Journal of Nuclear Materials最新文献_第3页

Enhanced thermal stability and irradiation resistance of ODS-W/CuCrZr joints by interlayer employ and interface improvement 通过层间和界面改进，提高了ODS-W/CuCrZr接头的热稳定性和耐辐照性

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-10 DOI: 10.1016/j.jnucmat.2025.155818

Dang Xu , Changcheng Sang , Kaichao Fu , Ruizhi Chen , Pengqi Chen , Yingwei Lu , Dahuan Zhu , Qiu Xu , Jigui Cheng

{"title":"Enhanced thermal stability and irradiation resistance of ODS-W/CuCrZr joints by interlayer employ and interface improvement","authors":"Dang Xu , Changcheng Sang , Kaichao Fu , Ruizhi Chen , Pengqi Chen , Yingwei Lu , Dahuan Zhu , Qiu Xu , Jigui Cheng","doi":"10.1016/j.jnucmat.2025.155818","DOIUrl":"10.1016/j.jnucmat.2025.155818","url":null,"abstract":"<div><div>To enhance the performance of W/Cu divertor materials under high-temperature and irradiation conditions, this study utilizes oxide dispersion-strengthened tungsten (ODS-W) and CuCrZr alloy as base materials. A tri-layer ODS-W/W-50Cu/CuCrZr joint was fabricated using spark plasma sintering (SPS), incorporating a nanoporous surface treatment on the ODS-W surface and a W-50Cu interlayer between ODS-W and CuCrZr. The effects of the surface treatment and W-50Cu interlayer on the microstructure, mechanical properties, and irradiation resistance of the joints were systematically investigated. Results demonstrate that the nanoporous structure significantly enhances interfacial bonding, achieving a tensile strength of 227.6 MPa and a ductility of 5.82 %. Fracture analysis reveals a transition in failure mode. Fractures shift from the ODS-W/Cu interface to the W-50Cu interlayer, accompanied by a transition from brittle to ductile fracture behavior. The W-50Cu interlayer effectively mitigates the mismatch in thermal expansion and minimizes stress concentrations, thereby enhancing interfacial stability at elevated temperatures while maintaining excellent thermal conductivity and mechanical properties. Under irradiation, the W-50Cu interlayer acts as a “trap”, capturing and neutralizing irradiation-induced defects. This mechanism reduces interfacial damage, mitigates hardening, and improves irradiation stability. These findings establish a framework for optimizing W/Cu divertor material design for high-temperature and irradiation-intensive applications.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"611 ","pages":"Article 155818"},"PeriodicalIF":2.8,"publicationDate":"2025-04-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143833758","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}

引用次数: 0

Hydrogen interactions in solution-strengthened niobium-based alloys for direct internal recycling 溶液强化铌基合金中氢相互作用的直接内部回收

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-10 DOI: 10.1016/j.jnucmat.2025.155808

Z.J. Bergstrom , J. Henry , A. Basaran , C. Monton , T. Abrams , B. Grierson

{"title":"Hydrogen interactions in solution-strengthened niobium-based alloys for direct internal recycling","authors":"Z.J. Bergstrom , J. Henry , A. Basaran , C. Monton , T. Abrams , B. Grierson","doi":"10.1016/j.jnucmat.2025.155808","DOIUrl":"10.1016/j.jnucmat.2025.155808","url":null,"abstract":"<div><div>Group 5 metals are promising candidates for hydrogen (H) separation due to their exceptionally high permeability. However, they are prone to fracture-failure caused by H-induced embrittlement which limits their application. First-principles calculations were used to assess the effect of alloying element density in niobium-tungsten (Nb-W), niobium-nickel (Nb-Ni), and niobium-iron (Nb-Fe) alloys on H solubility, diffusivity, and permeability. Ground state energy calculations were performed to assess the average heat of solution and nudged elastic band calculations were performed to assess migration barriers between adjacent H interstitial positions. Migration barriers were used to parameterize a kinetic Monte Carlo diffusion model. Results show diminished H solubility and diffusivity with increasing dopant concentration. H delocalization and enhanced trapping are observed for Ni and Fe dopants, resulting in dramatic reduction in diffusivity and permeability. Nb-W alloys show high permeability and no enhanced trapping, suggesting Nb-W alloys may reduce H-induced embrittlement of membranes in metal foil pumps (MFP).</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"612 ","pages":"Article 155808"},"PeriodicalIF":2.8,"publicationDate":"2025-04-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143837834","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}

引用次数: 0

Fission product solubility and speciation in UN SIMFUEL 裂变产物在unsimfuel中的溶解度和形态

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-09 DOI: 10.1016/j.jnucmat.2025.155815

J.H. Stansby , D.A. Lopes , F. Sweidan , Y. Mishchenko , M. Ranger , M. Jolkkonen , V.K. Peterson , E.G. Obbard , P. Olsson

{"title":"Fission product solubility and speciation in UN SIMFUEL","authors":"J.H. Stansby , D.A. Lopes , F. Sweidan , Y. Mishchenko , M. Ranger , M. Jolkkonen , V.K. Peterson , E.G. Obbard , P. Olsson","doi":"10.1016/j.jnucmat.2025.155815","DOIUrl":"10.1016/j.jnucmat.2025.155815","url":null,"abstract":"<div><div>U(X)N-based SIMFUEL samples, where X represents Zr, Nb, Mo, and Ru, were fabricated using spark plasma sintering. These samples were characterized by neutron diffraction and scanning electron microscopy to gain insights into fission product solubility and speciation at high burnup levels. The fabricated samples included pseudo-binary and higher-order compositions, allowing for the decomposition of individual fission product effects. The characterization revealed the presence of U<sub>1-x</sub>Zr<sub>x</sub>N, Zr<sub>1-x</sub>U<sub>x</sub>N, ZrN, Nb<sub>1-x</sub>U<sub>x</sub>, U<sub>x</sub>Nb<sub>1-x</sub>, Nb<sub>2</sub>N, URu<sub>3</sub>, Mo, and (U,Mo)Ru<sub>3</sub> as distinct fission-product-containing phases. Notably, only Zr was found to be soluble within the primary UN fuel matrix. Significant agglomeration and formation of a (Nb-rich core)–(Nb-poor shell) microstructure was observed for the Nb-containing samples. Mo was the only fission product to form metallic inclusions and the presence of Ru led to the formation of URu<sub>3</sub> in the pseudo-binary system (UN-10at.%Ru), or (U,Mo)Ru<sub>3</sub> in the higher-order samples containing 1, 1.5, and 2 at.% each of all of fission product elements i.e. UN-1at.%(ZrN, Nb, Mo, Ru). No complex nitride precipitates were found to form. The phases identified in the pseudo-binary compositions were analyzed using the Thermodynamics of Advanced Fuels-International Database (TAF-ID) and showed good agreement to experimental data, except for a possible miscibility gap in the UN-ZrN tie line and absence of the (U,Mo)Ru<sub>3</sub> phase.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"611 ","pages":"Article 155815"},"PeriodicalIF":2.8,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143833759","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}

引用次数: 0

The influence of porosity and alloying elements on tungsten-based composites thermal conductivity 孔隙率和合金元素对钨基复合材料导热性能的影响

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-09 DOI: 10.1016/j.jnucmat.2025.155817

Oleksii Popov , Vladimir Vishnyakov

引用次数: 0

Effects of dislocations on He bubble behaviors in Al0.1CoCrFeNi high-entropy alloys at 773 K and 973 K 773 K和973 K时位错对Al0.1CoCrFeNi高熵合金He气泡行为的影响

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-09 DOI: 10.1016/j.jnucmat.2025.155816

Jiulong Zhu , Xudong An , Ning Rong , Tongxuan Jia , Shilv Li , Zijing Huang , Huiqiu Deng , Wangyu Hu , Tengfei Yang

