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Title: Effect of alloying elements, cold work, and hydrogen on the irradiation-induced growth behavior of zirconium alloy variants - 2016-0040

Abstract

In-reactor dimensional changes in zirconium-based alloys result from a complex interplay of many factors, such as (1) alloy type and composition, including the addition of elements such as niobium, iron, and tin; (2) fabrication process, including cold work, texture, and residual stresses; (3) irradiation temperature; and (4) hydrogen levels. In many cases, the observed dimensional changes in light water reactor fuel-assembly components-especially at high exposures-cannot be fully explained based on current growth and creep models. Therefore, a systematic approach was taken in this multi-year (2005-2011) Nuclear Fuel Industry Research Program investigation. The objective was to measure stress-free irradiation-induced growth (IIG) of specially fabricated alloys through irradiation under controlled conditions in the BOR-60 fast-flux test reactor up to a high fluence of approximately 2X10{sup 26} m{sup -2} (E>1 MeV)-equivalent to maximum of approximately 37 dpa exposure-followed by postirradiation examinations (PIEs). Irradiation temperature was within a narrow temperature range (320±10 deg. C). The PIEs included dimensional-change and microhardness measurements, metallography and hydride etching, and scanning transmission electron microscopy (STEM) or transmission electron microscopy (TEM). All irradiation samples (typically flat rectangular coupons or curvilinear cutouts of cladding tubes sized 35 by 6.5 by 0.8 mm) were pre-filmed to avoid the uptake of impuritymore » hydrogen from sodium-cooled BOR-60. A wide variety of samples representing standard LWR cladding alloys with and without pre-hydriding (approximately 116 to approximately 718 ppm) as well as special compositions with iron contents (100 to 4,000 ppm) were irradiated. The irradiation in BOR-60 was done in five different stages (eight micro-cycles) and lasted approximately 18 months with interim and final growth measurements made using a high precision-length measurement device. Results of the extensive investigation include: significant effects of Fe, Nb, and hydrogen additions; quantification of growth rates from low to very high fluences (dpas); measurement of volume changes; and correlation of growth with -component dislocation densities. (authors)« less

Authors:
 [1];  [2];  [3];  [4];  [5];  [6];  [7];  [8];  [3];  [9]
  1. EPRI, 3420 Hillview Ave., Palo Alto, CA, 94304 (United States)
  2. Zircology Plus, 36848 Montecito Dr., Fremont, CA 94536 (United States)
  3. Research Institute of Atomic Reactors, Dimitrovgrad-10, 433510 (Russian Federation)
  4. Institute of Nuclear Energy Research, Lungtan, Taoyuan, 325 Taiwan (China)
  5. CEA, Saclay Center, Gif-sur-Yvette, 91191 (France)
  6. Global Nuclear Fuel, Yokosuka-Shi, Kanagawa-ken, 239-0836 (Japan)
  7. Nuclear Fuel Industry, Tokai-mura, Naka-gun, Ibaraki 319-1198 (Japan)
  8. Westinghouse, Vasteras, 72163 (Sweden)
  9. 4437-C Valley Ave. Pleasanton, CA 94566 (United States)
Publication Date:
Research Org.:
ASTM International, 100 Barr Harbor Drive, P.O. Box C700, West Conshohocken, PA, 19428-2959 (United States)
OSTI Identifier:
22788409
Resource Type:
Conference
Resource Relation:
Conference: 18. International Symposium on Zirconium in the Nuclear Industry, Hilton Head, SC (United States), 15-19 May 2016; Other Information: Country of input: France; 31 refs.
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; ATOMIC DISPLACEMENTS; BOR-60 REACTOR; CREEP; DISLOCATIONS; FUEL ASSEMBLIES; IRRADIATION; MICROHARDNESS; NIOBIUM; NUCLEAR FUELS; POST-IRRADIATION EXAMINATION; RESIDUAL STRESSES; TEST REACTORS; TRANSMISSION ELECTRON MICROSCOPY; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM BASE ALLOYS

Citation Formats

Yagnik, Suresh, Adamson, Ronald B., Kobylyansky, Gennady, Chen, Jen-Hung, Gilbon, Didier, Ishimoto, Shinji, Fukuda, Takuji, Hallstadius, Lars, Obukhov, Alexander, and Mahmood, Sheikh. Effect of alloying elements, cold work, and hydrogen on the irradiation-induced growth behavior of zirconium alloy variants - 2016-0040. United States: N. p., 2016. Web. doi:10.1520/STP159720160040.
Yagnik, Suresh, Adamson, Ronald B., Kobylyansky, Gennady, Chen, Jen-Hung, Gilbon, Didier, Ishimoto, Shinji, Fukuda, Takuji, Hallstadius, Lars, Obukhov, Alexander, & Mahmood, Sheikh. Effect of alloying elements, cold work, and hydrogen on the irradiation-induced growth behavior of zirconium alloy variants - 2016-0040. United States. https://doi.org/10.1520/STP159720160040
Yagnik, Suresh, Adamson, Ronald B., Kobylyansky, Gennady, Chen, Jen-Hung, Gilbon, Didier, Ishimoto, Shinji, Fukuda, Takuji, Hallstadius, Lars, Obukhov, Alexander, and Mahmood, Sheikh. Fri . "Effect of alloying elements, cold work, and hydrogen on the irradiation-induced growth behavior of zirconium alloy variants - 2016-0040". United States. https://doi.org/10.1520/STP159720160040.
@article{osti_22788409,
title = {Effect of alloying elements, cold work, and hydrogen on the irradiation-induced growth behavior of zirconium alloy variants - 2016-0040},
author = {Yagnik, Suresh and Adamson, Ronald B. and Kobylyansky, Gennady and Chen, Jen-Hung and Gilbon, Didier and Ishimoto, Shinji and Fukuda, Takuji and Hallstadius, Lars and Obukhov, Alexander and Mahmood, Sheikh},
abstractNote = {In-reactor dimensional changes in zirconium-based alloys result from a complex interplay of many factors, such as (1) alloy type and composition, including the addition of elements such as niobium, iron, and tin; (2) fabrication process, including cold work, texture, and residual stresses; (3) irradiation temperature; and (4) hydrogen levels. In many cases, the observed dimensional changes in light water reactor fuel-assembly components-especially at high exposures-cannot be fully explained based on current growth and creep models. Therefore, a systematic approach was taken in this multi-year (2005-2011) Nuclear Fuel Industry Research Program investigation. The objective was to measure stress-free irradiation-induced growth (IIG) of specially fabricated alloys through irradiation under controlled conditions in the BOR-60 fast-flux test reactor up to a high fluence of approximately 2X10{sup 26} m{sup -2} (E>1 MeV)-equivalent to maximum of approximately 37 dpa exposure-followed by postirradiation examinations (PIEs). Irradiation temperature was within a narrow temperature range (320±10 deg. C). The PIEs included dimensional-change and microhardness measurements, metallography and hydride etching, and scanning transmission electron microscopy (STEM) or transmission electron microscopy (TEM). All irradiation samples (typically flat rectangular coupons or curvilinear cutouts of cladding tubes sized 35 by 6.5 by 0.8 mm) were pre-filmed to avoid the uptake of impurity hydrogen from sodium-cooled BOR-60. A wide variety of samples representing standard LWR cladding alloys with and without pre-hydriding (approximately 116 to approximately 718 ppm) as well as special compositions with iron contents (100 to 4,000 ppm) were irradiated. The irradiation in BOR-60 was done in five different stages (eight micro-cycles) and lasted approximately 18 months with interim and final growth measurements made using a high precision-length measurement device. Results of the extensive investigation include: significant effects of Fe, Nb, and hydrogen additions; quantification of growth rates from low to very high fluences (dpas); measurement of volume changes; and correlation of growth with -component dislocation densities. (authors)},
doi = {10.1520/STP159720160040},
url = {https://www.osti.gov/biblio/22788409}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2016},
month = {7}
}

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