DEC
- ALKALI METALS; BOILERS; BREEDER REACTORS; CONTROL EQUIPMENT; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLOW REGULATORS; LIQUID METAL COOLED REACTORS; METALS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS; VAPOR GENERATORS