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Title: Data summary report for fission product release test VI-5

Abstract

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.

Authors:
; ; ; ;  [1]
  1. Oak Ridge National Lab., TN (United States)
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Oak Ridge National Lab., TN (United States)
Sponsoring Org.:
USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
6365729
Report Number(s):
NUREG/CR-5668; ORNL/TM-11743
ON: TI92002677
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
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

Citation Formats

Osborne, M F, Lorenz, R A, Travis, J R, Webster, C S, and Collins, J L. Data summary report for fission product release test VI-5. United States: N. p., 1991. Web. doi:10.2172/6365729.
Osborne, M F, Lorenz, R A, Travis, J R, Webster, C S, & Collins, J L. Data summary report for fission product release test VI-5. United States. https://doi.org/10.2172/6365729
Osborne, M F, Lorenz, R A, Travis, J R, Webster, C S, and Collins, J L. 1991. "Data summary report for fission product release test VI-5". United States. https://doi.org/10.2172/6365729. https://www.osti.gov/servlets/purl/6365729.
@article{osti_6365729,
title = {Data summary report for fission product release test VI-5},
author = {Osborne, M F and Lorenz, R A and Travis, J R and Webster, C S and Collins, J L},
abstractNote = {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.},
doi = {10.2172/6365729},
url = {https://www.osti.gov/biblio/6365729}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Oct 01 00:00:00 EDT 1991},
month = {Tue Oct 01 00:00:00 EDT 1991}
}