Search
Filters

Irradiation Accelerated Corrosion of 316L Stainless Steel T91 and Zircaloy-4 in Primary Water

Austenitic and ferritic-martensitic steel were irradiated with  protons while exposed to simulated PWR primary water for 4-72 hr in 320°C water with 3 wppm hydrogen while irradiated at surface dose rates from 400-4000 kGy/s (4x10-7 to 7x10-6 dpa/s).

Product Number: 51317--9131-SG
ISBN: 9131 2017 CP
Author: Stephen Raiman
Publication Date: 2017
$0.00
$20.00
$20.00

316L stainless steel T91 and Zircaloy-4 were irradiated with a proton beam while simultaneously exposed to simulated PWR primary water. Samples were exposed for 4-72 hr in 320°C water with 3 wppm hydrogen while simultaneously irradiated at surface dose rates from 400-4000 kGy/s (7E-7 to 7E-6 dpa/s). After exposure samples were characterized with TEM EDS and Raman spectroscopy to determine the effects of radiation on the growth and stability of the oxide films.Radiolysis was found to alter the oxide morphology and composition of F-M and stainless steel while having no discernable effect on Zircaloy corrosion. Direct irradiation however caused a large increase in oxide thickness in Zircaloy. Oxide films on stainless steel were found to be deficient in protective oxides suggesting a loss of passivity. This paper reports new insights into the effects of radiolysis and radiation damage on corrosion behavior of several materials used in light water reactor cores.

316L stainless steel T91 and Zircaloy-4 were irradiated with a proton beam while simultaneously exposed to simulated PWR primary water. Samples were exposed for 4-72 hr in 320°C water with 3 wppm hydrogen while simultaneously irradiated at surface dose rates from 400-4000 kGy/s (7E-7 to 7E-6 dpa/s). After exposure samples were characterized with TEM EDS and Raman spectroscopy to determine the effects of radiation on the growth and stability of the oxide films.Radiolysis was found to alter the oxide morphology and composition of F-M and stainless steel while having no discernable effect on Zircaloy corrosion. Direct irradiation however caused a large increase in oxide thickness in Zircaloy. Oxide films on stainless steel were found to be deficient in protective oxides suggesting a loss of passivity. This paper reports new insights into the effects of radiolysis and radiation damage on corrosion behavior of several materials used in light water reactor cores.

Also Purchased
Picture for Effect of Yield Strength on Stress Corrosion Cracking Growth in Neutron-Irradiated Stainless Steels
Available for download

51314-4231-Effect of Yield Strength on Stress Corrosion Cracking Growth in Neutron-Irradiated Stainless Steels

Product Number: 51314-4231-SG
ISBN: 4231 2014 CP
Author: Yugo Ashida
Publication Date: 2014
$0.00
Picture for 00204 STRESS CORROSION CRACKING OF TYPE 304
Available for download

00204 STRESS CORROSION CRACKING OF TYPE 304 STAINLESS STEEL IRRADIATED TO VERY HIGH DOSE

Product Number: 51300-00204-SG
ISBN: 00204 2000 CP
Author: H. M. Chung, W. E. Ruther, R. V. Strain, and W. J. Shack
$20.00