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Title: Results from the power burst facility severe fuel damage test 1-4; A simulated severe fuel damage accident with irradiated fuel rods and control rods

Abstract

Highly irradiated fuel rods and control rods are used in the Power Burst Facility Severe Fuel Damage (SFD) Test 1-4 to simulate conditions expected during a high-temperature, severe fuel damage accident in a pressurized water reactor. The objective of the test is to provide data on fuel and control rod behavior, hydrogen generation, the release and transport of fission products and aerosols during severe accidents. This paper presents important results from the test based upon the response of on-line instrumentation, analysis of fission product and aerosol data, and postirradiation examination of the fuel bundle. The results from SFD 1-4 provide insight into phenomena governing fuel bundle thermal response, Zircaloy oxidation and hydrogen generation, control rod degradation behavior, core melt progression, fission product release, aerosol generation, and fission product and aerosol deposition and transport.

Authors:
; ;  [1];  [2]
  1. (Idaho National Engineering Lab., EG and G Idaho, Inc., Idaho Falls, ID (US))
  2. (Los Alamos Technical Associates, Albuquerque, NM (US))
Publication Date:
OSTI Identifier:
5105109
DOE Contract Number:  
AC07-76ID01570
Resource Type:
Journal Article
Journal Name:
Nuclear Technology; (United States)
Additional Journal Information:
Journal Volume: 94:3; Journal ID: ISSN 0029-5450
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PBF REACTOR; FUEL ELEMENT FAILURE; AEROSOLS; CONTROL ELEMENTS; FISSION PRODUCTS; FUEL ELEMENT CLUSTERS; FUEL RODS; HYDROGEN; MELTDOWN; OXIDATION; PRODUCTION; REACTOR ACCIDENTS; SIMULATION; TESTING; THERMAL TESTING; USES; ZIRCALOY; ACCIDENTS; ALLOYS; CHEMICAL REACTIONS; COLLOIDS; DISPERSIONS; ELEMENTS; FUEL ASSEMBLIES; FUEL ELEMENTS; ISOTOPES; MATERIALS; MATERIALS TESTING; NONDESTRUCTIVE TESTING; NONMETALS; PULSED REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; SOLS; TANK TYPE REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; 220900* - Nuclear Reactor Technology- Reactor Safety; 220600 - Nuclear Reactor Technology- Research, Test & Experimental Reactors

Citation Formats

Petti, D.A., Martinson, Z.R., Hobbins, R.R., and Osetek, D.J. Results from the power burst facility severe fuel damage test 1-4; A simulated severe fuel damage accident with irradiated fuel rods and control rods. United States: N. p., 1991. Web.
Petti, D.A., Martinson, Z.R., Hobbins, R.R., & Osetek, D.J. Results from the power burst facility severe fuel damage test 1-4; A simulated severe fuel damage accident with irradiated fuel rods and control rods. United States.
Petti, D.A., Martinson, Z.R., Hobbins, R.R., and Osetek, D.J. Sat . "Results from the power burst facility severe fuel damage test 1-4; A simulated severe fuel damage accident with irradiated fuel rods and control rods". United States.
@article{osti_5105109,
title = {Results from the power burst facility severe fuel damage test 1-4; A simulated severe fuel damage accident with irradiated fuel rods and control rods},
author = {Petti, D.A. and Martinson, Z.R. and Hobbins, R.R. and Osetek, D.J.},
abstractNote = {Highly irradiated fuel rods and control rods are used in the Power Burst Facility Severe Fuel Damage (SFD) Test 1-4 to simulate conditions expected during a high-temperature, severe fuel damage accident in a pressurized water reactor. The objective of the test is to provide data on fuel and control rod behavior, hydrogen generation, the release and transport of fission products and aerosols during severe accidents. This paper presents important results from the test based upon the response of on-line instrumentation, analysis of fission product and aerosol data, and postirradiation examination of the fuel bundle. The results from SFD 1-4 provide insight into phenomena governing fuel bundle thermal response, Zircaloy oxidation and hydrogen generation, control rod degradation behavior, core melt progression, fission product release, aerosol generation, and fission product and aerosol deposition and transport.},
doi = {},
journal = {Nuclear Technology; (United States)},
issn = {0029-5450},
number = ,
volume = 94:3,
place = {United States},
year = {1991},
month = {6}
}