Quarterly progress report on fission product behavior in LWRs, April--June 1977. [Loss of coolant and spent fuel transportation accidents]

Technical Report · Mon Aug 01 04:00:00 EDT 1977

OSTI ID:7088486

Malinauskas, A P

Two fission product release experiments were conducted in an air atmosphere. One of these, High Burnup Fuel Test 5, was conducted over a 20-hr period at 500/sup 0/C. In this experiment, 0.5 x 10/sup -6/ percent of the total cesium inventory and 91 x 10/sup -6/ percent of the ruthenium inventory were released from the rod. The second test, High Burnup Fuel Test 6, was run over a 5-hr period at 700/sup 0/C. The experiment yielded a cesium release amounting to 14.3 x 10 rcent of inventory, whereas the ruthenium release was 7.3 x 10/sup -4/ percent. The ruthenium releases are markedly greater than observed previously in corresponding tests in steam. Design of the fission product transport test facility has progressed to the point at which estimates of the costs of construction can be made.

• Research Organization: Oak Ridge National Lab., Tenn. (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 7088486
• Report Number(s): ORNL/NUREG/TM-139
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COST
DESIGN
FISSION PRODUCT RELEASE
FUEL ELEMENTS
LEAKS
LOSS OF COOLANT
MELTDOWN
PWR TYPE REACTORS
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH PROGRAMS
SPENT FUEL ELEMENTS
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS