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02900nam a2200529 i 4500 |
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b1c7e8ce-c902-4542-8419-84a49f84fefb |
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20230617000000.0 |
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160219s1991 pau|||||o|||||||||||eng|| |
| 024 |
7 |
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|a 10.1520/STP25538S
|2 doi
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| 035 |
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|a (IN-ChSCO)ASTMSTP25538S
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| 040 |
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|a ASTM
|c SCOPE
|b eng
|e rda
|d PAU
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| 041 |
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|a eng
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| 100 |
1 |
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|a Van Swam, LFP,
|e author
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| 245 |
1 |
4 |
|a The Corrosion of Zircaloy-4 Fuel Cladding in Pressurized Water Reactors /
|c LFP Van Swam, SH. Shann
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| 264 |
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1 |
|a West Conshohocken, Pa. :
|b ASTM International,
|c 1991
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| 300 |
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|a 1 online resource (24 pages) :
|b illustrations, figures, tables
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| 336 |
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|a text
|2 rdacontent
|b txt
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| 337 |
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|a computer
|2 rdamedia
|b c
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| 338 |
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|a online resource
|2 rdacarrier
|b cr
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| 347 |
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|a text file
|b PDF
|2 rda
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| 504 |
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|a Includes bibliographical references
|b 16
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| 506 |
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|a Restricted for use by site license.
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| 520 |
3 |
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|a The effects of thermo-mechanical processing of cladding on the corrosion of Zircaloy-4 in commercial PWRs have been investigated. Visual observations and nondestructive measurements at poolside, augmented by observations in the hot cell, indicate that the initial black oxide transforms into a grey or tan and later white oxide layer at a thickness of 10 to 15 ?m independent of the thermal processing history of the tubing. At an oxide layer thickness of 60 to 80 ?m, the oxide may spall depending somewhat on the particular oxide morphology formed and possibly on the frequency of power and temperature changes of the fuel rods. Because spalling of oxide lowers the metal-to-oxide interface temperature of fuel rods, it reduces the corrosion rate and is beneficial from that point of view
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| 541 |
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|a ASTM International
|3 PDF
|c Purchase price
|h USD25
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| 588 |
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|a Description based on publisher's website, viewed February 19, 2016
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| 650 |
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|a Corrosion model
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| 650 |
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|a Corrosion parameter
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| 650 |
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|a Cumulative annealing parameter
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| 650 |
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|a In-reactor corrosion behavior
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| 650 |
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|a Nuclear fuel claddings
|v Congresses
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| 650 |
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|a Oxide thickness
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| 650 |
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0 |
|a Zircaloy tubing
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| 650 |
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0 |
|a Zircaloy-4
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| 650 |
1 |
4 |
|a Zircaloy-4
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| 650 |
2 |
4 |
|a Corrosion model
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| 650 |
2 |
4 |
|a Corrosion parameter
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| 650 |
2 |
4 |
|a Cumulative annealing parameter
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| 650 |
2 |
4 |
|a In-reactor corrosion behavior
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| 650 |
2 |
4 |
|a Oxide thickness
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| 650 |
2 |
4 |
|a PWRs
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| 650 |
2 |
4 |
|a Zircaloy tubing
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| 700 |
1 |
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|a Shann, SH.,
|e author
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| 710 |
2 |
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|a ASTM International
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| 710 |
2 |
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|a American Society for Testing and Materials
|t Selected Technical Papers.
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| 710 |
2 |
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|a American Society for Testing and Materials
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| 740 |
0 |
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|a ASTM digital library
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| 999 |
1 |
0 |
|i b1c7e8ce-c902-4542-8419-84a49f84fefb
|l 9978997873303681
|s US-PU
|m corrosion_of_zircaloy_4_fuel_cladding_in_pressurized_water_reactors________1991_______astmia________________________________________van_swam__lfp______________________e
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