Zircaloy-sheathed UO↓2 Fuel Irradiated with a Declining Power History to Determine Its Effect on Fission Product Gas Release

Zircaloy-sheathed UO↓2 Fuel Irradiated with a Declining Power History to Determine Its Effect on Fission Product Gas Release PDF Author: Atomic Energy of Canada Limited
Publisher: Chalk River, Ont. : Fuel Engineering Branch, Chalk River Nuclear Laboratories
ISBN:
Category :
Languages : en
Pages : 23

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Zircaloy-sheathed UO↓2 Fuel Irradiated with a Declining Power History to Determine Its Effect on Fission Product Gas Release

Zircaloy-sheathed UO↓2 Fuel Irradiated with a Declining Power History to Determine Its Effect on Fission Product Gas Release PDF Author: Atomic Energy of Canada Limited
Publisher: Chalk River, Ont. : Fuel Engineering Branch, Chalk River Nuclear Laboratories
ISBN:
Category :
Languages : en
Pages : 23

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Canadiana

Canadiana PDF Author:
Publisher:
ISBN:
Category : Canada
Languages : en
Pages : 1252

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Nuclear Technology

Nuclear Technology PDF Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 422

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List of Publications

List of Publications PDF Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 290

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Zircaloy-2 sheathed uo2 irradiated at varying power levels - post irradiation examination of fuel

Zircaloy-2 sheathed uo2 irradiated at varying power levels - post irradiation examination of fuel PDF Author: A. S. Bain
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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A proposal to irradiate a zircaloy-sheathed uo2 fuel element with a drilled sheath defect covered with a zircaloy pull-post device at high power in the x-2 loop

A proposal to irradiate a zircaloy-sheathed uo2 fuel element with a drilled sheath defect covered with a zircaloy pull-post device at high power in the x-2 loop PDF Author: M. R. Floyd
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1122

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Validation of the olander model for uo2 dissolution in molten zircaloy-4 at 2000 degrees c

Validation of the olander model for uo2 dissolution in molten zircaloy-4 at 2000 degrees c PDF Author: P. J. Hayward
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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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.

The Length Changes of Zircaloy Sheathed U0Â Fuel Elements During Irradiation

The Length Changes of Zircaloy Sheathed U0Â Fuel Elements During Irradiation PDF Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :

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A proposal to irradiate a zircaloy-sheathed uo2 fuel element with a drilled sheath defect covered with a zircaloy foil pull-tab device at high power in the x-2 loop

A proposal to irradiate a zircaloy-sheathed uo2 fuel element with a drilled sheath defect covered with a zircaloy foil pull-tab device at high power in the x-2 loop PDF Author: M. R. Floyd
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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