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                             74 results found
no title author magazine year volume issue page(s) type
1 Acceleration of within group iteration for pin-by-pin calculations Zhang, Tengfei
 2018
 112 C p. 225-235
 article
2 A comparison of curium, neptunium and americium transmutation feasibility Kooyman, Timothée
 2018
 112 C p. 748-758
 article
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
 article
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
 article
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
 article
6 Analysis for crack growth regularities in the nozzle-cylinder intersection area of Reactor Pressure Vessel Liu, Ran
 2018
 112 C p. 779-793
 article
7 Analysis of flow blockage accidents in rectangular fuel assembly based on CFD methodology Ma, Zhenhui
 2018
 112 C p. 71-83
 article
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
 article
9 An experimental investigation on flow-regime characteristics in debris bed formation behavior using gas-injection Cheng, Songbai
 2018
 112 C p. 856-868
 article
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
 article
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
 article
12 Application of Tone’s and embedded self-shielding methods to pressurized water reactor assemblies Hébert, A.
 2018
 112 C p. 439-449
 article
13 ARRC: A random ray neutron transport code for nuclear reactor simulation Tramm, John R.
 2018
 112 C p. 693-714
 article
14 Assessment of RELAP5/MOD3.2 for startup transients in a natural circulation test facility Shi, Shanbin
 2018
 112 C p. 257-266
 article
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
 article
16 Chaos in eigenvalue search methods Mancusi, Davide
 2018
 112 C p. 354-363
 article
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
 article
18 Cumulative migration method for computing rigorous diffusion coefficients and transport cross sections from Monte Carlo Liu, Zhaoyuan
 2018
 112 C p. 507-516
 article
19 DACOS: DAKOTA-AGENT neutronics computational optimization system Schow, Ryan
 2018
 112 C p. 245-256
 article
20 Dependence assessment in human reliability analysis based on evidence credibility decay model and IOWA operator Zheng, Xianglin
 2018
 112 C p. 673-684
 article
21 Development and validation of the new coupled code system TRADYN Gonzalez-Vargas, Jose Angel
 2018
 112 C p. 685-692
 article
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
 article
23 Dynamic response of generation III+ integral nuclear island structure considering fluid structure interaction effects Zhao, Chunfeng
 2018
 112 C p. 189-207
 article
24 Dynamics and thermal analysis of the auxiliary bearing for the helium circulator of HTR-PM Zhao, Yulan
 2018
 112 C p. 474-485
 article
25 Editorial board 2018
 112 C p. IFC
 article
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
 article
27 Eigenvalue sensitivity analysis capabilities with the differential operator method in the superhistory Monte Carlo method Yamamoto, Toshihiro
 2018
 112 C p. 150-157
 article
28 Estimation of appendage pressure-loss coefficients for fuel rod bundles using computational fluid dynamics Podila, K.
 2018
 112 C p. 597-602
 article
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
 article
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
 article
31 Flow resistances characteristics in a particulate bed with the configurations of uniform mixture and stratification Li, Liangxing
 2018
 112 C p. 62-70
 article
32 Fuel cycle analysis of Advanced Burner Reactor with breed-and-burn thorium blanket Zhang, Guanheng
 2018
 112 C p. 383-394
 article
33 Generalized equivalence methods for 3D multi-group neutron transport Giudicelli, Guillaume
 2018
 112 C p. 9-16
 article
34 Generation of the windowed multipole resonance data using Vector Fitting technique Liu, Shichang
 2018
 112 C p. 30-41
 article
35 How inelastic scattering stimulates nonlinear reactor core parameter behaviour Rochman, D.
 2018
 112 C p. 236-244
 article
36 Improving prompt temperature feedback by stimulating Doppler broadening in heterogeneous composite nuclear fuel forms Morrison, Christopher G.
 2018
 112 C p. 486-506
 article
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
 article
38 Integrated model development for safeguarding pyroprocessing facility: Part II – Case studies and model integration Zhou, Wentao
 2018
 112 C p. 48-61
 article
39 Integrated model development for safeguarding pyroprocessing facility: Part I-model development and validation Zhou, Wentao
 2018
 112 C p. 603-614
 article
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
 article
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
 article
42 Investigation on response of HPR1000 under different mitigation strategies after SGTR accident Sui, Danting
 2018
 112 C p. 328-336
 article
43 Kinetics solution with iteration scheme of history-based neutron source in accelerator driven system Kim, Song Hyun
 2018
 112 C p. 337-353
 article
44 Measurement of various monitors reaction rate in a special core at LR-0 reactor Košt’ál, Michal
 2018
 112 C p. 759-768
 article
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
 article
46 Micrometer-sized droplet impingement dynamics on flat and micro-structured surfaces Zhang, Zhen
 2018
 112 C p. 464-473
 article
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
 article
48 Modelling of pool stratification and mixing induced by steam injection through blowdown pipes Gallego-Marcos, Ignacio
 2018
 112 C p. 624-639
 article
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
 article
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
 article
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
 article
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
 article
53 Numerical simulations of molten salt pebble-bed lattices Dave, A.J.
 2018
 112 C p. 400-410
 article
54 Optimization of minor actinides bearing blankets with industrial fuel cycle constraints Kooyman, Timothée
 2018
 112 C p. 615-623
 article
55 Parametric effects on coupled neutronic-thermohydraulic stability characteristics of supercritical water cooled reactor Shankar, Daya
 2018
 112 C p. 120-131
 article
56 Photon and neutron shielding features of quarry tuff Vega-Carrillo, Hector Rene
 2018
 112 C p. 411-417
 article
57 Predicting correlation coefficients for Monte Carlo eigenvalue simulations with multitype branching process Miao, Jilang
 2018
 112 C p. 307-321
 article
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
 article
59 Progress in modeling in-containment source term with ASTEC-Na Herranz, L.E.
 2018
 112 C p. 84-93
 article
60 Quantification of condensation model uncertainty based on large scale PCS test SCOPE Wang, Zhangli
 2018
 112 C p. 869-875
 article
61 Quenching of candidate materials for accident tolerant fuel-cladding in LWRs Kang, Jun-young
 2018
 112 C p. 794-807
 article
62 Rapid radionuclide identification algorithm based on the discrete cosine transform and BP neural network He, Jianping
 2018
 112 C p. 1-8
 article
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
 article
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
 article
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
 article
66 Scaling of thermal stratification or mixing in outlet plena of SFRs Ward, Brendan
 2018
 112 C p. 431-438
 article
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
 article
68 Study on variance reduction technique based on adjoint Discrete Ordinate method Zheng, Zheng
 2018
 112 C p. 374-382
 article
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
 article
70 Thermal and fluid analysis of dry cask storage containers over multiple years of service Wu, Yongjia
 2018
 112 C p. 132-142
 article
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
 article
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
 article
73 The “virtual density” theory of neutronics Reed, Mark
 2018
 112 C p. 549-596
 article
74 “Virtual density” and traditional boundary perturbation theories: Analytic equivalence and numeric comparison Reed, Mark
 2018
 112 C p. 531-548
 article
                             74 results found
 
 Koninklijke Bibliotheek - National Library of the Netherlands