The source term experiments project deposition sample characterization: Interim report
A series of four experiments aimed at characterizing the radiological source term associated with postulated severe light water reactor accidents has been conducted at Argonne National Laboratory's TREAT Facility. The experiments were designed to provide dta regarding the physicochemical properties, near the point of origin, of the biologically important volatile fission products released early in such accidents. The experimental vehicles were equipped to capture representative fission products released from fuel rods undergoing severe cladding degradation in a steam environment. Test conditions of pressure, fuel heatup rate, and steam flow were selected to simulate conditions predicted for hypothetical reactor accident sequences. One of the main components of the experimental vehicle's aerosol characterization system, common to all four tests, was a sample tree. It served to suspend coupons composed of a variety of materials, some typical of reactor structures, into the fission-product-laden steam flow. These coupons collected particulates and condensing vapors. Coupons frome ach of the four tests have been examined using scanning electron microscopy and associated energy dispersive x-ray analysis. The results of these initial sample examinations are presented. They are preceeded by a brief description of the test series and the experimental vehicle. Also included is a discussion of planned posttest examinations of other aerosol characterization system components and the test fuel as well as further examinations of the sample tree coupons. Results of the additional examinations thermal-hydraulic data, and interpretation of the information for each test will be included in future reports.
- Research Organization:
- Argonne National Lab., IL (USA); Electric Power Research Inst., Palo Alto, CA (USA)
- OSTI ID:
- 7173237
- Report Number(s):
- EPRI-NP-4967M; ON: TI87004111
- Country of Publication:
- United States
- Language:
- English
Similar Records
Chemical characteristics of material released during Source Term Experiments Project (STEP) in-pile tests: Part 1
Source term experiments project (STEP): aerosol characterization system
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR ACCIDENTS
PWR TYPE REACTORS
FISSION PRODUCT RELEASE
DEPOSITION
FISSION PRODUCTS
HEAT TRANSFER
HYDRAULICS
RADIOACTIVITY TRANSPORT
TEST FACILITIES
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
ISOTOPES
MATERIALS
MECHANICS
RADIOACTIVE MATERIALS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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