Multirod burst test program. Quarterly progress report, October--December 1975. [BWR; PWR]
Internally pressurized unirradiated Zircaloy tubes containing tubular electric heaters (to simulate nuclear fuel pellet heating) will be tested to failure in a low-pressure superheated-steam environment. These assemblies will be heated over a 915-mm (approximately 36-in.) length at a constant rate of 28/sup 0/C/sec (50/sup 0/F); differential pressures will range from about 700 to 14,000 kPa (100 to 2000 psi), corresponding to approximate rupture temperatures from 1200 to 700/sup 0/C (2200 to 1300/sup 0/F). In addition to measurements of cladding surface temperature and internal pressure during the transient test, data will be obtained on pre- and post-test flow resistance (for the multirod arrays) and on deformation, rupture strain, and channel blockage (as measured by sectioning of tubes and tube bundles). Progress made on design and construction of components and systems, development tests and evaluations, and procurement of long delivery items are summarized. Preliminary results of single-rod tests are presented.
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- Sponsoring Organization:
- ERDA
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7359468
- Report Number(s):
- ORNL/NUREG/TM-10
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
DEFORMATION
FUEL CANS
FUEL ELEMENT FAILURE
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
RESEARCH PROGRAMS
SIMULATION
TEST FACILITIES
TIN ALLOYS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS