Behavior of Cs, I, and Te in the fission product release program at ORNL

Conference · Sun Jan 01 00:00:00 EST 1984

OSTI ID:6280854

Collins, J L; Osborne, M F; Lorenz, R A

Experiments have been conducted at ORNL with highly irradiated light-water reactor (PWR and BWR) fuel rod segments to investigate fission product release in steam in the temperature range 500 to 2000/sup 0/C. Objectives were to quantify and characterize the releases under conditions postulated for LOCA) and severe accident conditions. In all, 26 experiments have been conducted - 24 with high burnup and 2 with low burnup fuels. To aid in the interpretation of fission product release, 12 implant and 18 control experiments were also conducted; the behavior of HI, I/sub 2/, Cs/sub 2/O, CsOH, Te, and TeO/sub 2/ (individually and in different combinations) was studied. This paper discusses only the observed behavior of cesium, iodine, and tellurium. Cs and I were released primarily as CsOH and CsI, and Te release was controlled by steam oxidation of Zircaloy cladding.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6280854
• Report Number(s): CONF-841105-57; ON: TI85005369
• Resource Relation: Conference: Joint meeting of the American Nuclear Society and the Atomic Industrial Forum, Washington, DC, USA, 11 Nov 1984
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
LOSS OF COOLANT
FISSION PRODUCT RELEASE
REACTOR ACCIDENTS
CESIUM
FUEL RODS
IODINE
SPENT FUEL ELEMENTS
TELLURIUM
ACCIDENTS
ALKALI METALS
ELEMENTS
FUEL ELEMENTS
HALOGENS
METALS
NONMETALS
REACTOR COMPONENTS
SEMIMETALS
220900* - Nuclear Reactor Technology- Reactor Safety