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                             62 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A fuzzy-logic-based pressure setpoint modification method for pressurized water reactor pressurizers Wang, Pengfei
2020
135 C p.
artikel
2 A multi-scale and multi-physics approach to main steam line break accidents using coupled MASTER/CUPID/MARS code Park, Ik Kyu
2020
135 C p.
artikel
3 Analyses of LOFT LP-FW-1 using SPACE code Choi, Chiwoong
2020
135 C p.
artikel
4 Analyses of operation performance of advanced secondary passive residual heat removal system in PWR Li, Liangguo
2020
135 C p.
artikel
5 Analysis of fluctuation and breakdown characteristics of liquid film on corrugated plate wall Wang, Bo
2020
135 C p.
artikel
6 An analytical discrete ordinates nodal solution to the two-dimensional adjoint transport problem Barichello, L.B.
2020
135 C p.
artikel
7 An approximation function model for solving effective radiative heat transfer in packed bed Wu, Hao
2020
135 C p.
artikel
8 An iterative fission matrix scheme for calculating steady-state power and critical control rod position in a TRIGA reactor Topham, Tyler J.
2020
135 C p.
artikel
9 A non-linear stability monitor for boiling water reactors Olvera-Guerrero, Omar Alejandro
2020
135 C p.
artikel
10 Application of a 3D model in the transient system analysis of sodium-cooled fast reactor Ge, Li
2020
135 C p.
artikel
11 Application of total variation denoising in nuclear power plant signal pre-processing Yang, Bo
2020
135 C p.
artikel
12 A radiation avoiding algorithm of path optimization for radiation protection of workers and robots Tan, Ke
2020
135 C p.
artikel
13 CFD analysis of intra and inter fuel assembly mixing Bieder, Ulrich
2020
135 C p.
artikel
14 CFD simulation and analysis of reactor integral hydraulic tests Chen, Shuo
2020
135 C p.
artikel
15 Computational flow and heat transfer design and analysis for 1/12 gas-cooled space nuclear reactor Meng, Tao
2020
135 C p.
artikel
16 Conceptual study on a novel method for detecting nuclear material using a neutron source Komeda, Masao
2020
135 C p.
artikel
17 Development of a three-field mechanistic model for dryout prediction in annular flow Gui, Minyang
2020
135 C p.
artikel
18 Development of 3-D parallel first-collision source method for discrete ordinate code JSNT-S Yang, Chao
2020
135 C p.
artikel
19 Development of the integrated parallelism strategy for large scale depletion calculation in the Monte Carlo code RMC Liu, Shichang
2020
135 C p.
artikel
20 Editorial: A preface to the special issue on “PHYSOR-2018: Reactor Physics Paving the Way Towards More Efficient Systems, 22–26 April 2018, Cancun, Mexico” François, Juan-Luis
2020
135 C p.
artikel
21 Editorial Board 2020
135 C p.
artikel
22 Effects of compensating for fuel losses during the melt-refining process for a small CANDLE reactor Hoang, Van Khanh
2020
135 C p.
artikel
23 Enhanced heat transfer and reduced pressure loss with U-pattern of helical wire spacer arrangement for liquid metal cooled-fast reactor fuel assembly Jeong, Yeong Shin
2020
135 C p.
artikel
24 Experimental and numerical investigation for the geometrical parameters effect on the labyrinth-seal flow characteristics of fast reactor fuel assembly Qin, Haiqi
2020
135 C p.
artikel
25 Experimental research on assembly section stiffness and bending stiffness for sodium-cooled fast reactor Ma, Zehua
2020
135 C p.
artikel
26 Experimental research on subcooled boiling heat transfer for natural circulation flow in a vertical 3 × 3 rod bundle Tian, Chunping
2020
135 C p.
artikel
27 Experimental study of heat transfer outside C-shaped tube in water tank Liu, Yanbin
2020
135 C p.
artikel
28 Feasibility assessment of using external neutron and gamma radiation measurements for monitoring the state of fuel assemblies in dry storage casks Rachamin, Reuven
2020
135 C p.
artikel
29 Feasibility study of thorium-fueled molten salt reactor with application in radioisotope production Zheng, Gangyang
2020
135 C p.
artikel
30 Fractional-order particle swarm based multi-objective PWR core loading pattern optimization Zameer, Aneela
2020
135 C p.
artikel
31 Implementation of the CPU/GPU hybrid parallel method of characteristics neutron transport calculation using the heterogeneous cluster with dynamic workload assignment Song, Peitao
2020
135 C p.
artikel
32 Influence of the spatial Pu variation for evaluating the Pu content in spent nuclear fuel using Support Vector Regression Woo, Seung Min
2020
135 C p.
artikel
33 Investigation of CMT behavior between the ATLAS and SMART-ITL tests Kim, Yeon-Sik
2020
135 C p.
artikel
34 Neutron spectrum unfolding of the multiple activation foils based on sparse representation Liu, Bin
2020
135 C p.
artikel
35 New analytical formulations for the Doppler broadening function and interference term based on Kaniadakis distributions de Abreu, Willian V.
2020
135 C p.
artikel
36 Nuclear material input accountancy with a representative sampling method Yoo, Tae-Sic
2020
135 C p.
artikel
37 Numerical study of enhanced and deteriorated heat transfer phenomenon in supercritical pipe flow Sahu, Suresh
2020
135 C p.
artikel
38 On a measurement approach to support evaluation of thermal scattering law data Hawari, Ayman I.
2020
135 C p.
artikel
39 On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients Siefman, D.
2020
135 C p.
artikel
40 Optimization of software development life cycle quality for NPP safety software based on a risk-cost model Lee, Sang Hun
2020
135 C p.
artikel
41 Overlapping communication and computation of GPU/CPU heterogeneous parallel spatial domain decomposition MOC method Liang, Liang
2020
135 C p.
artikel
42 Performance and deterioration of forward osmosis membrane exposed to various dose of gamma-ray irradiation Liu, Xiaojing
2020
135 C p.
artikel
43 Phase-frequency characteristic based measurement of sodium flow rate using PMSF with embedded bluff body Yan, Xiao-Xue
2020
135 C p.
artikel
44 Preliminary surface soil area factor for elevated residual radioactivity of Kori Unit 1 considering adjacent Unit 2 Byon, Jihyang
2020
135 C p.
artikel
45 Publisher’s Note 2020
135 C p.
artikel
46 Radial distributions of power and fuel temperature in annular U3Si2 fuel with FeCrAl cladding Chen, Shengli
2020
135 C p.
artikel
47 Research on the on-the-fly homogenization method based on RMC code for criticality calculations Yuan, Yuan
2020
135 C p.
artikel
48 Second-order adjoint sensitivity analysis of a general ratio of functionals of the forward and adjoint fluxes in a multiplying nuclear system with source Cacuci, Dan Gabriel
2020
135 C p.
artikel
49 Sensitivity and uncertainty analysis of the vessel lower head failure mode and melt release conditions in Nordic BWR using MELCOR code Galushin, Sergey
2020
135 C p.
artikel
50 Serpent2-SUBCHANFLOW pin-by-pin modelling capabilities for VVER geometries García, Manuel
2020
135 C p.
artikel
51 Solution of one-group space- and time-dependent neutron kinetics equations for a reflected slab reactor Maleki, Bahram R.
2020
135 C p.
artikel
52 Status of computational fluid dynamics for in-vessel retention: Challenges and achievements Shams, A.
2020
135 C p.
artikel
53 Study on the water seal formation process in advanced PWR pressurizer using CFD method Wang, Xi
2020
135 C p.
artikel
54 The collimator shape design of segmented gamma-ray scanning for radioactive waste Suxia, Hou
2020
135 C p.
artikel
55 The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part II: BWRs Morrison, S.L.
2020
135 C p.
artikel
56 The effect of Am241 on UK plutonium recycle options in thorium-plutonium fuelled LWRs – Part I: PWRs Morrison, S.L.
2020
135 C p.
artikel
57 Theoretical comparative study of t tests and nonparametric tests for final status surveys of MARSSIM at decommissioning sites Sohn, Wook
2020
135 C p.
artikel
58 The technology of micro heat pipe cooled reactor: A review Yan, B.H.
2020
135 C p.
artikel
59 Validation of ENDF/B-VIII thermal neutron scattering data of heavy water by differential cross section measurements at various temperatures Li, G.
2020
135 C p.
artikel
60 Validation of the BERKUT fuel rod module against mixed nitride fuel experimental data Veprev, D.P.
2020
135 C p.
artikel
61 Variable coefficient depletion equations – Reference solution based on Rational Approximation Methods Huang, Kai
2020
135 C p.
artikel
62 3-Way coupled thermohydraulic-discrete element-neutronic simulation of solid fuel, molten salt reactor Mardus-Hall, Robert
2020
135 C p.
artikel
                             62 gevonden resultaten
 
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