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                             76 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Adsorption and immobilization of actinides using novel SiO2–ZrO2-calcium alginate aerogels from high level liquid waste Zhao, Junchuan
 2015
 85 C p. 713-718
6 p.
 artikel
2 Analysis of the radiological contamination of the RBMK-1500 reactor low salted water system Poskas, G.
 2015
 85 C p. 707-712
6 p.
 artikel
3 A numerical assessment of copper oxide and alumina nanoparticles during CHF occurrence Rabiee, Ataollah
 2015
 85 C p. 121-129
9 p.
 artikel
4 Application of CNUREAS and MCNP5 codes to VVER-1000 MOX Core Computational Benchmark Şentürk Lüle, Senem
 2015
 85 C p. 454-461
8 p.
 artikel
5 A thermal model to characterize the flattening effect of a nuclear fuel element in an annular channel using simple analytical approach Poddar, Antarip
 2015
 85 C p. 441-453
13 p.
 artikel
6 BDD algorithms based on modularization for fault tree analysis Deng, Yunli
 2015
 85 C p. 192-199
8 p.
 artikel
7 Breed-and-burn strategy in a fast reactor with optimized starter fuel Huang, Jinfeng
 2015
 85 C p. 11-16
6 p.
 artikel
8 CFD based approach for modeling steam–water direct contact condensation in subcooled water flow in a tee junction Li, S.Q.
 2015
 85 C p. 729-746
18 p.
 artikel
9 CFD study of an air–water flow inside helically coiled pipes Colombo, Marco
 2015
 85 C p. 462-472
11 p.
 artikel
10 Comparative study for modeling reactor internal geometry in CFD simulation of PWR and PHWR internal flow – Nuclear regulatory perspective Lee, Gong Hee
 2015
 85 C p. 588-599
12 p.
 artikel
11 Computation of fundamental time-eigenvalue of the neutron transport equation Shen, Huayun
 2015
 85 C p. 624-630
7 p.
 artikel
12 Control simulation and study of load rejection transient for AP1000 Wang, Pengfei
 2015
 85 C p. 28-43
16 p.
 artikel
13 Development and verification of molten corium–concrete interaction code Lin, Bo
 2015
 85 C p. 701-706
6 p.
 artikel
14 Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000 Mao, Keyou
 2015
 85 C p. 352-365
14 p.
 artikel
15 Development of DETAC and its application to the hydrogen detonation analysis Huang, Tao
 2015
 85 C p. 228-238
11 p.
 artikel
16 Development of the ALFRED reactor full power mode control system Ponciroli, Roberto
 2015
 85 C p. 428-440
13 p.
 artikel
17 Does it really make sense to use fission gas plenums in a lead-bismuth-cooled fast reactor? Arias, Francisco J.
 2015
 85 C p. 491-497
7 p.
 artikel
18 Editorial Board 2015
 85 C p. IFC-
1 p.
 artikel
19 Effect of high density dispersion fuels on transient behavior of MTR type research reactor under multiple reactivity transients Nasir, Rubina
 2015
 85 C p. 511-517
7 p.
 artikel
20 Estimation of relative power distribution and power peaking factor in a VVER-1000 reactor core using artificial neural networks Pirouzmand, Ahmad
 2015
 85 C p. 17-27
11 p.
 artikel
21 Evaluation of contribution of thermal radiation in transferring decay heat to the moderator, in case of 18 rod bundle facility, simulating advanced nuclear reactors Bopche, Santosh B.
 2015
 85 C p. 83-95
13 p.
 artikel
22 Experimental investigation of natural circulation instability in a BWR-type small modular reactor Shi, Shanbin
 2015
 85 C p. 96-107
12 p.
 artikel
23 Experimental research on aerosols collection performance of self-priming venturi scrubber in FCVS Zhou, Yanmin
 2015
 85 C p. 771-777
7 p.
 artikel
24 Experimental study on the adsorption and desorption of tritium in the graphite materials for HTR-PM Li, Hong
 2015
 85 C p. 676-681
6 p.
 artikel
25 Galerkin and Generalized Least Squares finite element: A comparative study for multi-group diffusion solvers Hosseini, Seyed Abolfazl
 2015
 85 C p. 473-490
18 p.
 artikel
26 Gas-cooled reactor thermal hydraulic analyses with MELCOR Beeny, Bradley
 2015
 85 C p. 404-414
11 p.
 artikel
27 Heavy Water Zero Power Reactor (HWZPR) mixed core first criticality, calculation and experiments Khorsandi, J.
 2015
 85 C p. 613-616
4 p.
 artikel
28 Hydrodynamic and mass transfer studies of 125 mm centrifugal extractor with 30% TBP/nitric acid system Mandal, Kinkar
 2015
 85 C p. 1-10
10 p.
 artikel
29 Improvement of a calculation procedure of neutron-flux distribution for radioactivity inventory estimation for decommissioning of nuclear power plants Tanaka, Ken-ichi
 2015
 85 C p. 254-270
17 p.
 artikel
30 Independent fission yields studied based on Langevin equation Aritomo, Yoshihiro
 2015
 85 C p. 568-572
5 p.
 artikel
31 Investigation of gamma radiation shielding properties of various ores Oto, Berna
 2015
 85 C p. 391-403
13 p.
 artikel
32 Large eddy simulation of rough and smooth liquid plunging jet processes Khezzar, Lyes
 2015
 85 C p. 140-155
16 p.
 artikel
33 Method of characteristics – A review with applications to science and nuclear engineering computation Eklund, Matthew
 2015
 85 C p. 548-567
20 p.
 artikel
34 Molecular dynamics calculations of heat conduction in actinide oxides under thermal gradient Matsumoto, Taku
 2015
 85 C p. 271-276
6 p.
 artikel
35 Numerical investigation of high level nuclear waste disposal in deep anisotropic geologic repositories Salama, Amgad
 2015
 85 C p. 747-755
9 p.
 artikel
36 Numerical investigation of the CANDU moderator thermal-hydraulics using the CUPID code Choi, Su Ryong
 2015
 85 C p. 541-547
7 p.
 artikel
37 Numerical simulation on single bubble behavior during Al2O3/H2O nanofluids flow boiling using Moving Particle Simi-implicit method Wang, Yun
 2015
 85 C p. 130-139
10 p.
 artikel
38 Numerical treatment for the point reactor kinetics equations using theta method, eigenvalues and eigenvectors Nahla, Abdallah A.
 2015
 85 C p. 756-763
8 p.
 artikel
39 Optimization of neutron energy-group structure in thermal lattices using ultrafine bilinear adjoint function Fallah, Vahid Farhang
 2015
 85 C p. 648-658
11 p.
 artikel
40 Partitioned-Matrix acceleration to the Fission-Source iteration of the Variational Nodal Method Li, Yunzhao
 2015
 85 C p. 640-647
8 p.
 artikel
41 Plutonium fingerprinting in nuclear forensics of spent nuclear fuel Lantzos, I.
 2015
 85 C p. 333-336
4 p.
 artikel
42 Potential application of a nanocomposite:HCNFe@polymer for effective removal of Cs (I) from nuclear waste Yousefi, Taher
 2015
 85 C p. 631-639
9 p.
 artikel
43 Prediction of MgO volume fraction in an ADS fresh fuel for the scenario code CLASS Thiollière, N.
 2015
 85 C p. 518-524
7 p.
 artikel
44 Preliminary simulation of fuel dispersion in a Lead-Bismuth Eutectic (LBE)-cooled research reactor Wang, Zhen
 2015
 85 C p. 337-343
7 p.
 artikel
45 Radionuclide transport in shallow groundwater Testoni, Raffaella
 2015
 85 C p. 277-290
14 p.
 artikel
46 Review of the historic neutron noise behavior in German KWU built PWRs Seidl, Marcus
 2015
 85 C p. 668-675
8 p.
 artikel
47 Rheological characterization of buffered boric acid aqueous solutions in light water reactors Hassan, Yassin A.
 2015
 85 C p. 239-253
15 p.
 artikel
48 Safety analysis of reactivity insertion accidents in a heavy water nuclear research reactor core using coupled 3D neutron kinetics thermal-hydraulic system code technique Titouche Kouidri, W.
 2015
 85 C p. 384-390
7 p.
 artikel
49 Searching for enrichment and gadolinia distributions in BWR fuel lattices through a Heuristic-Knowledge Method Montes-Tadeo, José-Luis
 2015
 85 C p. 213-227
15 p.
 artikel
50 Self-induced electrostatic-boosted radioisotope heat sources Arias, Francisco J.
 2015
 85 C p. 291-296
6 p.
 artikel
51 SLIMM-Scalable LIquid Metal cooled small Modular Reactor: Preliminary design and performance analyses El-Genk, Mohamed S.
 2015
 85 C p. 56-70
15 p.
 artikel
52 Slug flow in a vertical narrow rectangular channel – Laminar and turbulent regimes in the main flow and turbulent regime in the wake region of the Taylor bubble Wang, Yang
 2015
 85 C p. 164-177
14 p.
 artikel
53 Solution of PHWR 3D kinetics benchmark using TRIKIN code Kumar, Rakesh
 2015
 85 C p. 200-212
13 p.
 artikel
54 Spent fuel interrogation using delayed fast neutron spectrum at Missouri University of Science and Technology Reactor Akyurek, T.
 2015
 85 C p. 525-540
16 p.
 artikel
55 Startup and burnup strategy for Th–U/U–Pu fuel cycles in an EM2 reactor Ma, Y.W.
 2015
 85 C p. 764-770
7 p.
 artikel
56 Steady and transient solutions of neutronics problems based on finite volume method (FVM) with a CFD code Ge, Jian
 2015
 85 C p. 366-374
9 p.
 artikel
57 Strategy evaluation for fire spray system on Advanced Passive PWR Severe Accident Management Guideline Li, Y.B.
 2015
 85 C p. 319-324
6 p.
 artikel
58 Strength assessment of SMART design against anticipated transient without scram Chung, Young-Jong
 2015
 85 C p. 617-623
7 p.
 artikel
59 Synthesis and characterization of ultra-fine well-dispersed thoria nano spheres through reduction reactions in nitrate bath Yousefi, Taher
 2015
 85 C p. 600-604
5 p.
 artikel
60 System assessment of an FPGA-based RPS for ABWR nuclear power plant Lu, Jun-Jen
 2015
 85 C p. 44-55
12 p.
 artikel
61 Technetium transmutation in thin layer coating on PWR fuel rods Liu, Bin
 2015
 85 C p. 375-383
9 p.
 artikel
62 Testing actinide fission yield treatment in CINDER90 for use in MCNP6 burnup calculations Fensin, Michael Lorne
 2015
 85 C p. 719-728
10 p.
 artikel
63 The design and utilization of a high-temperature helium loop and other facilities for the study of advanced gas-cooled reactors in the Czech Republic Berka, Jan
 2015
 85 C p. 156-163
8 p.
 artikel
64 The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe – Part I: Uranium fuel cycle Lindley, Benjamin A.
 2015
 85 C p. 498-510
13 p.
 artikel
65 The influence of ocean conditions on thermal-hydraulic characteristics of a passive residual heat removal system Xi, Mengmeng
 2015
 85 C p. 573-587
15 p.
 artikel
66 Thermal and stress analysis of window target for accelerator-driven sub-critical system during beam trip transients Jin, Ming
 2015
 85 C p. 325-332
8 p.
 artikel
67 Thermal-hydraulic analysis of EBR-II Shutdown Heat Removal Tests SHRT-17 and SHRT-45R Yue, Nina
 2015
 85 C p. 682-693
12 p.
 artikel
68 Thermal-hydraulics analysis during fuel element failure in an operating PWR Chen, Wenzhen
 2015
 85 C p. 694-700
7 p.
 artikel
69 Thermodynamic analysis of a solid nuclear fuel element surrounded by flow of coolant through a concentric annular channel Poddar, Antarip
 2015
 85 C p. 178-191
14 p.
 artikel
70 The use of heat balance method in the thermal power calibration of Nigeria Research Reactor-1 (NIRR-1) Agbo, S.A.
 2015
 85 C p. 344-351
8 p.
 artikel
71 The use of ionising radiation to image nuclear fuel: A review Parker, Helen M. O'D.
 2015
 85 C p. 297-318
22 p.
 artikel
72 Three-dimensional analysis of flow blockage accident in Tehran MTR research reactor core using CFD Davari, Amin
 2015
 85 C p. 605-612
8 p.
 artikel
73 TRACY and SILENE Benchmark Phase II evaluation by TRACE code Liem, Peng Hong
 2015
 85 C p. 71-82
12 p.
 artikel
74 Two group, three dimensional diffusion theory coupled with single heated channel model: A study based on xenon transient simulation of Tehran research reactor Hosseini, Mohammad
 2015
 85 C p. 108-120
13 p.
 artikel
75 Verification of Neutronics and Thermal-hydraulics Coupled Simulation Program NTC by the PDS-XADS transient simulation Wang, Gang
 2015
 85 C p. 659-667
9 p.
 artikel
76 Vertical upward two-phase flow CFD using interfacial area transport equation Chuang, Tien-Juei
 2015
 85 C p. 415-427
13 p.
 artikel
                             76 gevonden resultaten
 
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