A novel bismuth-nickel-aluminium nanocomposite as a protective barrier against nuclear radiation (Englisch)
- Neue Suche nach: Chandrika, B.M.
- Neue Suche nach: Manjunatha, Holaly Chandrashekara Shastry
- Neue Suche nach: Munirathnam, R.
- Weitere Informationen zu Munirathnam, R.:
- https://orcid.org/0000-0002-9971-8914
- Neue Suche nach: Sridhar, K.N.
- Neue Suche nach: Seenappa, L.
- Neue Suche nach: Manjunatha, S.
- Neue Suche nach: Lourduraj, A.J. Clement
- Neue Suche nach: Chandrika, B.M.
- Neue Suche nach: Manjunatha, Holaly Chandrashekara Shastry
- Neue Suche nach: Munirathnam, R.
- Neue Suche nach: Sridhar, K.N.
- Neue Suche nach: Seenappa, L.
- Neue Suche nach: Manjunatha, S.
- Neue Suche nach: Lourduraj, A.J. Clement
In:
Nuclear Engineering and Design
;
415
;
2023
-
ISSN:
- Aufsatz (Zeitschrift) / Elektronische Ressource
-
Titel:A novel bismuth-nickel-aluminium nanocomposite as a protective barrier against nuclear radiation
-
Beteiligte:Chandrika, B.M. ( Autor:in ) / Manjunatha, Holaly Chandrashekara Shastry ( Autor:in ) / Munirathnam, R. ( Autor:in ) / Sridhar, K.N. ( Autor:in ) / Seenappa, L. ( Autor:in ) / Manjunatha, S. ( Autor:in ) / Lourduraj, A.J. Clement ( Autor:in )
-
Erschienen in:
-
Verlag:
- Neue Suche nach: Elsevier B.V.
-
Erscheinungsdatum:06.10.2023
-
ISSN:
-
DOI:
-
Medientyp:Aufsatz (Zeitschrift)
-
Format:Elektronische Ressource
-
Sprache:Englisch
-
Schlagwörter:
-
Datenquelle:
Inhaltsverzeichnis – Band 415
Zeige alle Jahrgänge und Ausgaben
Die Inhaltsverzeichnisse werden automatisch erzeugt und basieren auf den im Index des TIB-Portals verfügbaren Einzelnachweisen der enthaltenen Beiträge. Die Anzeige der Inhaltsverzeichnisse kann daher unvollständig oder lückenhaft sein.
-
Numerical study of debris bed formation behavior for severe accident in sodium-cooled fast reactor by using least square MPS-DEM methodXu, Ruicong / Liu, Xiaoxing / Cheng, Songbai et al. | 2023
-
Axial compressive behavior of low steel–concrete composite walls with multi-partition steel tubes and concreteYang, Ke / Sun, Guohua / Yang, Wenxia et al. | 2023
-
CFD investigation of fluid and heat transfer in a single-phase natural circulation toroidal loopPinheiro, Larissa C. / Alvim, Antonio Carlos M. et al. | 2023
-
Multiphysics fuel performance modeling of dispersed TRISO-coated particle fuel plate under long-time normal condition and accident conditionsCai, Mengke / Cong, Tenglong / Gu, Hanyang et al. | 2023
-
Development of an accelerator-based neutron source to prototype Mo-99 production, part I: A liquid LBE windowless targetKong, Ran / Wahlen, Robert / Grimm, Terry / Grote, Matthew / Singh, Bhavini / Olivas, Eric / Woloshun, Keith et al. | 2023
-
Reactivity-initiated accidents in two pressurized water reactor high burnup core designsFox, Mason A. / Lindsay, Isabelle O. / Gorton, Jacob P. / Brown, Nicholas R. et al. | 2023
-
Study on application of wood and orthogonal trapezoidal honeycomb aluminum as filling material for nuclear spent-fuel transport casksXing, Youdong / Lu, Shiqing / Yang, Siyi / Wang, Chongyang / Li, Zhongfang et al. | 2023
-
Cross-Evaluation of the PU-MET-FAST criticality benchmark experiments in ICSBEP handbook (by the end of 2022)Fan, Kai / Yin, Yanpeng / Song, Lingli / Wang, Sanbing et al. | 2023
-
Feasibility study on cooling scheme design of the concrete shielding for swimming pool-type low-temperature heating reactorHao, Shuai / Fan, Guangming / Yue, Zhiting / Zhang, Rui / Xu, Junxiu / Ma, Fubing / Li, Zongkun / Yan, Changqi et al. | 2023
-
Phase-field simulation of the microstructure and properties evolution in cast austenitic stainless steels for nuclear power plants during thermal aging and annealingLu, Chenxin / Yang, Zhichao / Chen, Feida / Fan, Minyu / Huang, Pin / Ge, Guojia / Tang, Xiaobin et al. | 2023
-
Improvements in the decay heat model of the RELAP5 for liquid-fueled molten-salt reactorLi, Rui / Xia, Shaopeng / Cheng, Maosong / Dai, Zhimin et al. | 2023
-
Economic evaluation of hydrogen production in second and third units of Bushehr nuclear power plant regarding future need of nuclear fission technologyNaserbegi, A. / Aghaie, M. / Yadollahpour, S. / Sadeghi, K. / Farshbaf, F. et al. | 2023
-
The effect of the future of nuclear energy on the decarbonization pathways and continuous supply of electricity in the European UnionAszódi, Attila / Biró, Bence / Adorján, László / Csaba Dobos, Ádám / Illés, Gergely / Krisztián Tóth, Norbert / Zagyi, Dávid / Tas Zsiborás, Zalán et al. | 2023
-
Electrochemical and spectroscopic study on corrosion behavior of Ni-based alloys in chloride melts: Materials for an integral molten salt fast reactorSuzuki, Yuta / Watanabe, Takashi / Goto, Takuya et al. | 2023
-
Numerical simulation of a shock absorber used for protecting of casks for spent nuclear fuelEidukynas, V. / Dundulis, G. / Babilas, E. et al. | 2023
-
CFD analyses of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheresDehbi, A. / Kapulla, R. et al. | 2023
-
Deep generative modeling-based data augmentation with demonstration using the BFBT benchmark void fraction datasetsAlsafadi, Farah / Wu, Xu et al. | 2023
-
Precipitation behaviour of simulated high-level liquid waste during the denitration process based on two-step vitrificationchangfu, Wang / xu, Liu / bobo, Shao / zhiyi, Xu / Yan, Liu / yun, Wang / shengheng, Tan / zhirong, Liu / shengdong, Zhang et al. | 2023
-
Evaluation of uncertainties associated with best estimates of parameters in the deterministic analysis of a severe accidentRyzhov, N.I. / Dolganov, K.S. / Zvonarev, Yu.A. / Kiselev, A.E. / Kozlova, N.A. / Melnikov, I.A. / Tomashchik, D.Yu. / Philippov, M.F. / Chalyy, R.V. / Shevchenko, S.A. et al. | 2023
-
Study of xenon evolution in UO using multi-grain cluster dynamics modelingBai, He / Hu, Changjun / Zhu, Yuhan / Chen, Dandan et al. | 2023
-
A novel bismuth-nickel-aluminium nanocomposite as a protective barrier against nuclear radiationChandrika, B.M. / Manjunatha, Holaly Chandrashekara Shastry / Munirathnam, R. / Sridhar, K.N. / Seenappa, L. / Manjunatha, S. / Lourduraj, A.J. Clement et al. | 2023
-
Corrigendum to “A study of ammonia-hydrogen-electricity cogeneration coupled to a very high-temperature heat source” [Nucl. Eng. Design 414 (2023) 112585]>Liu, Bin / Huang, Jingzhong / Chen, Wei / Liu, Wei / Pan, Liangming / Zhu, Longxiang / Kang, Zongyao et al. | 2023
-
Assessment of alternative nuclear fuel cycles for the Brazilian nuclear energy systemEstanislau, Fidéllis B.G.L. / Velasquez, Carlos E. / Costa, Antonella L. / Pereira, Claubia et al. | 2023
-
Time-dependent fragility analysis of a nuclear containment structure under internal pressure and chloride-induced corrosionDing, Jia-Yi / Fei, Zi-Jian / Feng, De-Cheng et al. | 2023
-
Neutronic performance evaluation of Plutonium Recycling in two core sizes for a 250 MWt Molten salt reactorWulandari, Cici / Trianti, Nuri / Permana, Sidik / Kinoshita, Motoyasu / Waris, Abdul et al. | 2023
-
Preliminary design of the suppressive containment system based on HPR1000Qi, Xiangjie / Yu, Fangxiaozhi / Meng, Zhaoming / Sun, Zhongning / Zhang, Nan / Guo, Zehua et al. | 2023
-
Eccentric drop of a control rod in the guide tube with annular gap flowLiu, Jun / He, Luyao / Peng, Qing / Chen, Xiaodong / Liu, Xiaoming / Wei, Yueguang et al. | 2023
