{"title":"Evaluation of boron evaporation kinetics from stainless-steel–B4C alloy during steam oxidation at high temperatures","authors":"Kosuke Inoue , Ayumi Itoh , Masato Mizokami , Mutsumi Hirai","doi":"10.1016/j.jnucmat.2024.155456","DOIUrl":"10.1016/j.jnucmat.2024.155456","url":null,"abstract":"<div><div>To understand the core degradation process at the Fukushima Daiichi Nuclear Power Station, the oxidation of boron carbide–stainless steel alloy under steam starvation condition was studied at temperatures in the range of 1,288–1,573 K. Low steam supply led to swift Fe–O layer formation, embedding Fe–B–O and Fe–Cr–O, and boron evaporation mainly as oxides was observed through the Fe–B–O phase precipitated in the Fe–O layer. The rate constant of boron evaporation <em>k</em><sub>B</sub> was derived from the measured data as <em>k</em><sub>B</sub> = 0.0157 <em>exp</em> (–79.8 × 10<sup>3</sup>/<em>RT</em>) for <em>T</em> ≥ 1,423 K and <em>k</em><sub>B</sub> = 8.69 × 10<sup>−5</sup> <em>exp</em> (–44.4 × 10<sup>3</sup>/<em>RT</em>) for <em>T</em> < 1,423 K where <em>R</em> and <em>T</em> are the gas constant and temperature, respectively. The obtained constant was comparable to the reaction rate of B<sub>4</sub>C oxidation. In addition, a test with an even more decreased steam supply was conducted to examine the impact of steam quantity on the boron evaporation kinetics. Consequently, it was confirmed that decreasing the oxygen supply resulted in a slowdown of outer Fe–O layer formation, which enhances the outwards diffusion of B and allows greater evaporation of B oxides.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"603 ","pages":"Article 155456"},"PeriodicalIF":2.8,"publicationDate":"2024-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142537323","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Zixie Wang , Jie Pan , Ao Liu , Li Zhang , Zeyuan Sun , Zhen Wang , Jun Li , Xueshan Xiao
{"title":"Microstructure and properties controlling of Al-xGd alloys for thermal neutron absorbing","authors":"Zixie Wang , Jie Pan , Ao Liu , Li Zhang , Zeyuan Sun , Zhen Wang , Jun Li , Xueshan Xiao","doi":"10.1016/j.jnucmat.2024.155447","DOIUrl":"10.1016/j.jnucmat.2024.155447","url":null,"abstract":"<div><div>A novel lightweight thermal neutron absorbing Al-<em>x</em>Gd alloy (<em>x</em> = 2.5, 5, and 10 wt.%) with tunable mechanical properties was fabricated by induction melting followed by a rolling process and an annealing treatment. During solidification, the Al<sub>3</sub>Gd phase predominantly formed and was distributed along grain boundaries. Cold rolling crushed and redistributed the Al<sub>3</sub>Gd phase throughout the matrix. Furthermore, the large deformation imposed on the material during cold rolling enhanced the work hardening effect and promoted dynamic recrystallization. The load transfer strengthening effect was influenced by the size, volume fraction, and distribution of the second phase. The spheroidization of the second phase increased rapidly and then remained stable during 5000 h long-term aging at 400 °C. The thermal neutron absorbing performance of the Al-5Gd alloy is comparable to the 30 %B<sub>4</sub>C/Al composite evaluated by Monte Carlo simulations. Furthermore, Al-5Gd alloy exhibited higher plasticity (>20 %). This novel Al-<em>x</em>Gd alloy is a promising candidate for future lightweight thermal-neutron-absorbing materials.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"603 ","pages":"Article 155447"},"PeriodicalIF":2.8,"publicationDate":"2024-10-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142537322","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Le Zhang , Bo Sun , Qili Zhang , Haifeng Liu , Haifeng Song