{"title":"Effects of dislocations on He bubble behaviors in Al0.1CoCrFeNi high-entropy alloys at 773 K and 973 K","authors":"Jiulong Zhu , Xudong An , Ning Rong , Tongxuan Jia , Shilv Li , Zijing Huang , Huiqiu Deng , Wangyu Hu , Tengfei Yang","doi":"10.1016/j.jnucmat.2025.155816","DOIUrl":"10.1016/j.jnucmat.2025.155816","url":null,"abstract":"<div><div>The evolutions of He bubbles in Al<sub>0.1</sub>CoCrFeNi high-entropy alloy (HEA) with different dislocation densities were investigated after 400 keV He<sup>+</sup> irradiations at 773 K and 973 K to a fluence of 1.5 × 10<sup>16</sup> cm<sup>−2</sup>. The introduction of dislocations decreases the average size of He bubbles and delays the volume swelling at both temperatures. At 773 K, the homogeneous nucleation of He bubbles at vacancy clusters are dominant. Since the dislocations can absorb the neighboring vacancies and deposited He atoms, the nucleation and growth of He bubbles are suppressed and both the average size and density of He bubbles are decreased with the increase of dislocation density. When the temperature increases to 973 K, the long range diffusion of He is greatly enhanced and the homogeneous nucleation transforms to heterogeneous nucleation. The increase of dislocation density provides more trapping and nucleation sites, thus, resulting in the decrease of average sizes and increase of density of He bubbles. Furthermore, the distribution depth ranges of He bubbles are decreased with dislocation density at both temperatures, which is probably due to the fast migration of He atoms along dislocations. This work demonstrates the beneficial effects of introduction of dislocations on resistance of HEAs to He bubbles, which would provide helpful evidences for designing and optimizing deformation processes to improve the irradiation resistances of HEAs.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"611 ","pages":"Article 155816"},"PeriodicalIF":2.8,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143821051","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}

引用次数: 0

Impacts of helium and hydrogen on the defect evolution in tungsten under high-energy cascades: A molecular dynamics study 高能级联下氦和氢对钨缺陷演化的影响：分子动力学研究

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-08 DOI: 10.1016/j.jnucmat.2025.155814

Mingxuan Jiang , Lixia Liu , Rongyang Qiu , Long Guo , Yangchun Chen , Guangdong Liu , Huiqiu Deng

{"title":"Impacts of helium and hydrogen on the defect evolution in tungsten under high-energy cascades: A molecular dynamics study","authors":"Mingxuan Jiang , Lixia Liu , Rongyang Qiu , Long Guo , Yangchun Chen , Guangdong Liu , Huiqiu Deng","doi":"10.1016/j.jnucmat.2025.155814","DOIUrl":"10.1016/j.jnucmat.2025.155814","url":null,"abstract":"<div><div>Tungsten (W) is widely regarded as one of the primary candidates for plasma-facing materials in fusion reactors. However, during the fusion process, hydrogen (H) and helium (He) are inevitably present in the materials, making it essential to consider their impact on radiation damage. This study employed molecular dynamics simulations to investigate cascade behavior in W under varying H and He concentrations, with primary knock-on atom (PKA) energies ranging from 10 keV to 100 keV. Our results indicate that cascades with higher PKA energies are more likely to exhibit unfragmented configurations. He increases the number of Frenkel pairs (FPs), whereas H has minimal effect. Moreover, both H and He influence cluster size. The variation in FPs counts can be attributed to the vacancy occupancy and threshold displacement energy in W, while changes in cluster size result from their impact on formation energy. Notably, while H and He do not affect the type of dislocation loop, He significantly disrupts the interactions between dislocation loops, promoting the formation of a mixed-dislocation network and inhibiting the development of loops with a single Burgers vector. These findings contribute to a deeper understanding of the influence of H and He on defect evolution in W.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"611 ","pages":"Article 155814"},"PeriodicalIF":2.8,"publicationDate":"2025-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143828160","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}

引用次数: 0

Hydrogen charging effects on the oxidation of Alloy 690 with different cold rolling degrees in high temperature water environment 加氢对690合金不同冷轧度在高温水环境下氧化的影响

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-08 DOI: 10.1016/j.jnucmat.2025.155812

ShiChen Wei , Xu Wang , Xiangguo Li , Haijing Sun , Jian Xu , Testuo Shoji

引用次数: 0

Stress/dynamic straining effects on the corrosion and cracking behavior of a new AFA steel exposed to sCO2 应力/动态应变对新型AFA钢暴露于sCO2下腐蚀和开裂行为的影响

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-08 DOI: 10.1016/j.jnucmat.2025.155811

Xianglong Guo , Qiyin Zhou , Zhu Liu , Jianye Chen , Huigang Shi , Lefu Zhang , Gen Zhang , Yongfu Zhao , Yanping Huang

