Data summary report for fission product release test VI-5

Technical Report · Tue Oct 01 00:00:00 EDT 1991

DOI:https://doi.org/10.2172/6365729· OSTI ID:6365729

Osborne, M F; Lorenz, R A; Travis, J R; Webster, C S; Collins, J L ^[1]

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1. Oak Ridge National Lab., TN (United States)

Test VI-5, the fifth in a series of high-temperature fission product release tests in a vertical test apparatus, was conducted in a flowing mixture of hydrogen and helium. The test specimen was a 15.2-cm-long section of a fuel rod from the BR3 reactor in Belgium which had been irradiated to a burnup of {approximately}42 MWd/kg. Using a hot cell-mounted test apparatus, the fuel rod was heated in an induction furnace under simulated LWR accident conditions to two test temperatures, 2000 K for 20 min and then 2700 K for an additional 20 min. The released fission products were collected in three sequentially operated collection trains on components designed to measure fission product transport characteristics and facilitate sampling and analysis. The results from this test were compared with those obtained in previous tests in this series and with the CORSOR-M and ORNL diffusion release models for fission product release. 21 refs., 19 figs., 12 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6365729
• Report Number(s): NUREG/CR-5668; ORNL/TM-11743; ON: TI92002677
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
FISSION PRODUCTS
FUEL ELEMENTS
FISSION PRODUCT RELEASE
BR-3 REACTOR
BURNUP
C CODES
COMPUTERIZED SIMULATION
DEPOSITION
FURNACES
GAMMA SPECTROSCOPY
O CODES
POST-IRRADIATION EXAMINATION
QUANTITATIVE CHEMICAL ANALYSIS
RADIOISOTOPES
REACTOR ACCIDENTS
STAINLESS STEELS
TEMPERATURE GRADIENTS
TEST FACILITIES
V CODES
WATER COOLED REACTORS
ACCIDENTS
ALLOYS
CHEMICAL ANALYSIS
COMPUTER CODES
ENRICHED URANIUM REACTORS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
MATERIALS
POWER REACTORS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
SIMULATION
SPECTROSCOPY
STEELS
THERMAL REACTORS
WATER MODERATED REACTORS
220502* - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents
220900 - Nuclear Reactor Technology- Reactor Safety
220300 - Nuclear Reactor Technology- Fuel Elements