{"title":"The reaction mechanism of CO2 on PuO2 and α-Pu2O3 surfaces","authors":"Le Zhang , Bo Sun , Qili Zhang , Haifeng Liu , Haifeng Song","doi":"10.1016/j.jnucmat.2024.155451","DOIUrl":"10.1016/j.jnucmat.2024.155451","url":null,"abstract":"<div><div>Within DFT+<em>U</em>-D3 scheme, we systematically investigate the major steps of CO<sub>2</sub> reaction on Pu-oxide surfaces, including CO<sub>2</sub> adsorption, dissociation and CO releasing. On intact Pu-oxide surfaces, the chemical adsorption of CO<sub>2</sub> needs to be activated, while the dissociation is unlikely to happen. Interestingly, both steps can be notably promoted when Pu-oxide surfaces are covered with *H or *OH from dissociated H<sub>2</sub>O, which is fully consistent with the experimental findings that moisture can boosting CO<sub>2</sub> adsorption on PuO<sub>2</sub> surface. Specifically, the polarons induced by *H or *OH show strong couplings with CO<sub>2</sub>, which first activate the barrier-less chemisorption of CO<sub>2</sub> and then promote the dissociation of CO<sub>2</sub> by weaken the C<img>O bond. Furthermore, we find that the oxidation state of Pu in its oxides determines the tendency of CO releasing step, which is endothermic and exothermic on PuO<sub>2</sub> and α-Pu<sub>2</sub>O<sub>3</sub> surfaces, respectively. Thus, we predict the reaction of CO<sub>2</sub> on Pu-oxide surface is not impossible, especially when PuO<sub>2</sub> is reducing to α-Pu<sub>2</sub>O<sub>3</sub> during the long-term storage. This work reveals the reaction mechanism and possible reactive pathway of CO<sub>2</sub> on Pu-oxides, which provides a significant step forward in the understanding of the surface reactions of actinide oxides.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"603 ","pages":"Article 155451"},"PeriodicalIF":2.8,"publicationDate":"2024-10-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142440983","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Yi Liu , Yusheng Zhang , Lianwen Wang , Jinping Wu , Xin Jia , Jianping Xu , Zhonglin Shen , Naizhi Liu , Chengze Liu
{"title":"Accelerated failure behavior of Zr702 in boiling nitric acid solutions under constant stress loading","authors":"Yi Liu , Yusheng Zhang , Lianwen Wang , Jinping Wu , Xin Jia , Jianping Xu , Zhonglin Shen , Naizhi Liu , Chengze Liu","doi":"10.1016/j.jnucmat.2024.155453","DOIUrl":"10.1016/j.jnucmat.2024.155453","url":null,"abstract":"<div><div>The constant stress tensile deformation behavior of commercial Zr702, used in spent fuel reprocessing industry, was investigated in 108 °C/200 MPa nitric acid solutions and non-corrosive silicone oil. Microscopic characterization of surface as well as cross-section of deformed Zr702 was carried out. In silicone oil, there were minimal cracks observed on the sample's surface. However, a significant number of cracks appeared on the sample's surface in nitric acid solutions. In nitric acid solutions, at the interface between the oxide layer and the matrix, cracks occurred, extended, the oxide film fractured, cracks further expanded, and the stress concentration at the cracks tip led to the formation of new cracks. This cyclic process resulted in the strength of the material decreasing and accelerated failure.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"603 ","pages":"Article 155453"},"PeriodicalIF":2.8,"publicationDate":"2024-10-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142440985","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"The capacity of disclinated non-equilibrium GBs to accommodate point defects in tungsten","authors":"Yingchong Xu , Hongxian Xie , Guang-Hong Lu","doi":"10.1016/j.jnucmat.2024.155442","DOIUrl":"10.1016/j.jnucmat.2024.155442","url":null,"abstract":"<div><div>Experimental observations reveal that disclinated non-equilibrium grain boundaries (GBs) exist extensively in polycrystalline metals; however, the interaction between these GBs and irradiation-induced point defects is rarely reported. In the present work, Molecular statics simulation was used to evaluate the capacity of disclinated non-equilibrium GBs to accommodate point defects in tungsten. Simulation results showed that disclinated non-equilibrium GBs are more efficient sinks for point defects than their equilibrium counterparts because of long-range stress field around them. Continuous segregation of point defects will change the structure of the disclinated non-equilibrium GBs and leads to the GBs tending to relax to equilibrium state. According to theoretical calculation, the disclinated non-equilibrium GBs can absorb a large number of point defects before transforming into equilibrium state; therefore, disclinated non-equilibrium GBs have very strong capacity to accommodate point defects and can be used as strong defect sinks for developing radiation resistance materials.