{"title":"Stress/dynamic straining effects on the corrosion and cracking behavior of a new AFA steel exposed to sCO2","authors":"Xianglong Guo , Qiyin Zhou , Zhu Liu , Jianye Chen , Huigang Shi , Lefu Zhang , Gen Zhang , Yongfu Zhao , Yanping Huang","doi":"10.1016/j.jnucmat.2025.155811","DOIUrl":"10.1016/j.jnucmat.2025.155811","url":null,"abstract":"<div><div>Alumina forming austenitic stainless steel (AFA steel) shows high creep and corrosion resistance in high temperature environments, which makes it a promising candidate structural material for supercritical carbon dioxide (sCO<sub>2</sub>) Brayton cycle system. The compatibility of AFA steel with sCO<sub>2</sub> should be carefully studied as stress corrosion cracking (SCC) poses high threat to the safe operation of the materials. In this work, the SCC of a new AFA steel was evaluated by constant load (CL) testing and slow strain rate tensile (SSRT) testing in 600 °C/20 MPa sCO<sub>2</sub> for 185 h. General corrosion (GC) test was also carried out as a comparison. A protective Cr/Al/Si rich oxide layer was formed on the surface of GC specimen, which is also formed on the uncracked area of CL and SSRT tested specimen. The thickness of Cr/Al/Si rich oxide layer firstly increased and then decreased with the increase of nominal strain, which can be attributed to the change of diffusion mechanism from internal-stress controlled mechanism to defects/cracks-controlled mechanism. Intragranular cracking is the only cracking mode of the AFA steel exposed to sCO<sub>2</sub>, regardless of the testing method, and this result is ascribed to preferentially oxidation of the NiAl precipitates in the AFA steel, which makes it the weak point to be cracked.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"612 ","pages":"Article 155811"},"PeriodicalIF":2.8,"publicationDate":"2025-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143848681","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}

引用次数: 0

Development of a miniaturized ring notched bend specimen for the assessment of the fracture toughness of ODS steel fuel claddings 用于ODS钢燃料包壳断裂韧性评估的小型环形缺口弯曲试样的研制

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-08 DOI: 10.1016/j.jnucmat.2025.155810

Boualem Rais , Jérôme Garnier , Elodie Pons , Bernard Marini , Jacques Besson

{"title":"Development of a miniaturized ring notched bend specimen for the assessment of the fracture toughness of ODS steel fuel claddings","authors":"Boualem Rais , Jérôme Garnier , Elodie Pons , Bernard Marini , Jacques Besson","doi":"10.1016/j.jnucmat.2025.155810","DOIUrl":"10.1016/j.jnucmat.2025.155810","url":null,"abstract":"<div><div>A miniaturized Ring Notched Bend test (mRNB) was developed as a means to assess the fracture toughness of thin-walled tubes. The fracture resistance curve (<em>J</em>–<em>R</em> curve) was derived from both the load-CMOD curve and the load-LLD curve, utilizing a single specimen technique. Following the procedures proposed in the ASTM <span><span>E1820</span><svg><path></path></svg></span> standard <span><span>[1]</span></span>, the elastic unloading methods were employed for the load-CMOD curve. Alternatively, the normalization method was utilized to analyze the load-LLD curve when CMOD measurements was not possible. However, for the application of this methodology to the mRNB test, the standard lacks the necessary functions, including the compliance function, the geometric stress intensity function, and the plastic factor, to process the test results. In this study, the finite element analysis was used to determine the geometric functions required for crack length evaluation during the test, as well as the elastic and plastic components of the <em>J</em>-integral, whether derived from the load—CMOD or load—LLD curve. This methodology was applied to experimentally investigate the crack growth resistance and damage of two types of ODS (Oxide Dispersion Strengthened) steel tubes, (containing specifically 9%Cr and 14%Cr), which are considered candidate materials for fuel claddings of future fast-neutron reactors.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"611 ","pages":"Article 155810"},"PeriodicalIF":2.8,"publicationDate":"2025-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143808484","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}

引用次数: 0

Study on the mechanical properties at high temperatures and relevant mechanism of beryllium oxide ceramics 氧化铍陶瓷的高温力学性能及其机理研究

IF 2.8 2区工程技术

Journal of Nuclear Materials Pub Date : 2025-04-08 DOI: 10.1016/j.jnucmat.2025.155813

Xiang-wen Zhou, Jin Zhang, Ming-dong Hou, Shouchi Zhang, Kaihong Zhang, Rongzheng Liu, Bing Liu, Yaping Tang, Lei Shi

引用次数: 0