Analysis of fission product release, deposition and transport during the BTF-104 experiment PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Analysis of fission product release, deposition and transport during the BTF-104 experiment PDF full book. Access full book title Analysis of fission product release, deposition and transport during the BTF-104 experiment by R. S. Dickson. Download full books in PDF and EPUB format.
Author: R. S. Dickson
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author: R. S. Dickson
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author: P. H. Elder
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author: L. W. Dickson
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author: James A. Gieseke
Publisher:
ISBN:
Category : Dispersion
Languages : en
Pages : 20
Get Book Here
Book Description
Author: D. S. Cox
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author: L. W. Dickson
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Understanding the behaviour of candu fuel under accident conditions is important for licensing current candu-phw reactors and for improving the safety performance of future candu designs. the btf in-reactor severe fuel damage experiments are being performed to increase our understanding of fuel thermo-mechanical behaviour, and fission-product release and transport under the degraded-cooling conditions typical of loss-of-coolant accident (loca) and loss-of-emergency-core-cooling (loecc) accident scenarios. data from the btf experiments will be used to benchmark candu safety analysis codes. this study of the fission-product retention characteristics of stainless steel and inconel surfaces was partially funded as an "in-kind" contribution to the phebus fp research program within the framework of the cog-phebus fp agreement. the primary objective of the btf-104 test was to determine the amount and timing of fission-product release from a candu fuel element under loca/loecc conditions resulting in a volume-average fuel temperature of 1550 degrees c. the value of this report is that it presents the results of a comparison of the fission-product retention characteristics of stainless steel and inconel at 500 to 700 degrees c in a steam-hydrogen atmosphere. the tellurium retention was similar on the two materials but the iodine and cesium were retained more effectively by the stainless steel. the implications of this work are that stainless steel piping surfaces are more effective than inconel surfaces in reducing the amount of iodine and cesium released to the containment under loca/loecc conditions.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
The program was designed to determine fission product and aerosol release rates from irradiated fuel under accident conditions, to identify the chemical forms of the released material, and to correlate the results with experimental and specimen conditions with the data from related experiments. These tests of PWR fuel were conducted and fuel specimen and test operating data are presented. The nature and rate of fission product vapor interaction with aerosols were studied. Aerosol deposition rates and transport in the reactor vessel during LWR core-melt accidents were studied. The Nuclear Safety Pilot Plant is dedicated to developing an expanded data base on the behavior of aerosols generated during a severe accident.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
In response to the accident at Three Mile Island Unit 2 (TMI-2), the United States Nuclear Regulatory Commission (USNRC) initiated a series of Severe Fuel Damage tests that were performed in the Power Burst Facility at the Idaho National Engineering Laboratory to obtain data necessary to understand (a) fission product release, transport, and deposition; (b) hydrogen generation; and (c) fuel/cladding material behavior during degraded core accidents. Data are presented about fission product behavior noted during the second experiment of this series, the Severe Fuel Damage Test 1-1, with an in-depth analysis of the fission product release, transport, and deposition phenomena that were observed. Real-time release and transport data of certain fission products were obtained from on-line gamma spectroscopy measurements. Liquid and gas effluent grab samples were collected at selected periods during the test transient. Additional information was obtained from steamline deposition analysis. From these and other data, fission product release rates and total release fractions are estimated and compared with predicted release behavior using current models. Fission product distributions and a mass balance are also summarized, and certain probable chemical forms are predicted for iodine, cesium, and tellurium. An in-depth evaluation of phenomena affecting the behavior of the high-volatility fission products - xenon, krypton, iodine, cesium, and tellurium - is presented. Analysis indicates that volatile release from fuel is strongly influenced by parameters other than fuel temperature. Fission product behavior during transport through the Power Burst Facility effluent line to the fission product monitoring system is assessed. Tellurium release behavior is also examined relatve to the extent of Zircaloy cladding oxidation. 81 fig., 53 tabs.
Author: James A. Gieseke
Publisher:
ISBN:
Category : Dispersion
Languages : en
Pages : 20
Get Book Here
Book Description
Author: E. P. Stock
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
The btf-105 experiment in the blowdown test facility is one of a series of experiments sponsored by the candu owners group (cog) to determine the release, transport and deposition of fission products from nuclear fuel under high-temperature transient conditions. the btf-105 experiment has been broken up into two tests: btf-105a and btf-105b. the btf-105a test is a precursor to the btf-105b test, which will generate fission product release data used to benchmark candu safety analysis codes. the btf-105a test will be used to assess instrumentation and procedures to be used during btf-105b, and to generate correlations between fuel sheath and fuel centreline temperatures. fission product release and transport data will also be obtained from low burnup fuel. the btf-105a test consists of a fuel stringer containing a single unirradiated instrumented zircaloy-clad uo2 fuel element. the assembly will be irradiated at a linear power of 50 kw/m for 10 days to establish an inventory of fission products in the fuel. following the soak irradiation, the stringer will be subjected to a coolant blowdown where the volume average temperature of the uo2 will rise to and be maintained at about 1600-1800 degrees c for about 10 minutes. the fuel element is predicted to fail during the ramp up to this temperature due to complete oxidation of the sheath. fission products released during the transient will be monitored by gamma spectrometers. following the test, the fuel stringer will be removed from the reactor and destructively examined in the crl hot cells. grab samples from inside the test section will also be removed and analyzed for fission products. this report presents an overall plan for the activities to be completed before, during and after the btf-105a blowdown test.
