Characterization of different forms of Zr-2.5Nb samples before and after neutron irradiation

被引:20
作者
Silva, Chinthaka [1 ]
Leonard, Keith [1 ]
Trammel, Michael [1 ]
Bryan, Chris [1 ]
机构
[1] Oak Ridge Natl Lab, One Bethel Rd, Oak Ridge, TN 37831 USA
来源
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING | 2018年 / 716卷
关键词
Zir-2.5Nb; Neutron irradiation; E-beam welding; TIG welding; Zirconium hydride; DELAYED HYDRIDE CRACKING; CRYSTALLOGRAPHIC ORIENTATION; ZR-2.5-PERCENT NB; DELTA-HYDRIDES; ZIRCALOY-4; ALLOY; MICROSTRUCTURE; ZIRCONIUM; TUBES;
D O I
10.1016/j.msea.2018.01.059
中图分类号
TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
Deleterious effects of hydride precipitation on the mechanical properties of Zr-based alloy systems have been studied for many years. Most of these studies have been conducted at high-temperature irradiation conditions that are compatible with those in commercial reactor systems, such as light water and pressurized water reactors. Evaluations of hydride effects on the mechanical properties of welded Zr-2.5Nb are sparse among these reported studies. Research on the mechanical properties of Zr-based alloys neutron irradiated at low temperatures (< 100 degrees C) is also very rare in the literature. Since some companies are interested in using Zr-based alloys as structural materials and in other parts such as pressure tubes in small reactor systems, low-temperature irradiation studies of these materials are important. The current work presents an evaluation of the tensile properties of Zr-2.5Nb welded using tungsten inert gas and electron beam welding as a function of hydrogen charging and neutron irradiation at low temperatures (60-100 degrees C).
引用
收藏
页码:296 / 307
页数:12
相关论文
共 21 条
[1]   AGE HARDENING OF ZR-2.5 WT PERCENT NB SLOWLY COOLED FROM (ALPHA+BETA) PHASE FIELD [J].
ALDRIDGE, SA ;
CHEADLE, BA .
JOURNAL OF NUCLEAR MATERIALS, 1972, 42 (01) :32-&
[2]  
Allen TR, 2012, COMPREHENSIVE NUCLEAR MATERIALS, VOL 5: MATERIAL PERFORMANCE AND CORROSION/WASTE MATERIALS, P49
[3]  
[Anonymous], PER TAB EL
[4]   BRITTLE-FRACTURE INDUCED BY HYDRIDES IN ZIRCALOY-4 [J].
BAI, JB ;
PRIOUL, C ;
LANSIART, S ;
FRANCOIS, D .
SCRIPTA METALLURGICA ET MATERIALIA, 1991, 25 (11) :2559-2563
[5]   Optimization of stress relief heat treatment of PHWR pressure tubes (Zr-2.5Nb alloy) [J].
Choudhuri, Gargi ;
Srivastava, D. ;
Gurumurthy, K. R. ;
Shah, B. K. .
JOURNAL OF NUCLEAR MATERIALS, 2008, 383 (1-2) :178-182
[6]   Effect of alloying elements on the properties of Zr and the Zr-H system [J].
Christensen, M. ;
Wolf, W. ;
Freeman, C. M. ;
Wimmer, E. ;
Adamson, R. B. ;
Hallstadius, L. ;
Cantonwine, P. E. ;
Mader, E. V. .
JOURNAL OF NUCLEAR MATERIALS, 2014, 445 (1-3) :241-250
[7]  
Evans J. W., 1971, AECL2982
[8]   Characterization of the variant selection occurring during the α→β→α phase transformations of a cold rolled titanium sheet [J].
Gey, N ;
Humbert, M .
ACTA MATERIALIA, 2002, 50 (02) :277-287
[9]   EFFECT OF NEUTRON-IRRADIATION ON TENSILE PROPERTIES OF ZIRCALOY-2 AND ZIRCALOY-4 [J].
HIGGY, HR ;
HAMMAD, FH .
JOURNAL OF NUCLEAR MATERIALS, 1972, 44 (02) :215-&
[10]   Metallographic and fractographic observations of hydrides during delayed hydride cracking in Zr-2.5% Nb alloy [J].
Jovanovic, MT ;
Shek, GK ;
Seahra, H ;
Eadie, RL .
MATERIALS CHARACTERIZATION, 1998, 40 (01) :15-25