Multirod Burst Test Program quarterly progress report, April--June 1977. [BWR; PWR]

Technical Report · Mon Nov 14 00:00:00 EST 1977

OSTI ID:5287241

Chapman, R H

Checkout of the multirod test facility was completed, and operation and test procedures were prepared. Fabrication of the first 4 x 4 test bundle was nearly completed, using the best fuel simulators (internal heaters) available at the time. Since this was the first time some of the assembly procedures were used under strict quality control measures, difficulties were encountered; these are discussed in some detail. Two additional single-rod burst tests (SR-28 and SR-29) were conducted. The fuel pin simulators used in these tests were fabricated as prototypes to verify the procedures used in fabricating the simulators for the first bundle. Conditions selected for these tests were representative of those planned for the first bundle test to give a basis for comparison. Simulators for the second 4 x 4 test array were received and accepted; in-house preparations are under way on this group. About half of the fuel simulators required for the third test array have been received and are undergoing acceptance inspection and evaluation. All the single-rod tests were reviewed and evaluated for validity; several tests were eliminated from the data set as a result of this process. The valid tests and pertinent results are summarized.

• Research Organization: Oak Ridge National Lab., Tenn. (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5287241
• Report Number(s): ORNL/NUREG/TM-135
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
FUEL ELEMENT FAILURE
RESEARCH PROGRAMS
PWR TYPE REACTORS
DEFORMATION
FUEL CANS
SIMULATION
TEST FACILITIES
TRANSIENTS
ZIRCALOY
ACCIDENTS
ALLOYS
ELASTICITY
MECHANICAL PROPERTIES
REACTOR ACCIDENTS
REACTORS
TENSILE PROPERTIES
THERMOELASTICITY
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled