Digitale Bibliotheek
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                             74 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Acceleration of within group iteration for pin-by-pin calculations Zhang, Tengfei
2018
112 C p. 225-235
artikel
2 A comparison of curium, neptunium and americium transmutation feasibility Kooyman, Timothée
2018
112 C p. 748-758
artikel
3 A conceptual design for a generic heavy water research reactor to a more proliferation-resistant reactor Mansourzadeh, Fatemeh
2018
112 C p. 418-430
artikel
4 Adequacy of effective diameter in predicting pressure gradients of air flow through packed beds with particle size distribution Park, Jin Ho
2018
112 C p. 769-778
artikel
5 A methodology to investigate the effect of vertical seismic acceleration on the qualitative dynamic behaviors of a natural circulation loop with parallel nuclear-coupled boiling channels Lee, Jin Der
2018
112 C p. 289-306
artikel
6 Analysis for crack growth regularities in the nozzle-cylinder intersection area of Reactor Pressure Vessel Liu, Ran
2018
112 C p. 779-793
artikel
7 Analysis of flow blockage accidents in rectangular fuel assembly based on CFD methodology Ma, Zhenhui
2018
112 C p. 71-83
artikel
8 An analysis of condensation errors in multi-group cross section generation for fine-mesh neutron transport calculations Boyd, William
2018
112 C p. 267-276
artikel
9 An experimental investigation on flow-regime characteristics in debris bed formation behavior using gas-injection Cheng, Songbai
2018
112 C p. 856-868
artikel
10 An experimental study on the depressurization of the containment by water spray in a small scale facility Jain, Manish
2018
112 C p. 208-224
artikel
11 Application of artificial rare earth compound (RE2O3) based neutron absorber in a PWR spent fuel cask Kim, Kyung-O
2018
112 C p. 640-645
artikel
12 Application of Tone’s and embedded self-shielding methods to pressurized water reactor assemblies Hébert, A.
2018
112 C p. 439-449
artikel
13 ARRC: A random ray neutron transport code for nuclear reactor simulation Tramm, John R.
2018
112 C p. 693-714
artikel
14 Assessment of RELAP5/MOD3.2 for startup transients in a natural circulation test facility Shi, Shanbin
2018
112 C p. 257-266
artikel
15 A survey of the state of condition-based maintenance (CBM) in the nuclear power industry Ayo-Imoru, R.M.
2018
112 C p. 177-188
artikel
16 Chaos in eigenvalue search methods Mancusi, Davide
2018
112 C p. 354-363
artikel
17 Computational validation of the fission rate distribution experimental benchmark at the JSI TRIGA Mark II research reactor using the Monte Carlo method Štancar, Žiga
2018
112 C p. 94-108
artikel
18 Cumulative migration method for computing rigorous diffusion coefficients and transport cross sections from Monte Carlo Liu, Zhaoyuan
2018
112 C p. 507-516
artikel
19 DACOS: DAKOTA-AGENT neutronics computational optimization system Schow, Ryan
2018
112 C p. 245-256
artikel
20 Dependence assessment in human reliability analysis based on evidence credibility decay model and IOWA operator Zheng, Xianglin
2018
112 C p. 673-684
artikel
21 Development and validation of the new coupled code system TRADYN Gonzalez-Vargas, Jose Angel
2018
112 C p. 685-692
artikel
22 Development of a quantitative method for evaluating the efficacy of cyber security controls in NPPs based on intrusion tolerant concept Lee, Chanyoung
2018
112 C p. 646-654
artikel
23 Dynamic response of generation III+ integral nuclear island structure considering fluid structure interaction effects Zhao, Chunfeng
2018
112 C p. 189-207
artikel
24 Dynamics and thermal analysis of the auxiliary bearing for the helium circulator of HTR-PM Zhao, Yulan
2018
112 C p. 474-485
artikel
25 Editorial board 2018
112 C p. IFC
artikel
26 Effect of axial power distribution on flow instability in parallel channels with water at supercritical pressures Shitsi, Edward
2018
112 C p. 109-119
artikel
27 Eigenvalue sensitivity analysis capabilities with the differential operator method in the superhistory Monte Carlo method Yamamoto, Toshihiro
2018
112 C p. 150-157
artikel
28 Estimation of appendage pressure-loss coefficients for fuel rod bundles using computational fluid dynamics Podila, K.
2018
112 C p. 597-602
artikel
29 Estimation of the poisons reactivity in the P.W.R Nuclear Reactors using modified higher order sliding mode observer based on the multi-point nuclear reactor model Zahedi yeganeh, M.H.
2018
112 C p. 158-169
artikel
30 Experimental study on heat-removal performance in accordance with mesh size of screen installed at opening of inlets and outlets of concrete storage cask Seo, Ki-Seog
2018
112 C p. 322-327
artikel
31 Flow resistances characteristics in a particulate bed with the configurations of uniform mixture and stratification Li, Liangxing
2018
112 C p. 62-70
artikel
32 Fuel cycle analysis of Advanced Burner Reactor with breed-and-burn thorium blanket Zhang, Guanheng
2018
112 C p. 383-394
artikel
33 Generalized equivalence methods for 3D multi-group neutron transport Giudicelli, Guillaume
2018
112 C p. 9-16
artikel
34 Generation of the windowed multipole resonance data using Vector Fitting technique Liu, Shichang
2018
112 C p. 30-41
artikel
35 How inelastic scattering stimulates nonlinear reactor core parameter behaviour Rochman, D.
2018
112 C p. 236-244
artikel
36 Improving prompt temperature feedback by stimulating Doppler broadening in heterogeneous composite nuclear fuel forms Morrison, Christopher G.
2018
112 C p. 486-506
artikel
37 Integral formulation and numerical simulations for the neutron transport equation in X-Y geometry de Azevedo, F.S.
2018
112 C p. 735-747
artikel
38 Integrated model development for safeguarding pyroprocessing facility: Part II – Case studies and model integration Zhou, Wentao
2018
112 C p. 48-61
artikel
39 Integrated model development for safeguarding pyroprocessing facility: Part I-model development and validation Zhou, Wentao
2018
112 C p. 603-614
artikel
40 Intelligent intrusion detection system featuring a virtual fence, active intruder detection, classification, tracking, and action recognition Kim, Seung Hyun
2018
112 C p. 845-855
artikel
41 Investigation of uncertainty caused by random arrangement of coated fuel particles in HTTR criticality calculations Ho, Hai Quan
2018
112 C p. 42-47
artikel
42 Investigation on response of HPR1000 under different mitigation strategies after SGTR accident Sui, Danting
2018
112 C p. 328-336
artikel
43 Kinetics solution with iteration scheme of history-based neutron source in accelerator driven system Kim, Song Hyun
2018
112 C p. 337-353
artikel
44 Measurement of various monitors reaction rate in a special core at LR-0 reactor Košt’ál, Michal
2018
112 C p. 759-768
artikel
45 MELCOR modeling and sensitivity analysis of Fukushima Daiichi unit 2 accident considering the latest TEPCO investigations Li, Gen
2018
112 C p. 364-373
artikel
46 Micrometer-sized droplet impingement dynamics on flat and micro-structured surfaces Zhang, Zhen
2018
112 C p. 464-473
artikel
47 Mixing of hot and cold fluid inside a square chimney model for a pool type research reactor – An experimental study Sengupta, Samiran
2018
112 C p. 829-844
artikel
48 Modelling of pool stratification and mixing induced by steam injection through blowdown pipes Gallego-Marcos, Ignacio
2018
112 C p. 624-639
artikel
49 Neutronic study of a combined fast fission FFHR and thermal fission FFHR system using thorium bearing molten salt fuel Xiao, S.C.
2018
112 C p. 666-672
artikel
50 Neutron noise observations in German KWU built PWRs and analyses with the reactor dynamics code DYN3D Rohde, Ulrich
2018
112 C p. 715-734
artikel
51 Newton-Krylov method in solving drift-flux two-phase flow problems for both pre-CHF and post-CHF conditions at steady state Zou, Ling
2018
112 C p. 517-530
artikel
52 Numerical simulation of the nuclear reactors kinetics behavior using method of lines based on the GDQ method Ansarifar, G.R.
2018
112 C p. 808-828
artikel
53 Numerical simulations of molten salt pebble-bed lattices Dave, A.J.
2018
112 C p. 400-410
artikel
54 Optimization of minor actinides bearing blankets with industrial fuel cycle constraints Kooyman, Timothée
2018
112 C p. 615-623
artikel
55 Parametric effects on coupled neutronic-thermohydraulic stability characteristics of supercritical water cooled reactor Shankar, Daya
2018
112 C p. 120-131
artikel
56 Photon and neutron shielding features of quarry tuff Vega-Carrillo, Hector Rene
2018
112 C p. 411-417
artikel
57 Predicting correlation coefficients for Monte Carlo eigenvalue simulations with multitype branching process Miao, Jilang
2018
112 C p. 307-321
artikel
58 Prediction of performance of Safety Injection Tank with Fluidic Device using a model of two flow paths and its effect on LBLOCA Bang, Young Seok
2018
112 C p. 143-149
artikel
59 Progress in modeling in-containment source term with ASTEC-Na Herranz, L.E.
2018
112 C p. 84-93
artikel
60 Quantification of condensation model uncertainty based on large scale PCS test SCOPE Wang, Zhangli
2018
112 C p. 869-875
artikel
61 Quenching of candidate materials for accident tolerant fuel-cladding in LWRs Kang, Jun-young
2018
112 C p. 794-807
artikel
62 Rapid radionuclide identification algorithm based on the discrete cosine transform and BP neural network He, Jianping
2018
112 C p. 1-8
artikel
63 Reconstruction of radiation dose rate profiles by autonomous robot with active learning and Gaussian process regression Silveira, Paulo R.
2018
112 C p. 876-886
artikel
64 Research on fault diagnosis methods for the reactor coolant system of nuclear power plant based on D-S evidence theory Gong, Yongjian
2018
112 C p. 395-399
artikel
65 Resonance self-shielding treatment and analysis of resonance integral tables for Fully Ceramic Micro-encapsulated fuels with the Embedded Self-Shielding Method Li, Jikui
2018
112 C p. 450-463
artikel
66 Scaling of thermal stratification or mixing in outlet plena of SFRs Ward, Brendan
2018
112 C p. 431-438
artikel
67 Study of in-containment source term behavior for VVER-1000 under LOCA conditions using the IRBURN code system Jafarikia, S.
2018
112 C p. 17-29
artikel
68 Study on variance reduction technique based on adjoint Discrete Ordinate method Zheng, Zheng
2018
112 C p. 374-382
artikel
69 The core instability analysis under ocean condition for offshore floating nuclear power plant with neutron coupling based on multi-point model Hu, Miao
2018
112 C p. 170-176
artikel
70 Thermal and fluid analysis of dry cask storage containers over multiple years of service Wu, Yongjia
2018
112 C p. 132-142
artikel
71 The shaking table experiments on sliding and overturning of CAP1400 spent fuel storage rack with the effect of FSI Liu, Yu
2018
112 C p. 277-288
artikel
72 The study of the mitigation strategy of Lungmen ABWR nuclear power plant using RELAP5 and FRAPTRAN with the interface SNAP Li, Wan-Yun
2018
112 C p. 655-665
artikel
73 The “virtual density” theory of neutronics Reed, Mark
2018
112 C p. 549-596
artikel
74 “Virtual density” and traditional boundary perturbation theories: Analytic equivalence and numeric comparison Reed, Mark
2018
112 C p. 531-548
artikel
                             74 gevonden resultaten
 
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