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A defect test on a previously irradiated u-si-a1 fuel element of simple design

A defect test on a previously irradiated u-si-a1 fuel element of simple design PDF Author: M. A. Feraday
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Languages : en
Pages : 0

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A defect test on a previously irradiated u-si-a1 fuel element of simple design

A defect test on a previously irradiated u-si-a1 fuel element of simple design PDF Author: M. A. Feraday
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ISBN:
Category :
Languages : en
Pages : 0

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A defect test on a previously irradiated u-si-a1 fuel element of simple design - phase 2a

A defect test on a previously irradiated u-si-a1 fuel element of simple design - phase 2a PDF Author: M. A. Feraday
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Category :
Languages : en
Pages : 0

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Result of u-si-a1 defect test x-27802 (corrodible layer design with no previous irradiation).

Result of u-si-a1 defect test x-27802 (corrodible layer design with no previous irradiation). PDF Author: A. M. Ross
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Category :
Languages : en
Pages : 0

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Pre-irradiation data on peripheral voidage u-si-a1 fuel elements containing several designs of defect detection devices

Pre-irradiation data on peripheral voidage u-si-a1 fuel elements containing several designs of defect detection devices PDF Author: K. D. Cotnam
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Category :
Languages : en
Pages : 0

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Proposal to test a previously irradiated fuel element with a burnup of 100 mw.h/kg u in dryout at sheath temperatures of 700 degrees - 800 degrees c

Proposal to test a previously irradiated fuel element with a burnup of 100 mw.h/kg u in dryout at sheath temperatures of 700 degrees - 800 degrees c PDF Author: A. R. Yamazaki
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Category :
Languages : en
Pages : 0

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Pre-irradiation data for u-si-a1 fuel element hkw which contained a disc-type detection device with a corrodible strip

Pre-irradiation data for u-si-a1 fuel element hkw which contained a disc-type detection device with a corrodible strip PDF Author: J. L. Conversi
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Category :
Languages : en
Pages : 0

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The fabrication and pre-irradiation data for u-si-a1 fuel element fpz which contained a disc-type detection device with a corrodible strip

The fabrication and pre-irradiation data for u-si-a1 fuel element fpz which contained a disc-type detection device with a corrodible strip PDF Author: J. L. Conversi
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Category :
Languages : en
Pages : 0

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Pre-irradiation data on the u-si-a1 fuel elements containing several designs of peripheral voidage

Pre-irradiation data on the u-si-a1 fuel elements containing several designs of peripheral voidage PDF Author: P. A. Morel
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Category :
Languages : en
Pages : 0

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Test Design Description

Test Design Description PDF Author:
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Category :
Languages : en
Pages :

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The metal fuel in FFTF (MFF) tests represented by the Test Design Description (TDD), Volume II, Part I will be the second irradiation test of full length Integral Fast Reactor (IFR) fuel elements in FFTF. The MFF-1 Test, designated as the HF168 Test Assembly, will contain six sodium-bonded metallic fuel elements clad in HT9 interspersed in a basically oxide fuel assembly. The wire-wrapped elements will be irradiated to breach or 900 EFPD with peak nominal cladding temperatures of 1127°F. The MFF-1A test, designated as the HF169 Test assembly, will also contain six sodium-bonded metallic fuel elements clad in HT9 interspersed in an oxide fuel assembly. The MFF-1A elements will be irradiated at a peak nominal cladding temperature of 1127°F to 450 EFPD or until a cladding breach occurs. The metal fuel elements contain U-10Zr cast slugs and have a fuel-smeared density of 75%. The enriched zone is 36-in. long, composed of three slugs and has one 6.5-in. long depleted-uranium axial blanket slug (DU-10Zr) at each end. The metal fuel elements were fabricated at ANL-W and delivered to Westinghouse-Hanford for assembly into the test article. This Test Design Description contains only the relevant fabrication data for the metal fuel elements built at Argonne. The elements conform to the requirements in MG-22, "User`s Guide for the Irradiation of Experiments in the FTR."

Nuclear Regulatory Commission Issuances

Nuclear Regulatory Commission Issuances PDF Author: U.S. Nuclear Regulatory Commission
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 950

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