Technical Note: Development of a generalized source model for flux estimation in nuclear reactors (English)
- New search for: Loirec, C. Le
- New search for: Hernandez, N.
- New search for: Loirec, C. Le
- New search for: Hernandez, N.
In:
Annals of Nuclear Energy
;
165
;
2021
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ISSN:
- Article (Journal) / Electronic Resource
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Title:Technical Note: Development of a generalized source model for flux estimation in nuclear reactors
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Contributors:Loirec, C. Le ( author ) / Hernandez, N. ( author )
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Published in:Annals of Nuclear Energy ; 165
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Publisher:
- New search for: Elsevier Ltd
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Publication date:2021-10-15
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ISSN:
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DOI:
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Type of media:Article (Journal)
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Type of material:Electronic Resource
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Language:English
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Keywords:
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Source:
Table of contents – Volume 165
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
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A semi-empirical model of radiolytic gas bubble formation and evolution during criticality excursions in uranyl nitrate solutions for nuclear criticality safety assessmentWinter, George E. / Cooling, Christopher M. / Eaton, Matthew D. et al. | 2021
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Coupled MELCOR/COCOMO analysis on quench of ex-vessel debris bedsChen, Yangli / Zhang, Huimin / Ma, Weimin et al. | 2021
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Manufacturing LEU-foil annular target in BrazilDurazzo, Michelangelo / Souza, Jose A.B. / Ianelli, Ricardo F. / Takara, Eriki M. / Neto, Jose S. Garcia / Saliba-Silva, Adonis M. / Urano de Carvalho, Elita F. et al. | 2021
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On the stability of algorithms for enforcing xenon equilibriumCosgrove, P. / Shwageraus, E. et al. | 2021
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The dynamical system scaling analysis for single-phase integral test facilitiesLiu, Zihan / Guo, Yun / Bao, Hui / Peng, Changhong / Lu, Jianchao et al. | 2021
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The assembly homogeneous few-group constants generation method for PWR based on machine learningTan, Kai / Liu, Zhihong / Wei, Chunlin / Liu, Meidan et al. | 2021
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One dimensional analytical model considering end effects for analysis of electromagnetic pressure characteristics of annular linear induction electromagnetic pumpZhang, Zhenyang / Liu, Huijuan / Song, Tengfei / Zhang, Qian / Yang, Lixin / Bi, Keming et al. | 2021
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The transient performances of AP1000 IVR under the conservative scenario of DVI line breakWang, Meng / Chen, Wenzhen / Fu, Shenwei / Xiao, Hongguang et al. | 2021
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Bayesian inverse uncertainty quantification of a MOOSE-based melt pool model for additive manufacturing using experimental dataXie, Ziyu / Jiang, Wen / Wang, Congjian / Wu, Xu et al. | 2021
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Optical and thermal visualization of quench front on hot wall during refloodKim, Woo Shik / Jeon, Byong Guk / Jung, Satbyoul / Kim, Seok / Moon, Sang-Ki et al. | 2021
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The influence of internal flow on the nonlinear dynamics of a flexible tube in tube bundles subjected to two-phase cross-flowLai, Jiang / Yang, Shihao / Tan, Tiancai / Sun, Lei et al. | 2021
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Comparison of probabilistic and deterministic methods for calculation of kinetic parameters of HWZPRTaghizadeh, Leili / Zolfaghari, Ahmadreza / Zangian, Mahdi / Mokhtari, Javad / Sardjono, Yohannes et al. | 2021
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Design of computerized operator support system for technical specification monitoringLee, Subong / Kim, Jonghyun et al. | 2021
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Transformation of classical PSA and DSA into the form of conditional event tree: An approach of human action in time dependent core damage riskNajafi, Alireza / Shahsavand, Athena / Hosseini, Seyed Ali / Shirani, Amir Saeed / Yousefpour, Faramarz / Karimi, Kaveh et al. | 2021
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Cross sections polynomial axial expansion within the APOLLO3® 3D characteristics methodGammicchia, A. / Santandrea, S. / Dulla, S. et al. | 2021
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Optimal study of swordfish fin microchannel heat exchanger for the next generation nuclear power conversion system of lead-based reactorLu, Yiming / Guo, Zhangpeng / Gong, Ya / Zhang, Tianyi / Huang, Yanping / Niu, Fenglei et al. | 2021
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Chemical spectral shift control method for VVER-1000 LEU fuel assembly benchmarkElzayat, T. / Chertkov, Y.B. / Ashraf, O. et al. | 2021
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Gamma dose rates from a spent UO2 fuel Assembly: Calculations vs measurementsPergreffi, Roberto / Rocchi, Federico / Guglielmelli, Antonio / Ferrari, Paolo et al. | 2021
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Development of a dynamic event tree (DET) to analyze SBO accident in VVER-1000/V446 nuclear reactorAmirsoltani, M.E. / Pirouzmand, A. / Nematollahi, M.R. et al. | 2021
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On the use of average power in predicting radioisotope productionsKastanya, Doddy et al. | 2021
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Analytical assessment of VVER-1000 fuel assembly deformation in loss of coolant accidentTaheranpour, N. / Talebi, S. / Pesaraklu, A. et al. | 2021
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Fractional scaling analysis for the thermal hydraulic behavior of pressurizerWang, C. / Zhang, J. / Yan, B.H. et al. | 2021
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Implementation of two-phase gas transport into VERA for molten salt reactor analysisTaylor, Zack / Salko, Robert / Graham, Aaron M. / Collins, Benjamin S. / Maldonado, G. Ivan et al. | 2021
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Internal model control based proportional-integral controller with class topper optimization for power control of molten salt breeder reactor corePradhan, Subrat Kumar / Acharya, Debasis / Das, Dushmanta Kumar et al. | 2021
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Development and validation of a time-dependent deterministic model for neutron noise on CROCUS experimental measurementsBrighenti, A. / Santandrea, S. / Zmijarevic, I. / Stankovski, Z. et al. | 2021
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Effect of geometry and upstream stagnation thermodynamic parameters on CO2 choked flow through orificesHuang, Jiajian / Wang, Yangle / Huang, Yanping / Zhou, Yuan / Tian, Gengyuan / Wang, Junfeng et al. | 2021
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Simulation-based methodology to assess the lattice defects creation as energy storing processPonciroli, Roberto / Shriwise, Patrick / Mei, Zhi-Gang / Stauff, Nicolas / Petersen, Andrew / Romano, Paul et al. | 2021
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Uncertainty analysis of infinite multiplication factor and nuclide number density based on the UAM-PWR benchmark with respect to cross sections, fission yields and decay half-lifeZu, Tiejun / Lu, Zerun / Han, Fenglin / Shu, Nengchuan / Liu, Zhouyu / Cao, Liangzhi / Wu, Hongchun et al. | 2021
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Effects of ATF cladding properties on PWR responses to an SBO accident: A sensitivity analysisAlraisi, Ali / Yi, Yongsun / Lee, Suwon / Alameri, Saeed A. / Qasem, Maryam / Paik, Chan-Young / Jang, Changheui et al. | 2021
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Site selection for radioactive waste disposal facility by GIS based multi criteria decision makingBilgilioğlu, Süleyman Sefa et al. | 2021
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A pure dynamic Monte Carlo code for the neutronic analysis of nuclear reactorsAjami, Mona / Kamkar, Ali / Zangian, Mahdi / Minuchehr, Abdolhamid / Zolfaghari, Ahmadreza et al. | 2021
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Research on robustness of five typical data-driven fault diagnosis models for nuclear power plantsLi, Jiangkuan / Lin, Meng et al. | 2021
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Propagation of VHTRC manufacturing uncertainties with RAVEN/PHISICSRouxelin, Pascal / Alfonsi, Andrea / Strydom, Gerhard / Avramova, Maria / Ivanov, Kostadin et al. | 2021
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On a characteristic method for the SN neutron transport equationWang, Dean et al. | 2021
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Research on non-uniform control rod system of PWRLiu, Cheng / Zhao, Fuyu / Liu, Du / Yang, Bo / Li, Jiangbo / Zhang, Xiulu / Pan, Yingchun / Chen, Zhong et al. | 2021
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An insight into the flow field characteristics of the high temperature liquid Sodium (Na) with cavitation effects in the 600 MW fast reactor systemXie, Zhongliang / Chen, Rugang / Zhu, Weidong et al. | 2021
