Influence of hydrogen on the oxygen solubility in Zircaloy-4

被引：12

作者：

Guilbert-Banti, Severine ^{[1
]}

Lacote, Pauline ^{[1
]}

Taraud, Gaelle ^{[1
]}

Berger, Pascal ^{[2
]}

Desquines, Jean ^{[1
]}

Duriez, Christian ^{[1
]}

机构：

[1] Inst Radioprotect & Surete Nucl, SEREX LE2M, Batiment 327,BP3, F-13115 St Paul Les Durance, France

[2] Univ Paris Saclay, CNRS, CEA, NIMBE, F-91191 Gif Sur Yvette, France

来源：

JOURNAL OF NUCLEAR MATERIALS | 2016年 / 469卷

关键词：

Oxygen; Hydrogen; Zircaloy-4; Phase diagram; PHASE-TRANSFORMATION; OXIDATION; ALLOYS;

D O I：

10.1016/j.jnucmat.2015.11.019

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Despite the influence of hydrogen on the behavior of zirconium fuel cladding in many nuclear safety issues, the pseudo-binary Zircaloy-4 oxygen phase diagram still lacks of data, especially above 1000 degrees C. The aim of this study was to provide experimental data to better assess the influence of hydrogen on the oxygen solubility in Zircaloy-4. Homogenized two-phase Zircaloy-4 samples were elaborated from 300 to 1000 wppm pre-hydrided samples. Local distributions were characterized thoroughly using Electron Probe Micro-Analysis (EPMA) for oxygen and Elastic Recoil Detection Analysis (ERDA) for hydrogen. The data obtained in this work were included in the pseudo-binary Zircaloy-4 - oxygen phase diagram and have shown that hydrogen has limited influence on the alpha + beta -> beta transus. Regarding the alpha -> alpha + beta transus, no influence of hydrogen concentration in the alpha phase below 400 wppm was evidenced. (C) 2015 Elsevier B.V. All rights reserved.

引用

页码：228 / 236

页数：9

共 50 条

[31] Hydrogen embrittlement of Zircaloy-4 fabricated by ultrasonic additive manufacturing
Yan, Yong
Massey, Caleb P.
Garrison, Ben E.
Taller, Stephen A.
Kang, Soyoung
Nelson, Andrew T.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2024, 914
[32] Amount of hydrogen and loss of ductility in welded joints of zircaloy-4
Fernandez, L
Fernandez, G
Corso, HL
Martinez, R
Tiglio, F
Gonzalez, OA
Meyer, G
HYDROGEN ENERGY PROGRESS XII, VOLS 1-3, 1998, : 1409 - 1414
[33] Reaction of Zircaloy-4 with tellurium under different oxygen potentials
Arima, T
Masuzumi, T
Furuya, H
Idemitsu, K
Inagaki, Y
JOURNAL OF NUCLEAR MATERIALS, 2002, 301 (2-3) : 90 - 97
[34] Effect of thermal history on the terminal solid solubility of hydrogen in Zircaloy-4 (vol 39, pg 16442, 2014)
Kim, Ju-Seong
Kim, Yong-Soo
INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2017, 42 (20) : 14353 - 14353
[35] Effects of hydrogen contents on the mechanical properties of Zircaloy-4 sheets
Tung, Hsiao-Ming
Chen, Tai-Cheng
Tseng, Che-Chung
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2016, 659 : 172 - 178
[36] Kinetics of hydrogen desorption from Zircaloy-4: Experimental and modelling
Juillet, C.
Tupin, M.
Martin, F.
Auzoux, Q.
Berthinier, C.
Miserque, F.
Gaudier, F.
INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2019, 44 (39) : 21264 - 21278
[37] Non-destructive assessment of the thickness of oxide layers on zircaloy-4: influence of hydrogen content
Perotti, A
Lanzani, L
Marengo, JA
Ruch, M
INSIGHT, 2000, 42 (09) : 597 - 602
[38] Investigation of the impact of coatings on corrosion and hydrogen uptake of Zircaloy-4
Daub, K.
Van Nieuwenhove, R.
Nordin, H.
JOURNAL OF NUCLEAR MATERIALS, 2015, 467 : 260 - 270
[39] Modeling and simulation of hydrogen behavior in Zircaloy-4 fuel cladding
Courty, Olivier
Motta, Arthur T.
Hales, Jason D.
JOURNAL OF NUCLEAR MATERIALS, 2014, 452 (1-3) : 311 - 320
[40] CHARACTERIZATION OF HYDROGEN CONTENT IN ZIRCALOY-4 NUCLEAR FUEL CLADDING
Pfeif, E. A.
Lasseigne, A. N.
Krzywosz, K.
Mader, E. V.
Mishra, B.
Olson, D. L.
REVIEW OF PROGRESS IN QUANTITATIVE NONDESTRUCTIVE EVALUATION, VOLS 29A AND 29B, 2010, 1211 : 1317 - +

← 1 2 3 4 5 →