-
Development and validation of machine learning-based transient identification models in a liquid-fueled molten salt reactor systemZhou, Tianze / Yu, Kaicheng / Cheng, Maosong / Li, Rui / Dai, Zhimin et al. | 2023
-
Prediction of LOCA’s break size and location based on random forest and Multi Tasking Deep Neural NetworkDesterro, Filipe S.M. / Pinheiro, Victor H.C. / Pereira, Cláudio M.N.A. / Schirru, Roberto et al. | 2023
-
Loading method of Li rods for tritium production using High-Temperature Gas-Cooled reactor for fusion reactorsKoga, Yuki / Matsuura, Hideaki / Katayama, Kazunari / Otsuka, Teppei / Goto, Minoru / Hamamoto, Shimpei / Ishitsuka, Etsuo / Nakagawa, Shigeaki / Tobita, Kenji / Someya, Youji et al. | 2023
-
Accident tolerant fuels behavior analysis for Pressurized Water reactor in steady state and transient conditionsReis, Patrícia A.L. / Magalhães, Isabella R. / de Faria, Rochkhudson B. / Costa, Antonella L. / Veloso, Maria Auxiliadora F. / Silva, Clarysson A.M. / Pereira, Claubia et al. | 2023
-
Conceptual design of narrow annular channel heater with rectangular wire coil for the simulator of solid-fuel thorium molten salt reactorYang, Yang / Zou, Yang / Zhou, Chong et al. | 2023
-
Two-phase flow instability characteristics of HTGR Once Through Steam GeneratorsSu, Yang / Li, Xiaowei / Wu, Xinxin et al. | 2023
-
Optimization of IEA-R1 reactor core parameters using the particle swarm algorithmdos Santos, Thiago A. / Genezini, Frederico A. / de Stefani, Giovanni L. et al. | 2023
-
Assessment of radiological dose and emergency planning zones of TRIGA Mark-II research reactor of Bangladesh due to a postulated severe accidental conditionKhaer, M.A. / Hoq, M.A. / Hassan, S.M.T. / Chowdhury, M.T. / Rahman, M.M. et al. | 2023
-
Assessment of the research reactors in opposition to severe accidentsGharari, R. / Ahangari, R. / Esmaili, H. / Hasanifard, E. et al. | 2023
-
Development of an accelerator-based neutron source to prototype Mo-99 production, Part II: A liquid LBE loop under a high vacuumKong, Ran / Wahlen, Robert / Grimm, Terry / Grote, Matthew / Singh, Bhavini / Olivas, Eric / Woloshun, Keith et al. | 2023
-
Dissolution of contaminant Zr-DBP and corrosion of stainless steel by dissolved solutionWang, Guanghui / Du, Yulong / Zhang, Meng / Jiao, Caishan / He, Hui et al. | 2023
-
Method of negative pressure analysis for secondary containment of BWR-6 plantLi-Ying, Huang / Yng-Ruey, Yuann et al. | 2023
-
Modeling and operation strategy of nuclear power plant with electric heat storage in the ancillary service marketWang, Haixin / Mu, Siyu / Li, Gen / Yang, Zihao / Yang, Junyou / Marquez, Fausto Pedro Garcia / Zhou, Xiran / Ma, Yiming / Chen, Zhe et al. | 2023
-
The development of nuclear reactor three-dimensional neutronic thermal–hydraulic coupling code: CorTAF-2.0Dong, Zhengyang / Liu, Kai / Wang, Mingjun / Tian, Wenxi / Qiu, Suizheng / Su, G.H. et al. | 2023
-
Utilizing MATLAB machine learning models to categorize transient events in a nuclear power plant using generic pressurized water reactor simulatorZubair, Muhammad / Akram, Yumna et al. | 2023
-
Thermal Modeling of an eVinci™-like heat pipe microreactor using OpenFOAMPrice, Dean / Roskoff, Nathan / Radaideh, Majdi I. / Kochunas, Brendan et al. | 2023
-
Development of a Fully-Implicit Second-Order system Thermal-Hydraulics analysis code for reactor modeling and simulationsHu, Guojun et al. | 2023
-
Know-why? and know-how? in the development of nuclear talents: An analysis of recent nuclear engineering Ph. D. researchCizelj, Leon / Kljenak, Ivo / Tiselj, Iztok et al. | 2023
-
A proposal for advanced supplementary technologies and a hybrid system with gas-cooled fast reactor concept ALLEGROMelichar, Tomáš / Lukášová, Pavla / Šilhan, Martin et al. | 2023
-
Adaptation of the turbulence model to the heat transfer in a rod bundleSergeenko, K. et al. | 2023
-
Development of optimal framework SARAX/DAKOTA for multiple objective optimization of fast reactor and its applicationDu, Xianan / Li, Xiaoqi / Zheng, Youqi / Wang, Yongping / Zhai, Zi'an et al. | 2023
-
Determination of the linear behavior of FC detectors in Isfahan MNSR using ex-core offline and online experimentsAsgari, Afrouz / Hosseini, Seyed Abolfazl / Choopan Dastjerdi, Mohammad Hosein / Mokhtari, Javad et al. | 2023
-
Thermal analysis and optimization of the heat exchange system in the test loop for the fuel assembly steady-state irradiation based on a re-evaluation methodJunping, Si / Xiaosong, Liu / Wenbin, Zhao / Yuheng, Xu / Jin, Lei / Jinkang, Cheng / Yueyan, Song / Gang, Huang et al. | 2023
-
Simulation of noble metal particle growth and removal in the molten salt fast reactorFrederix, E.M.A. / Komen, E.M.J. et al. | 2023
-
Assessment of minimum allowable thickness of advanced steel (FeCrAl) cladding for accident tolerant fuelAbe, Alfredo / Giovedi, Claudia / Melo, Caio / Teixeira e Silva, Antonio et al. | 2023
-
Predictive maturity of non-linear concrete constitutive models for impact simulationHogancamp, Joshua / Jones, Christopher et al. | 2023
-
Multiscale analysis of the boron dilution sequence in the NuScale reactor using TRACE and SUBCHANFLOWSanchez-Torrijos, Jorge / Zhang, Kanglong / Queral, Cesar / Imke, Uwe / Sanchez-Espinoza, Victor Hugo et al. | 2023
-
Evaluation of the influence of the viscous sublayer on the mechanical stability of fuel plates under axial flow conditionsMoura, A.J.S. / Mattar Neto, M. et al. | 2023
-
Investigating the effect of bedrock temperature on the design of a Brazilian deep geological repository for LEU and reprocessed fuelJonusan, Raoni A.S. / Pereira, Fernando / Pereira, Claubia et al. | 2023
-
Iodine and fission gas release rates from HTR fuel – experiments, correlations, and mathematical modelsVerfondern, K. / Liu, B. / Nabielek, H. / Wang, T. / Allelein, H.J. / Tang, C.H. et al. | 2023
-
A new design of composite fuel with Zr-coated TRISO particles dispersed in metal matrixCheng, Xinyu / Yang, Xu / Liu, Bing / Liu, Malin / Shao, Youlin / Liu, Rongzheng et al. | 2023
-
Editorial Board| 2023
-
Core nuclear design and heat transfer analysis of a megawatt-level SiC coated particle based vehicular micro reactorZhang, Fangyuan / Zhu, Guifeng / Zou, Yang / Yan, Rui / Xu, Hongjie et al. | 2023
-
Development of computational methodology in simulating thermal responses of spent fuel in deep geological disposalTsai, Y.H. / Ferng, Y.M. et al. | 2023
-
Design and application of a special underwater cutting device for the decommissioning of the first HWRR reactor in ChinaRen, Ren / Guo, Yaping / Zhang, Xingwang / Zhang, Lijun / Nie, Peng / Li, Ruizhi / Li, Hongyin / Zhao, Zelong et al. | 2023
-
Review of recent research on heat pipe cooled reactorBo, Wang / Shunhao, Xu / Bin, Wang / Weibing, Wang / Yongchao, Liu / Tong, Li / Shaochun, Hu / Jiayi, Zhang / Mengyao, Wang et al. | 2023
-
Irradiation and analysis of Uranyl Nitrate solutions in different Uranium concentrations for use in subcritical reactors for 99Mo productionPutra, Feryantama / Syarip, Syarip / Sihana, Sihana et al. | 2023
-
Information and analytical system as a promising database used to justify the safety of nuclear energyVurim, Alexandr / Mukhamedova, Nuriya / Baklanova, Yuliya / Syssaletin, Andrey / Akayev, Assan et al. | 2023