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Comparison between APOLLO2 and MCNP6 on depletion calculations for an Er-SHB PWR fuel assemblyPergreffi, Roberto / Rocchi, Federico / Guglielmelli, Antonio / Console Camprini, Patrizio et al. | 2021
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Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5Shama, Ahmed / Rochman, Dimitri / Caruso, Stefano / Pautz, Andreas et al. | 2021
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Calculation of delayed neutron precursors’ transit time in the external loop during a flow velocity transient in a Molten Salt ReactorsDiniz, Rodrigo Costa / da Rosa, Felipe Siqueira de Souza / Gonçalves, Alessandro da Cruz et al. | 2021
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Analytical nodal method for solution of neutron diffusion equation in polar coordinatesRaj, Manish / Ahmed, Nadeem / Singh, Suneet et al. | 2021
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A new method to solve the neutron transport problem of spherical structureLiu, Yang / Shi, Hangyu / Cao, Liangzhi / Zheng, Qi / Ouyang, Xiaoping et al. | 2021
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Proliferation resistance assessment of a typical pebble bed reactor fuelMulyana, Dany / Chirayath, Sunil S. et al. | 2021
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Robust controller design for small pressurized water reactors using non-smooth optimizationWang, Pengfei / Jiang, Qingfeng / Wan, Jiashuang / Wu, Shifa et al. | 2021
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A two-phase three-field modeling framework for heat pipe application in nuclear reactorsShi, Shanbin / Liu, Yang / Yilgor, Ilyas / Sabharwall, Piyush et al. | 2021
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The cross section measurements of 131X produced in 238U(n,f) reaction induced by 14 MeV neutronYang, Luocheng / Han, Yafei / Dai, Xiaorong / Qin, Qing / Wang, Qiang / Zhang, Shuo / Fang, Kaihong / Lan, Changlin et al. | 2021
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Implementation of a built-in self-test for nuclear power plant FPGA-based safety-critical control systemsLin, Zequn / Wang, Lingzhi / Cai, Yuanfeng / Wang, Fanyu / Wu, Yichun et al. | 2021
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Quasi-differential neutron induced neutron emissions from 235U, and 239PuMohindroo, Kumar S. / Danon, Yaron / Blain, Ezekiel / Devlin, Matthew / Kelly, Keegan J. et al. | 2021
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Analysis of double-layered buffer in high-level waste repositoryTan, Yunzhi / Xu, Xun / Ming, Huajun / Sun, De'an et al. | 2021
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Study on the representativeness of airborne effluent sampling in the stack of a high-temperature gas-cooled pebble-bed modular reactorSun, Qi / Peng, Wei / Li, Peng / Xie, Feng / Ding, Shihai et al. | 2021
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Single neutron tracking method for calculating the probability of survival based on the RMC codeJia, Conglong / Shi, Guanlin / Feng, Zhiyuan / Guo, Xiaoyu / Wang, Kan / Huang, Shanfang / Liang, Jingang et al. | 2021
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Editorial Board| 2021
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Experimental analysis of step reactivity insertion effect on reactor power, fuel temperature and reactor period in BAEC TRIGA research reactorHossain, Nazmul / Soner, Md. Abdul Malek / Prodhan, Md. Mahidul Haque / Sahadath, Md. Hossain / Kabir, Khorshed Ahmad et al. | 2021
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Pressure drop and flow characteristics in partially blocked wire wrapped rod bundlesBovati, Octavio / Alper Yildiz, Mustafa / Hassan, Yassin / Vaghetto, Rodolfo et al. | 2021
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Evaluation of a freeze-tolerant decay heat removal system redundancy for fluoride salt-cooled high-temperature reactors (FHR)Liu, Maolong / Zeng, Chen / Liu, Limin / Gu, Hanyang et al. | 2021
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Risk analysis virtual ENvironment for dynamic event tree-based analysesAlfonsi, Andrea / Mandelli, Diego / Parisi, Carlo / Rabiti, Cristian et al. | 2021
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Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditionsSun, Hao / Liu, Xiao / Liao, Haoyu / Wang, Chenglong / Zhang, Jing / Tian, Wenxi / Qiu, Suizheng / Su, Guanghui et al. | 2021
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Technical Note: Development of a generalized source model for flux estimation in nuclear reactorsLoirec, C. Le / Hernandez, N. et al. | 2021
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