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"603 ","pages":"Article 155442"},"PeriodicalIF":2.8,"publicationDate":"2024-10-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142440984","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"First-principles thermodynamical modeling of molecular reactions on α-U(001) and α-UH3(001) surfaces and their influence on hydrogen activation","authors":"Jinfan Chen, Tao Tang","doi":"10.1016/j.jnucmat.2024.155455","DOIUrl":"10.1016/j.jnucmat.2024.155455","url":null,"abstract":"<div><div>Density functional theory calculations coupled with thermodynamic analysis have been performed to investigate the reactions of hydrogen and impurity gases including O<sub>2</sub>, CO<sub>2</sub>, CO, N<sub>2</sub> on α-U(001) and α-UH<sub>3</sub>(001) surfaces. Binding strength of adsorbates on α-UH<sub>3</sub> is calculated to be weaker than α-U, suggesting enhanced poisoning-resistant properties of U-hydride compared to its metallic state. Surface phase diagrams of U under binary H<sub>2</sub>-O<sub>2</sub>, H<sub>2</sub>-N<sub>2</sub> and H<sub>2</sub>-CO gaseous environments show that while N and C elements prefer to stay in their hydrogenated states on the hydride surface, isolated O atoms favorably interact with both α-U(001) and α-UH<sub>3</sub>(001), indicating the heavily poisoning effect of impurities containing oxygen. Global optimization of partially oxidized α-U(001) slabs induces surface geometry reconstruction and the activity of oxidized surfaces toward hydrogen adsorption can be linearly correlated with local electronic and atomic properties of the adsorption site.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"603 ","pages":"Article 155455"},"PeriodicalIF":2.8,"publicationDate":"2024-10-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142537321","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Effects of coolant pH on crud deposition behavior on fuel cladding tube under subcooled nucleate boiling condition in high temperature pressurized water","authors":"Zihao Lin , Ziyu Zhang , Jibo Tan , Xinqiang Wu","doi":"10.1016/j.jnucmat.2024.155454","DOIUrl":"10.1016/j.jnucmat.2024.155454","url":null,"abstract":"<div><div>The effects of coolant pH on the crud deposition behavior on the Zr alloy and the FeCrAl fuel cladding tubes under subcooled nucleate boiling condition were investigated. With the increase of coolant pH, the coverage rate and thickness of crud on the surfaces of both the Zr alloy and the FeCrAl fuel cladding tubes showed a decreasing trend. The solubility of crud compositions was reduced due to the increase of coolant pH, which resulted in the inhibition of the crud deposition process caused by SNB condition. Consequently, the elevated coolant pH value reduced the amount of crud on the surface of the fuel cladding tube.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"603 ","pages":"Article 155454"},"PeriodicalIF":2.8,"publicationDate":"2024-10-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142440986","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Xian-Wei Zheng , Li Jiang , Kai Wang , Qing-Chun Zhu , Jian-Ping Liang , Chao-Wen Li , Zhi-Jun Li , Guang-Dong Che
{"title":"Corrosion and Te embrittlement behaviors of Ni-Mo-Cr-Nb alloy in Te-containing molten salts","authors":"Xian-Wei Zheng , Li Jiang , Kai Wang , Qing-Chun Zhu , Jian-Ping Liang , Chao-Wen Li , Zhi-Jun Li , Guang-Dong Che","doi":"10.1016/j.jnucmat.2024.155450","DOIUrl":"10.1016/j.jnucmat.2024.155450","url":null,"abstract":"<div><div>The corrosion and Te embrittlement behaviors of Ni-Mo-Cr-Nb based alloy in the Te-containing molten salts have been investigated as compared with the standard GH3535 alloy. Nb is more resistant to molten salt dissolution than Cr due to the less negative Gibbs formation energy of fluoride and the more sluggish lattice diffusion. Furthermore, it was verified the Ni-Mo-Cr-Nb alloy possesses the obvious better Te embrittlement resistance than GH3535 alloy. Our results confirmed that Ni-Mo-Cr-Nb alloy is one of the most promising candidate materials in molten salt reactors.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"603 ","pages":"Article 155450"},"PeriodicalIF":2.8,"publicationDate":"2024-10-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142432456","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Qi Sun , Yu Qin , Xiaoqiang Fan , Yanxiang Liang , Xue Mi , Minhao Zhu
