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Title: Source term experiments project (STEP): aerosol characterization system

Abstract

A series of four experiments is being conducted at Argonne National Laboratory's TREAT Reactor. They have been designed to provide some of the necessary data regarding magnitude and release rates of fission products from degraded fuel pins, physical and chemical characteristics of released fission products, and aerosol formation and transport phenomena. These are in-pile experiments, whereby the test fuel is heated by neutron induced fission and subsequent clad oxidation in steam environments that simulate as closely as practical predicted reactor accident conditions. The test sequences cover a range of pressure and fuel heatup rate, and include the effect of Ag/In/Cd control rod material.

Authors:
;
Publication Date:
Research Org.:
Argonne National Lab., IL (USA)
OSTI Identifier:
5918877
Report Number(s):
CONF-850406-5
ON: DE85010248
DOE Contract Number:  
W-31-109-ENG-38
Resource Type:
Conference
Resource Relation:
Conference: International symposium and workshop on particulate and multi-phase processes and the 16th annual meeting of the Fine Particle Society, Miami Beach, FL, USA, 22 Apr 1985
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; REACTOR ACCIDENTS; FISSION PRODUCT RELEASE; TREAT REACTOR; AEROSOLS; FUEL PINS; SAMPLERS; SAMPLING; SPENT FUEL ELEMENTS; STEAM; ACCIDENTS; AIR COOLED REACTORS; COLLOIDS; DISPERSIONS; ENRICHED URANIUM REACTORS; EQUIPMENT; EXPERIMENTAL REACTORS; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; SOLS; TEST REACTORS; THERMAL REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 220600 - Nuclear Reactor Technology- Research, Test & Experimental Reactors

Citation Formats

Schlenger, B J, and Dunn, P F. Source term experiments project (STEP): aerosol characterization system. United States: N. p., 1985. Web.
Schlenger, B J, & Dunn, P F. Source term experiments project (STEP): aerosol characterization system. United States.
Schlenger, B J, and Dunn, P F. 1985. "Source term experiments project (STEP): aerosol characterization system". United States. https://www.osti.gov/servlets/purl/5918877.
@article{osti_5918877,
title = {Source term experiments project (STEP): aerosol characterization system},
author = {Schlenger, B J and Dunn, P F},
abstractNote = {A series of four experiments is being conducted at Argonne National Laboratory's TREAT Reactor. They have been designed to provide some of the necessary data regarding magnitude and release rates of fission products from degraded fuel pins, physical and chemical characteristics of released fission products, and aerosol formation and transport phenomena. These are in-pile experiments, whereby the test fuel is heated by neutron induced fission and subsequent clad oxidation in steam environments that simulate as closely as practical predicted reactor accident conditions. The test sequences cover a range of pressure and fuel heatup rate, and include the effect of Ag/In/Cd control rod material.},
doi = {},
url = {https://www.osti.gov/biblio/5918877}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jan 01 00:00:00 EST 1985},
month = {Tue Jan 01 00:00:00 EST 1985}
}

Conference:
Other availability
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