Energy Materials 2017: Materials for Nuclear Energy: Poster Session
Sponsored by: Chinese Society for Metals
Program Organizers: Raul Rebak, GE Global Research; Zhengdong Liu, China Iron & Steel Research Institute Group; Peter Hosemann, University of California, Berkeley; Jian Li, CanmetMATERIALS
Monday 6:00 PM
February 27, 2017
Room: Hall B1
Location: San Diego Convention Ctr
Session Chair: Raul Rebak, GE Global Research
C-17: Effect of Heat Treatments on the Microstructure and Mechanical Properties of Zr-1NB-1SN-0,1Fe Alloy used in the Nuclear Industry: Dielle Costa1; Daniele Baeta1; Monica Rezende1; Neil Medeiros1; 1UFF
Zirconium alloys are widely used in the nuclear industry, principally as the fuel cladding tubes and other structural components for PWR reactors (Pressurized Water Reactor). This is due to their high corrosion resistance at elevated temperatures in combination with a transparency to thermal energy neutrons. Currently, the Zr-1NB-1SN-0,1Fe has highlighted between alloys zirconium . The main advantage of using this alloy is that it shows better resistance to corrosion and higher dimensional stability higher than others. Dimensional stability is a key factor associated to wear resistance and influences directly the insertion of control rods. In this context, the aims of this work is to perform various heat treatments routes in the Zr-1NB-1SN-0,1Fe alloy in order to improve mechanical properties and consequently increase lifetime. It was made microstructural analysis in SEM and TEM. Tensile tests and hardness were performed. Results indicate the best route to optimize mechanical properties.
C-18: Effects of Irradiation on Thermal Conductivity of Nickel Alloys: Mandeep Singh1; Linu Malakkal2; Aseem Chauhan2; Jerzy Szpunar2; Michael P Bradely2; M Chicoine3; 1 PEC University of Technology; 2University of Saskatchewan; 3University of Montreal
Thermal conductivity is a critical property in the design of reactor core and the effect of irradiation on thermal conductivity is of keen interest. The thermal conductivity measurement after irradiation of Inconel X-750 and Inconel 600 were not investigated. Therefore, we prepared square samples of ½ inch width with a thickness of 1.5 mm to simulate the effect of irradiation by neutron using helium implantation. We implanted helium using a 1.7 MV Tandem accelerator with a beam current of 3 μA for around 20 minutes. This produced 1800 atomic parts per million (appm) of He. The analysis of our results clearly shows that the irradiated nickel alloys did not have significant changes in thermal conductivity. The negligible effect of irradiation on thermal conductivity for the nickel alloys is attributed to the recovery of the irradiation-induced defects.
C-19: Reduced Deuterium Retention in Simultaneously Damaged and Annealed Tungsten: Michael Simmonds1; Yongqiang Wang2; Russell Doerner1; Joseph Barton1; Matthew Baldwin1; George Tynan1; 1Center for Energy Research at UCSD; 2Los Alamos National Laboratory
Fusion relevant displacement damage performed at elevated temperature in tungsten (W) and its influence on deuterium (D) retention is explored. Displacement damage performed in room temperature W allows defects to effectively become frozen-in. In this work, 5 MeV Cu ions produced up to 0.2 dpa damage in W samples at various temperatures up to 1243 K were subsequently exposed to D plasma at 383 K to a fluence of 10^24 ions/m^2. Subsequent Nuclear Reaction Analysis (NRA) and Thermal Desorption Spectrometry (TDS) show that increased temperature during damage creation reduces D retention. TDS clearly shows that the Cu ion induced traps are annealed and approach intrinsic concentrations as the simultaneous damage/heating approaches 1243 K. Lastly, analysis of the TDS data is shown to provide an estimate of 0.09 eV for the recovery activation energy, similar to the mobility energy calculated for self-interstitial atoms (SIA) .
C-20: Studies of the Differential Thermal Analysis and Microstructural Characterization of Gd-containing Stainless Steel: Wu Zhaoyu1; Xiao Xueshan2; 1Panzhihua University; 2Shanghai University
The influence of Gd additions on the microstructure and performance of rolling of Gd containing stainless steel was investigated by various microstructural characterization techniques. This work was conducted as a key step toward the development of Gd containing stainless steel for spent nuclear fuel applications. The Gd containing stainless steel was observed to solidify in a manner similar to a binary eutectic system. Small gas tungsten arc melt buttons were prepared to produce Gd containing stainless steel with Gd levels from 0.5-3 wt.% Gd. Electron microprobe measurements showed that Gd is essentially insoluble in the austenite/ferrite matrix. All of the alloys formed an interdendritic intermetallic, and the amount of the intermetallic phase increased with increasing Gd concentration. The interdendritic intermetallic behavior is similar to a simple binary eutectic in several ways. Hardness increased with increasing Gd concentration due to the formation of the intermetallic.