{"title":"Insight into the fretting corrosion behavior of 316L steel in liquid lead-bismuth eutectic at 500°C","authors":"Qi Sun , Yu Qin , Xiaoqiang Fan , Yanxiang Liang , Xue Mi , Minhao Zhu","doi":"10.1016/j.jnucmat.2024.155448","DOIUrl":"10.1016/j.jnucmat.2024.155448","url":null,"abstract":"<div><div>Due to flow induced vibration caused by coolant circulation, fretting corrosion inevitably occurs between fuel cladding, heat exchanger tubes and their holders in Gen IV lead-bismuth eutectic (LBE) cooled nuclear reactors. In the current work, fretting corrosion behavior of 316 L steel in oxygen-saturated LBE at 500 °C has been investigated. It is shown that within the gross slip regime, the microstructure under fretting interface presents a stratified structure, composed of third body layer, oxide scales and plastic deformation layer. At the early stage of fretting corrosion, the dominant damage mechanism is fretting wear, showing that the thickness of third body layer is much larger than that of oxide scale. As fretting time increases, the dominant damage mechanism is gradually changed to LBE corrosion and fretting wear together, as the visible oxide scale is formed next to the third body layer. Moreover, the growth rate of oxide scales under fretting interface is accelerated by over an order of magnitude compared to that when 316 L steel exposed to LBE directly. In particular, after 60 h exposure, the thicknesses of oxide scale related to the worn and unworn regions are ∼4.5 μm and ∼0.2 μm, respectively. The occurrence of such phenomenon is thought to be ascribed to the severe plastic deformation under fretting contact interface, since the crystal defects served as perfectional nano-channels can promote the diffusivity of oxygen atoms. In addition, the acceleration diffusivities of oxygen atoms caused by the local high contact stress may also be responsible for this matter.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"603 ","pages":"Article 155448"},"PeriodicalIF":2.8,"publicationDate":"2024-10-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142432461","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
N. Kvashin , N. Anento , G. Bonny , A. Serra , L. Malerba
{"title":"On the capabilities of k-ART over MD for the study of the kinetics of small point defect clusters in α-Fe","authors":"N. Kvashin , N. Anento , G. Bonny , A. Serra , L. Malerba","doi":"10.1016/j.jnucmat.2024.155444","DOIUrl":"10.1016/j.jnucmat.2024.155444","url":null,"abstract":"<div><div>Molecular Dynamics simulations, while contributing to the understanding of the mechanisms of diffusion and interactions of point defects and their clusters, are inherently limited in their temporal scope (few nanoseconds). This constraint becomes particularly evident when studying the dynamics of vacancies at low temperatures, where their jump frequency is exceedingly low, posing challenges for accurate reproduction. Additionally, the size of the simulation box imposes constraints, influencing the representation of the system and potentially affecting the accuracy of results. A relatively new kinetic activation-relaxation technique (k-ART) efficiently resolves the limitations of MD simulations, such as computation time and system dimensionality, without the need for a priori knowledge of the simulated system. This technique enables simulations lasting up to several seconds and encompassing systems with higher dimensions. In this paper we check the validity of k-ART to reproduce accurately the migration mechanisms and energies of point defects and small clusters, previously obtained by MD and validated experimentally. We point out the advantages and difficulties of using AKMC with k-ART.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"603 ","pages":"Article 155444"},"PeriodicalIF":2.8,"publicationDate":"2024-10-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142445682","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}