Damage and annealing behavior in neutron-irradiated SiC used as a post-irradiation temperature monitor

2022 ◽  
Vol 512 ◽  
pp. 91-95
Author(s):  
Guangsheng Ning ◽  
Limin Zhang ◽  
Weihua Zhong ◽  
Shenghong Wang ◽  
Jian Liu ◽  
...  
Keyword(s):  
Irradiation Temperature ◽  
Annealing Behavior ◽  
Post Irradiation ◽  
Temperature Monitor

scholarly journals Post-irradiation annealing behavior of helium in irradiated Fe and ferritic-martensitic steels

2018 ◽  
Vol 15 ◽  
pp. 203-207 ◽  
Author(s):  
S. Chen ◽  
Y. Wang ◽  
N. Hashimoto ◽  
S. Ohnuki
Keyword(s):  
Martensitic Steels ◽  
Annealing Behavior ◽  
Post Irradiation

scholarly journals Post-irradiation annealing behavior of irradiation hardening of China low-Cu RPV steel

2020 ◽  
Vol 22 ◽  
pp. 100727
Author(s):  
Zhaonan Ding ◽  
Chonghong Zhang ◽  
Xianlong Zhang ◽  
Yuguang Chen ◽  
Yitao Yang ◽  
...  
Keyword(s):  
Irradiation Hardening ◽  
Annealing Behavior ◽  
Post Irradiation ◽  
Rpv Steel

Microstructure and Post-Irradiation Annealing Behavior of 20% Cold-Worked 316 Stainless Steel

2000 ◽  
Vol 650 ◽  
Author(s):  
J. I. Cole ◽  
T. R. Allen ◽  
H. Kusanagi ◽  
K. Dohi ◽  
J. Ohta
Keyword(s):  
Stainless Steel ◽  
Cold Work ◽  
Microstructural Development ◽  
Dislocation Loops ◽  
Annealing Behavior ◽  
Post Irradiation ◽  
316 Stainless Steel ◽  
Dose Rates ◽  
Cold Worked

ABSTRACTMicrostructural examination and in situ post-irradiation annealing studies were carried out on 20% cold-worked 316 stainless steel (SS) hexagonal duct material following irradiation in the reflector region of the EBR-II reactor. Stainless steel hexagonal ducts were used to house reactor subassemblies and provide a valuable source of information on irradiation behavior of reactor structural materials at lower dose-rates (on the order of 10-8 dpa/sec) than previously examined. The microstructural development of samples irradiated to doses of 1, 20 and 30 dpa is examined, while the post-irradiation annealing behavior of a sample irradiated to 20 dpa is described. Annealing studies were performed at 370 and 500°C to examine the kinetics of radiation damage recovery as a function of annealing temperature. The initial (pre-annealed) microstructures consists of a substantial density of irradiation induced chromium-rich M23C6 and M6C carbides which form both on the grain boundaries and within the grain interiors. Recovery of the cold- work is evident in the 1 dpa sample while samples irradiated to 20 and 30 dpa possess dense populations of voids and dislocation structures consisting of networks of line dislocations and faulted dislocation loops. Results indicate that post-irradiation annealing of the samples at 370°C for 1 hour has little effect on the microstructure, while further annealing at 500°C for 1 hour results in void shrinkage, the formation of small cavities, and a reduction in the dislocation loop and network density.

Positron Annihilation Study of Neutron-Irradiated Nuclear Reactor Pressure Vessel Steels and their Model Alloy: Effect of Purity on the Post-Irradiation Annealing Behavior

2012 ◽  
Vol 733 ◽  
pp. 257-263 ◽  
Author(s):  
Akira Kuramoto ◽  
Yasuyoshi Nagai ◽  
T. Toyama ◽  
T. Takeuchi ◽  
M. Hasegawa
Keyword(s):  
Positron Annihilation ◽  
First Generation ◽  
Nuclear Reactor ◽  
Positron Annihilation Spectroscopy ◽  
Atom Probe ◽  
Model Alloy ◽  
Annealing Behavior ◽  
Post Irradiation ◽  
Alloy Effect ◽  
Positron Annihilation Study

Post-irradiation annealing (PIA) behavior of irradiation-induced microstructural changes and hardening of two kind of A533B (first generation (1stGENS: 0.16 wt.% Cu) and second generation (2ndGENS: 0.04 wt.% Cu)) steels after neutron-irradiation of 3.9 × 1019 n cm–2 at 290 °C has been studied by positron annihilation spectroscopy, atom probe tomography and Vickers microhardness measurements. In the 1stGENS, clear two recovery stages are observed: (i) as-irradiated state to 450 °C and (ii) 450 to 600 °C. The first stage is due to annealing out of the most of irradiation-induced vacancy-related defects (VRDs), and the second stage corresponds to dissolving irradiation-induced Cu-rich solute nano-clusters (CRSCs). The experimental hardening is almost twice of the hardening due to the CRSCs estimated by Russell-Brown model below 350 °C, but almost the same as the estimation from 400 to 550 °C. In the 2ndGENS, the VRDs and non-Cu-rich solute nano-clusters (NCRSCs) recover at 450 °C. No CRSC has been formed even in all the annealing process. The experimental hardening is almost twice of the hardening estimated due to the NCRSCs by Russell-Brown model below 400 °C.

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