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                             91 results found
no title author magazine year volume issue page(s) type
1 Advanced fault diagnosis method for nuclear power plant based on convolutional gated recurrent network and enhanced particle swarm optimization Wang, Hang
151 C p.
 article
2 Aerosol processing of glass for radioactive salt waste immobilization Kang, Hyun Woo
151 C p.
 article
3 A hybrid porous model for full reactor core scale CFD investigation of a prismatic HTGR Wang, Chengqi
151 C p.
 article
4 A linearized coarse mesh finite difference preconditioner for the within-group Krylov subspace iteration based on two-dimensional method of characteristics Zhang, Guangchun
151 C p.
 article
5 A method of dynamic homogenization: application to 2D core calculation Galia, Antonio
151 C p.
 article
6 Analysis of the impact of fuel microstructure on irradiation-enhanced densification using grand potential simulations Greenquist, Ian
151 C p.
 article
7 A new methodology to estimate stochastic uncertainty of MCNP-predicted isotope concentrations in nuclear fuel burnup simulations Chirayath, Sunil S.
151 C p.
 article
8 An improvement to the Kalos’ formula for double layer gamma ray exposure buildup factors for shielding materials of nuclear and radiological facilities Basu, Pew
151 C p.
 article
9 A porous medium model for simulating conjugate heat transfer between wire-wrapped fuel bundles under forced and mixed convection Chen, Yutong
151 C p.
 article
10 Application of complex-step derivative method for k-eigenvalue sensitivity calculation in neutron transport models Wu, Zeyun
151 C p.
 article
11 Application of PLC based smart microgrid controller for sequential load restoration during station blackout of nuclear power plants Khatua, Subhakanta
151 C p.
 article
12 Application of the augmented block Householder Arnoldi method to the calculation of non-fundamental modes of the diffusion equation Hébert, Alain
151 C p.
 article
13 A preliminary study on concrete ablation during ex-vessel cooling in pre-flooded Westinghouse 3-loop NPP reactor cavity Na, Hanbee
151 C p.
 article
14 A radionuclide outlier identification and correlation analysis on low- and intermediate-level radioactive waste Jang, Sung-Chan
151 C p.
 article
15 Assessment of management measures on station blackout accident in Unit-1 Bushehr nuclear power plant Vahman, Navid
151 C p.
 article
16 Bubble coalescence, growth, breakup and distribution in boiling water-cooled packed bed reactor Xu, Guangzhan
151 C p.
 article
17 CFD analysis of thermal-hydraluic behaviors in a LBE cooled 19-pin wire wrapped bundle under porous lumped blockage conditions Lyu, Kefeng
151 C p.
 article
18 CFD simulation of thermal hydraulic phenomena in enclosed cavity of nuclear power plants Chen, Chong
151 C p.
 article
19 Characteristics and linear stability analysis of RELAP5 two-fluid model for two-component, two-phase flow Saraswat, S.P.
151 C p.
 article
20 Characteristics of liquid film rupture at wave plate corner: A short communication Wang, Bo
151 C p.
 article
21 Characterization of high-temperature nuclear fuel-coolant interactions through X-ray visualization and image processing Johnson, Michael
151 C p.
 article
22 Closed-loop experimental investigation of single-phase natural circulation flow phenomena based on temperature and heating power variations Bello, Solomon
151 C p.
 article
23 Comparison between passive reactor cavity cooling systems based on atmospheric radiation and atmospheric natural circulation Takamatsu, Kuniyoshi
151 C p.
 article
24 Constrained Bayesian optimization of criticality experiments Siefman, D.
151 C p.
 article
25 Coupling one-dimensional user code and STAR-CCM+ for simulation of rolling conditions in a rod bundle channel Zhang, Yinxing
151 C p.
 article
26 Criticality benchmark of Monte Carlo code MCS for light water reactor fuel in transportation and storage packages Lee, Hochul
151 C p.
 article
27 Demonstration of prospective application of the dual number automatic differentiation for uncertainty propagation in neutronic calculations Bokov, Pavel M.
151 C p.
 article
28 Derivation of preliminary DCGL for Kori Unit 1 using RESRAD-OFFSITE and comparison with RESRAD-ONSITE Park, Sang June
151 C p.
 article
29 Design, simulation and reconstruction for a fast speed two-phase flow CT with 241Am gamma ray sources Yan, Mingfei
151 C p.
 article
30 Development of a bypass control strategy for supercritical CO2 Brayton cycle cooled reactor system under load-following operation Gao, Chuntian
151 C p.
 article
31 Development of a four-fluid model for condensing steam flows Bolduc, CiCi P.
151 C p.
 article
32 Development of a steady state analysis code for molten salt reactor based on nodal expansion method Cui, Y.
151 C p.
 article
33 Development of thermal hydraulic analysis code of annular fuel under flow blockage condition Xia, Hang
151 C p.
 article
34 Dynamic characteristics and scaling distortion of gravity-driven draining process in Core Makeup Tank Li, Xiangbin
151 C p.
 article
35 Dynamic models and control system design for heated channels in a Canadian SCWR Han, Huirui
151 C p.
 article
36 Editorial Board
151 C p.
 article
37 Effect of par deactivation by carbon monoxide in the late phase of a severe accident Klauck, M.
151 C p.
 article
38 Effects of NaCl addition on magnetite deposition on the outer surfaces of steam generator tubes Lee, Ji-Min
151 C p.
 article
39 Estimation of system code SOCRAT/V3 accuracy to simulate the heat transfer in a pool of volumetrically heated liquid on the basis of BAFOND experiments Dolzhenkov, E.A.
151 C p.
 article
40 Evaluation of the MOC based on the Sanchez-Pomraning method for double heterogeneity system Liang, Yuechao
151 C p.
 article
41 Evolutionary simulated annealing for fuel loading optimization of VVER-1000 reactor Tran, Viet-Phu
151 C p.
 article
42 Experimental and numerical investigation on flow characteristics of inter-wrapper channel in LMFBR Liang, Yu
151 C p.
 article
43 Experimental and theoretical study of jet hydrodynamic breakup behavior with air entrainment Chen, Jingtan
151 C p.
 article
44 Experimental investigation on heat transfer characteristics of oxide layer of molten pool Li, Zongyang
151 C p.
 article
45 Experimental measurements to evaluate the effects of fuel microstructure on fission gas release in thoria Barry, A.
151 C p.
 article
46 Experimental research on the characteristics of steam jet condensation in subcooled water through a double-hole nozzle in one direction Lu, Daogang
151 C p.
 article
47 Experimental study of critical heat flux mechanism on a vertical heated surface under rolling motion Albdour, Samah A.
151 C p.
 article
48 Experimental study on flow modes and transient characteristics in low-pressure equal-height-difference natural circulation system Sun, Jianchuang
151 C p.
 article
49 Experimental study on heat transfer limit of high temperature potassium heat pipe for advanced reactors Wang, Chenglong
151 C p.
 article
50 Experimental study on the hydraulic characteristics of inertia tank after the failure of pump power Wang, Gongqing
151 C p.
 article
51 Experiments and simulation of helium breakdown at high pressure and temperature in a non-uniform electric field You, Qi
151 C p.
 article
52 Feasibility study on burnable poison credit concept to HTGR fuel fabrication from core specification perspective Fukaya, Yuji
151 C p.
 article
53 First order comprehensive adjoint sensitivity analysis methodology (1st-casam) for computing efficiently the exact response sensitivities for physical systems with imprecisely known boundaries and parameters: General theory and illustrative paradigm applications Cacuci, Dan Gabriel
151 C p.
 article
54 Geometry design and performance optimization of a terrestrial radioisotope thermoelectric generator based on finite element analysis Deng, Wei
151 C p.
 article
55 Global variance reduction method based on multi-group Monte Carlo adjoint calculation Shi, Tao
151 C p.
 article
56 Investigation of radiolysis in cement pastes immobilizing simulated evaporator concrentrates Zatloukalová, Jaroslava
151 C p.
 article
57 Kinetic methods in Monte Carlo code RMC and its implementation to C5G7-TD benchmark Guo, Xiaoyu
151 C p.
 article
58 Load-following control of nuclear reactors based on fuzzy input-output model Luan, Xiuchun
151 C p.
 article
59 Measurement, simulation and uncertainty quantification of the neutron flux at the McMaster Nuclear Reactor MacConnachie, Elizabeth L.
151 C p.
 article
60 Mechanism research of two-phase flow regimes during bottom reflooding in narrow rectangular channel Xu, Wei
151 C p.
 article
61 Modeling and neutronic analysis of pin-cell comprising nuclear fuel with different chemical composition and neutron moderator using Monte Carlo code OpenMC Reza, Farshid
151 C p.
 article
62 Modeling and validation of RELAP5 for natural circulation flow in a single PWR fuel assembly Ni, Song
151 C p.
 article
63 Modeling of oxidation of UO2 pellets Abolpour, Bahador
151 C p.
 article
64 NECP-MCX: A hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems He, Qingming
151 C p.
 article
65 Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods Ma, Yugao
151 C p.
 article
66 Nodal Integral method for multi-group neutron diffusion equation in three dimensional cylindrical coordinate system Raj, Manish
151 C p.
 article
67 Numerical optimization of a multiphysics calculation scheme based on partial convergence Cattaneo, Paolo
151 C p.
 article
68 Numerical study on the heat transfer deterioration and its mitigations for supercritical CO2 flowing in a horizontal miniature tube Eze, Chika
151 C p.
 article
69 ONIX: An open-source depletion code de Troullioud de Lanversin, J.
151 C p.
 article
70 Operator action log based monitoring and control and its verification of nuclear power plants Jang, Gwi-sook
151 C p.
 article
71 Performance assessment of longitudinal flow through rod bundle of ETRR-2 Cobalt/Iridium irradiation device Elbakhshawangy, Hesham
151 C p.
 article
72 Phonon parameters fitting for the simulated Thermal-Neutron scattering cross section of H in ZrHx using Unified Monte Carlo method Wang, Lipeng
151 C p.
 article
73 Precise localization of neutron noise sources based on transport theory and comparison with diffusion theory Bahrami, Mona
151 C p.
 article
74 Preferred core conceptual design of pebble bed advanced high temperature reactor Wang, Lianjie
151 C p.
 article
75 Preliminary prediction for survival time of fuel rod under critical heat flux He, Yanan
151 C p.
 article
76 Quasi-Maxwellian Interference Term Functions Guedes, Guilherme
151 C p.
 article
77 Re-evaluation of level 2 PSA results of a VVER-1000 NPP with consideration of innovative severe accident management strategies Mohsendokht, Massoud
151 C p.
 article
78 Revisitation of the studies on covariance data and adjustment analysis: A tribute to M. Salvatores for his great works and remaining future tasks Takeda, Toshikazu
151 C p.
 article
79 Scaling analysis for inertia tank based on the cold state of deep pool-type nuclear heating reactor Wang, Gongqing
151 C p.
 article
80 Sensitivity and uncertainty analyses of a high temperature gas-cooled reactor by using a 44-group covariance library Hartanto, Donny
151 C p.
 article
81 Sensitivity of the neutron multiplication factor to gadolinium isotopes’ nuclear data for light water reactor fuel assemblies in the peak reactivity burnup range Chiba, Go
151 C p.
 article
82 Simulations for worth determination of CPSARs in VVER-1000 reactor using EXCEL and TRIHEX-FA code system Thilagam, L.
151 C p.
 article
83 Study on algorithms for solving depletion sparse matrix based on DESCAR module Guo, Fengchen
151 C p.
 article
84 Study on evaluation method for nuclear emergency rescue measures at containment vessel Ruan, Fang
151 C p.
 article
85 Study on evidence-based LPSA method in nuclear power plant under abnormal operating conditions Lu, Hongxing
151 C p.
 article
86 Thermal-hydraulic efficiency of a modular reactor power plant by using the second law of thermodynamic Norouzi, Nima
151 C p.
 article
87 Thermochemical changes on swelling pressure of compacted bentonite Kim, Minseop
151 C p.
 article
88 Third order adjoint sensitivity analysis of reaction rate responses in a multiplying nuclear system with source Cacuci, Dan Gabriel
151 C p.
 article
89 Three-dimensional thermal–hydraulic coupled analysis in the nuclear waste repository Zhou, Xiangyun
151 C p.
 article
90 Two decades on human reliability analysis: A bibliometric analysis and literature review Hou, Lin-Xiu
151 C p.
 article
91 Virtual element methods for the spatial discretisation of the multigroup neutron diffusion equation on polygonal meshes with applications to nuclear reactor physics Ferguson, J.A.
151 C p.
 article
                             91 results found
 
 Koninklijke Bibliotheek - National Library of the Netherlands