Fission product deposition behavior during the in-pile severe fuel damage test SFD 1-3

Conference · Wed Jan 01 00:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6623224

Vinjamuri, K; Meikrantz, D H; Baker, J D; Osetek, D J

Retention mechanisms of radioactive material in the reactor coolant system are important because they have a significant effect on the consequences of a severe nuclear power plant accident. Fission products are normally retained in the fuel; however, during a severe accident, a significant quantity of radioactive gases and some aerosols may be expected to escape from the fuel region. Vapor and aerosol transport and deposition processes play a key role in the determination of accident source terms. This paper presents the observed behavior of fission product aerosols and vapor phase species during an in-pile severe fuel damage test (SFD 1-3) conducted in the Power Burst Facility at the Idaho National Engineering Laboratory. Fission product activities were deposited on vertical and horizontal surfaces presumably by vapor phase and aerosol deposition. In general, spherical shaped particles and agglomerates containing iron, chromium, nickel, barium, cesium, zirconium, and uranium were identified. The fission product deposition profiles for cesium, iodine, strontium, and lathanum are higher on horizontal surfaces than on vertical surfaces. The fission products cesium and iodine were likely deposited as a combination of vapor phase compounds and aerosols. Tellurium deposition profiles suggest vapor phase deposition. Strontium and lanthanum deposition profiles suggest aerosol deposition by gravitational settling.

• Research Organization: EG and G Idaho, Inc., Idaho Falls
• OSTI ID: 6623224
• Report Number(s): CONF-860610-; TRN: 87-016388
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 52; Conference: American Nuclear Society annual meeting, Reno, NV, USA, 15 Jun 1986
• 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
REACTOR ACCIDENTS
FISSION PRODUCTS
DEPOSITION
PWR TYPE REACTORS
AEROSOLS
CESIUM
FISSION PRODUCT RELEASE
FUEL ELEMENT FAILURE
IDAHO NATIONAL ENGINEERING LABORATORY
IODINE
LANTHANUM
PRIMARY COOLANT CIRCUITS
REACTOR CORE DISRUPTION
REACTOR SAFETY
RESEARCH PROGRAMS
SCANNING ELECTRON MICROSCOPY
STRONTIUM
TELLURIUM
US NRC
ACCIDENTS
ALKALI METALS
ALKALINE EARTH METALS
COLLOIDS
COOLING SYSTEMS
DISPERSIONS
ELECTRON MICROSCOPY
ELEMENTS
ENERGY SYSTEMS
HALOGENS
ISOTOPES
MATERIALS
METALS
MICROSCOPY
NATIONAL ORGANIZATIONS
NONMETALS
RADIOACTIVE MATERIALS
RARE EARTHS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
SEMIMETALS
SOLS
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
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210200 - Power Reactors
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Light-Water Moderated
Nonboiling Water Cooled