-
Site response analysis: Uncertain motions propagating through uncertain elastoplastic soilWang, Hexiang / Wang, Fangbo / Yang, Han / Jeremić, Boris et al. | 2023
-
Bubble transport during SGTR accident in lead-cooled fast reactor: A machine learningDong, Kejian / Ali Khan, Shahid / He, Sihong / Chen, Jingtan / Ding, Peng / Li, Wenhuai / Song, Juqing / Zhao, Jiyun et al. | 2023
-
A revised analysis towards accurate estimation of isothermal temperature coefficients in fast reactors having different power levels and core sizesSathiyasheela, T. / John, Rita / Riyas, A. / Devan, K. et al. | 2023
-
Electricity and water cogeneration using a small PWR of 75 MW(th) coupled to a DCMD desalination plant with heat recoveryde Sampaio, Paulo Augusto Berquó / Alves, Luiz Flávio Rodrigues / de Lourdes Moreira, Maria et al. | 2023
-
Performance evaluation of nuclear fuel in a reactor based on the CAREM 25Afonso, Thadeu H.S.C. / Fontes, Gabriel G.G. / Moreira, Maria L. / Palma, Daniel A.P. et al. | 2023
-
Linear or non-linear stability monitor in BWRs? Introducing a new non-linear monitor based on the fractal spectrumEspinosa-Paredes, Gilberto / Molina-Tenorio, Yanqueleth / Prieto-Guerrero, Alfonso / Olvera-Guerrero, Omar Alejandro et al. | 2023
-
The axial temperature distribution of the channel in the linear reactivity modelFigueiredo, Thales Gonçalves da Silva / Vellozo, Sergio de Oliveira / Oliveira, Claudio Luizde / Cabral, Ronaldo Glicério et al. | 2023
-
Numerical investigation of effects of nickel-base alloy overlay size on the welding residual stresses in an austenite stainless steel narrow-gap girth weldLiu, Chuan / Cai, Zhi / Xiao, Hui / Wang, Kai / Yuan, Quan / Wang, Jianxin et al. | 2023
-
The results of the CLADS-MADE-03 BWR bundle degradation test in steam under 1F Unit 1 postulated conditionsPshenichnikov, Anton / Nagae, Yuji et al. | 2023
-
The effect of central flux trap on-line sampling on Tehran Research Reactor(TRR) core safety parametersBagheri, S. / Khalafi, H. et al. | 2023
-
Analysis of startup process of small modular reactor with OTSGslin, Xian / junjie, Yan / ke, Zhou / guo, Chen / gaojian, Dang / danrong, Song et al. | 2023
-
Study of neutron flux redistribution and shadowing effect in rod worth measurements with the rod drop experimentStefani, Giovanni L. / Carvalho, Guilherme E.S. / Palma, Daniel A.P. / Silva, Marcelo V. / Raitz, Cesar et al. | 2023
-
Development and validation of the MAVR-TA code for analyzing the release and transport of fission products during a severe accident at a VVER NPP. Part 3 – Modelling of the release of fission products from the meltShmelkov, Yu.B. / Shutov, N.V. / Zvonarev, Yu.A. / Petrov, L.V. et al. | 2023
-
Optimum power determination and comparison of multi-pass and OTTO fuel management schemes of HTGR-based PeLUIt reactorTrianti, Nuri / Widiawati, Nina / Wulandari, Cici / Miftasani, Fitria / Rohanda, Anis / Khakim, Azizul / Setiadipura, Topan et al. | 2023
-
Theoretical analysis about model simplifications and boundary conditions on two-phase flow instability of parallel heated tube systemsSu, Yang / Li, Xiaowei / Fan, Hongyi / Wu, Xinxin et al. | 2023
-
Transient fuel behavior analysis of UN fuel with a two-layered SiC cladding based on multiphysics methodHan, Huiyun / Liao, Jihai / Liu, Rong / Liu, Shengyu et al. | 2023
-
Fuel performance evaluation of two high burnup PWR core designs during normal operation, control rod withdrawal, and control rod ejection scenariosLindsay, Isabelle O. / Fox, Mason / Sweet, Ryan T. / Capps, Nathan / Brown, Nicholas R. et al. | 2023