Chemical characteristics of material released during Source Term Experiments Project (STEP) in-pile tests: Part 1

Conference · Mon Sep 01 00:00:00 EDT 1986

OSTI ID:6614756

Schlenger, B J; Dunn, P F; Herceg, J E; Simms, R; Horton, E L; Baker, L Jr; Ritzman, R L

A series of four experiments aimed at characterizing the radiological source term associated with postulated severe light water reactor (LWR) accidents has been conducted at Argonne's Transient Reactor Test Facility (TREAT). The STEP tests drove fuel elements to the point of severe cladding disruption in steam environments by fission heating and oxidation of the Zircaloy cladding. The released fission products and volatile cladding constituents entrained in the steam/hydrogen flows were captured by the test vehicles' sampling systems and analyzed by SEM/EDX. The principal constituents of the deposits were fission product cesium, molybdenum and rubidium, and tin from the cladding. Iodine was generally seen collocated with cesium, although lone iodine deposits were observed indicating that the iodine was not completely transported as CsI. Structural material was also observed. The composition information in conjunction with counted particle distributions were used to determine the particle loading of that portion of the material released during the first test that was transported in aerosol form.

• Research Organization: Argonne National Lab., IL (USA); Electric Power Research Inst., Palo Alto, CA (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6614756
• Report Number(s): CONF-860911-28; ON: DE87004976; TRN: 87-018274
• Resource Relation: Conference: 192. American Chemical Society national meeting, Anaheim, CA, USA, 7 Sep 1986; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
TREAT REACTOR
FISSION PRODUCT RELEASE
FUEL-CLADDING INTERACTIONS
REACTOR OPERATION
CHEMICAL COMPOSITION
DEPOSITION
EXPERIMENTAL DATA
FISSION PRODUCTS
FUEL CANS
FUEL ELEMENTS
HYDROGEN
MORPHOLOGY
RADIOACTIVE AEROSOLS
REACTOR ACCIDENTS
SAMPLING
STEAM
URANIUM DIOXIDE
ZIRCALOY 4
ACCIDENTS
ACTINIDE COMPOUNDS
AEROSOLS
AIR COOLED REACTORS
ALLOYS
CHALCOGENIDES
COLLOIDS
DATA
DISPERSIONS
ELEMENTS
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
INFORMATION
ISOTOPES
MATERIALS
NONMETALS
NUMERICAL DATA
OPERATION
OXIDES
OXYGEN COMPOUNDS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
SOLS
TEST REACTORS
THERMAL REACTORS
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM OXIDES
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220502* - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors