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                             56 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Actinide inventory in Herndon’s georeactor operating throughout geologic time Lin, Kao-Ping
2015
77 C p. 361-368
artikel
2 Algorithmic choices in WARP – A framework for continuous energy Monte Carlo neutron transport in general 3D geometries on GPUs Bergmann, Ryan M.
2015
77 C p. 176-193
artikel
3 Analysis of accidental loss of pool coolant due to leakage in a PWR SFP Wu, Xiaoli
2015
77 C p. 65-73
artikel
4 Analysis of the THAI Iod-11 and Iod-12 tests: Advancements and limitations of ASTEC V2.0R3p1 and MELCOR V2.1.4803 Gonfiotti, Bruno
2015
77 C p. 451-476
artikel
5 A neutronic feasibility study on a small LEU fueled reactor for space applications Lee, Hyun Chul
2015
77 C p. 35-46
artikel
6 A novel research reactor concept based on coated particle fuel Hidayatullah, Rully
2015
77 C p. 477-486
artikel
7 A nuclear-natural gas coupled-cycle for power generation Tian, Jiafu
2015
77 C p. 281-284
artikel
8 Application of multivariate analysis techniques to safeguards of the electrochemical treatment of used nuclear fuel Rappleye, Devin
2015
77 C p. 265-272
artikel
9 A sipping test simulator for identifying defective fuels in MTR type nuclear research reactor Jafari, M.
2015
77 C p. 238-245
artikel
10 Assessment of long-term trend for environmental radioactivity around Wolsong nuclear power plant in Korea Yang, Yang-Hee
2015
77 C p. 231-237
artikel
11 Assessment of RVACS performance for small size lead-cooled fast reactor Wu, Guowei
2015
77 C p. 310-317
artikel
12 Benchmark of Neutronics and Thermal-hydraulics Coupled Simulation program NTC on beam interruptions in XADS Wang, Zhen
2015
77 C p. 172-175
artikel
13 CFD investigation of effect of helical wire-wrap parameters on the thermal hydraulic performance of 217 fuel pin bundle Gajapathy, R.
2015
77 C p. 498-513
artikel
14 CFD model of diabatic annular two-phase flow using the Eulerian–Lagrangian approach Li, Haipeng
2015
77 C p. 415-424
artikel
15 Comparative validation of Monte Carlo codes for the conversion of a research reactor Alferov, V.P.
2015
77 C p. 273-280
artikel
16 Comparison of nuclear data uncertainty propagation methodologies for PWR burn-up simulations Díez, C.J.
2015
77 C p. 101-114
artikel
17 Constrained non-collinear magnetism in disordered Fe and Fe–Cr alloys Nguyen-Manh, D.
2015
77 C p. 246-251
artikel
18 Control of xenon oscillations in Advanced Heavy Water Reactor via two-stage decomposition Munje, R.K.
2015
77 C p. 326-334
artikel
19 Correlation analysis for screening key parameters for passive system reliability analysis Yu, Yu
2015
77 C p. 23-29
artikel
20 Derivation of the Green’s function of the linear transport equation from the discrete-ordinate solution Coppa, Gianni
2015
77 C p. 252-256
artikel
21 Design of an MCNPX model to simulate the performance of BWRs using thorium as fuel and its validation with HELIOS code Abdelghafar Galahom, A.
2015
77 C p. 393-401
artikel
22 Development of an iterative diffusion-transport method based on MICROX-2 cross section libraries Hou, J.
2015
77 C p. 335-342
artikel
23 Development of a sub-channel code for liquid metal cooled fuel assembly Liu, X.J.
2015
77 C p. 425-435
artikel
24 DRACS thermal performance evaluation for FHR Lv, Q.
2015
77 C p. 115-128
artikel
25 Editorial board 2015
77 C p. IFC
artikel
26 Estimation of the xenon concentration and delayed neutrons precursors densities in the pressurized-water nuclear reactors (PWR) with sliding mode observer considering xenon oscillations Esteki, M.H.
2015
77 C p. 1-22
artikel
27 Heat transfer in a cooling water pool with tube bundles under natural circulation Chung, Young-Jong
2015
77 C p. 402-407
artikel
28 Improved S2 approximations Safari, Mohammad Javad
2015
77 C p. 257-264
artikel
29 Influencing factors research on CHF at low pressure, low flow conditions in narrow channel based on Rough Set Decision Model Zhou, Tao
2015
77 C p. 161-164
artikel
30 Investigation of fuel lattice pitch changes influence on reactor performance through evaluate the neutronic parameters Zareian Ronizi, F.
2015
77 C p. 343-350
artikel
31 Large LOCA accident analysis for AP1000 under earthquake Yu, Yu
2015
77 C p. 142-147
artikel
32 Minor actinide transmutation on PWR burnable poison rods Hu, Wenchao
2015
77 C p. 74-82
artikel
33 MOCABA: A general Monte Carlo–Bayes procedure for improved predictions of integral functions of nuclear data Hoefer, A.
2015
77 C p. 514-521
artikel
34 Modeling of realistic pebble bed reactor geometries using the Serpent Monte Carlo code Rintala, Ville
2015
77 C p. 223-230
artikel
35 Multi-group SP3 approximation for simulation of a three-dimensional PWR rod ejection accident Lee, Deokjung
2015
77 C p. 94-100
artikel
36 Neural network of Gaussian radial basis functions applied to the problem of identification of nuclear accidents in a PWR nuclear power plant Gomes, Carla Regina
2015
77 C p. 285-293
artikel
37 Neutron energy spectrum in a reactor exit channel with a single surface barrier sensor using GEANT4 Dehimi, F.Z.
2015
77 C p. 369-375
artikel
38 New analytic function expansion nodal (AFEN) method for solving multigroup neutron simplified P3 (SP3) equations Jalili Bahabadi, Mohammad Hasan
2015
77 C p. 148-160
artikel
39 New reactor cavity cooling system having passive safety features using novel shape for HTGRs and VHTRs Takamatsu, Kuniyoshi
2015
77 C p. 165-171
artikel
40 Numerical analysis on molten droplet hydrodynamic deformation and surface waves under high pressure pulse Lin, Meng
2015
77 C p. 133-141
artikel
41 Numerical modeling of a horizontal annular flow experiment using a droplet entrainment model Höhne, Thomas
2015
77 C p. 351-360
artikel
42 Numerical simulation of the transient behaviors in an open natural circulation system with a large scale Guo, Xueqing
2015
77 C p. 83-93
artikel
43 Power calculation of VVER-1000 reactor using a thermal method, applied to primary–secondary circuits Jabbari, M.
2015
77 C p. 129-132
artikel
44 Preliminary transient analysis of the Autonomous Reactivity Control system for fast reactors Suvdantsetseg, E.
2015
77 C p. 47-64
artikel
45 Quantitative assessment of probability of failing safely for the safety instrumented system using reliability block diagram method Jin, Jianghong
2015
77 C p. 30-34
artikel
46 Re-evaluation of the EURACOS integral shielding experiment series Žerovnik, Gašper
2015
77 C p. 318-325
artikel
47 SAS4A analysis on hypothetical total instantaneous flow blockage in SFRs based on in-pile experiments Fukano, Yoshitaka
2015
77 C p. 376-392
artikel
48 Solution of neutron transport equation by Method of Characteristics Mazumdar, Tanay
2015
77 C p. 522-535
artikel
49 Spatial homogenization method based on the inverse problem Tóta, Ádám
2015
77 C p. 436-443
artikel
50 The characterization of cement waste form for final disposal of decommissioning concrete wastes Lee, Yoon-ji
2015
77 C p. 294-299
artikel
51 The influence of the neutron source spectrum on the infinite homogeneous reactor in subcritical condition Dall’Osso, Aldo
2015
77 C p. 408-414
artikel
52 Theoretical analysis of recirculation zone and buffer zone in the ADS windowless spallation target Liu, Jie
2015
77 C p. 444-450
artikel
53 Theory and analysis of accuracy for the method of characteristics direction probabilities with boundary averaging Liu, Zhouyu
2015
77 C p. 212-222
artikel
54 Validating THERP: Assessing the scope of a full-scale validation of the Technique for Human Error Rate Prediction Shirley, Rachel Benish
2015
77 C p. 194-211
artikel
55 Verification of the new implementations in SHARKX against TSUNAMI to perform pinpower UQ and representativity analysis Hursin, Mathieu
2015
77 C p. 300-309
artikel
56 Visualization experiments on the geyser boiling-induced instability in vertical circular tube at low-pressures Tong, Lili
2015
77 C p. 487-497
artikel
                             56 gevonden resultaten
 
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