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                             47 results found
no title author magazine year volume issue page(s) type
1 A combined immersed body and adaptive mesh method for simulating neutron transport within complex structures Buchan, A.G.
 2019
 134 C p. 88-100
 article
2 A comparison of transport methods for the solution of a problem with shadowing effects in spherical geometry Vieira, W.J.
 2019
 134 C p. 370-375
 article
3 A local fission matrix correction method for heterogeneous whole core transport with RAPID He, Donghao
 2019
 134 C p. 263-272
 article
4 Analysis of a control rod ejection accident in a boron-free small modular reactor with coupled neutronics/thermal-hydraulics code Alzaben, Y.
 2019
 134 C p. 114-124
 article
5 Analysis of the stochastic point reactor using Wiener-Hermite expansion El-Beltagy, Mohamed
 2019
 134 C p. 250-257
 article
6 Boiling water cooled travelling wave reactor Chen, X.-N.
 2019
 134 C p. 342-349
 article
7 Bubble-induced enhancement of single-phase liquid forced convection heat transfer during subcooled nucleate flow boiling Amidu, Muritala Alade
 2019
 134 C p. 60-66
 article
8 Closed loop configuration in the axial flux tilt control of a PWR Zarei, M.
 2019
 134 C p. 47-53
 article
9 Combined cycle-coupled high-temperature and very high-temperature gas-cooled reactors: Part I—Cycle optimization Yang, Xiaoyong
 2019
 134 C p. 193-204
 article
10 Comparison of deterministic and stochastic methods for external gamma dose rate calculation in the decommissioning of nuclear power plants Bednár, Dávid
 2019
 134 C p. 67-76
 article
11 Computational study of full-scale VHTR lower plenum for turbulent mixing assessment Clifford, Corey E.
 2019
 134 C p. 101-113
 article
12 Control and thermal analysis for SCWR startup Yuan, Yuan
 2019
 134 C p. 27-37
 article
13 Convergence study of variants of CMFD acceleration schemes for fixed source neutron transport problems in 2D Cartesian geometry with Fourier analysis Chan, Yimeng
 2019
 134 C p. 273-283
 article
14 Covariance-oriented sample transformation: A new sampling method for reactor-physics uncertainty analysis Sui, Zhuojie
 2019
 134 C p. 452-463
 article
15 Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark Vasiliev, A.
 2019
 134 C p. 235-243
 article
16 Design simulation studies of pipe mounted boron concentration meter Dighe, Priyamvada M.
 2019
 134 C p. 414-423
 article
17 Development of the universe based geometry criticality search capability in RMC and analysis of NHR200-II reactor Li, Zeguang
 2019
 134 C p. 401-413
 article
18 1D thermal creep channel flow in the BGK approximation by adding and doubling Ganapol, Barry D.
 2019
 134 C p. 441-451
 article
19 Editorial Board 2019
 134 C p. ii
 article
20 Effects of neutron irradiation on elastic modulus of RPV steel Li, Chengliang
 2019
 134 C p. 20-26
 article
21 Establishing safety goals on radiation protection for a space reactor through a case assessment of a loss-of-coolant accident in the International Space Station Wang, Jiaxin
 2019
 134 C p. 170-177
 article
22 Evaluation of fuzzy based HS and GSA on reloading cycle length optimization of PWR nuclear power plant Mahmoudi, S.M.
 2019
 134 C p. 1-10
 article
23 Evaluation of recycle pathways for out-of-specification uranium microspheres from the internal gelation process Hunt, R.D.
 2019
 134 C p. 54-59
 article
24 Experimental study on air ingression and residence time of a small-scale decay tank for a research reactor Ji, Dae-Yun
 2019
 134 C p. 134-143
 article
25 Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements Li, Linfeng
 2019
 134 C p. 284-298
 article
26 Full core 3D simulation of the BEAVRS benchmark with OpenMOC Gunow, Geoffrey
 2019
 134 C p. 299-304
 article
27 GET-based time-dependent lattice homogenization using a global-local approach Schwanke, Peter
 2019
 134 C p. 359-369
 article
28 GPU accelerated lattice Boltzmann method in neutron kinetics problems II: Neutron transport calculation Wang, Yahui
 2019
 134 C p. 305-317
 article
29 Impact of the volume heat source on the RANS-based CFD analysis of Molten Salt Reactors Fiorina, Carlo
 2019
 134 C p. 376-382
 article
30 In-situ fabrication of dispersion nuclear fuel pellets with a core-shell structure Song, Tong
 2019
 134 C p. 258-262
 article
31 Metaheuristic optimization method for compact reactor radiation shielding design based on genetic algorithm Chen, Zhenping
 2019
 134 C p. 318-329
 article
32 Minor fault detection of thermocouple sensor in nuclear power plants using time series analysis Mandal, Shyamapada
 2019
 134 C p. 383-389
 article
33 Modeling of flow blockage due to swell and rupture for analysis of LBLOCA using a multiple fuel rods scheme under high burnup condition Bang, Young Seok
 2019
 134 C p. 350-358
 article
34 Modeling the consequences of fuel assembly bowing on PWR core neutronics using a Monte-Carlo code de Lambert, Stanislas
 2019
 134 C p. 330-341
 article
35 Nuclear data and applications at the nuclear safety and radioprotection institute: Analysis, evaluation and application Leal, L.
 2019
 134 C p. 244-249
 article
36 Parameters influencing the activation of dismantling nuclear facility structures Le Loirec, C.
 2019
 134 C p. 158-169
 article
37 Prediction of temperature distribution in annular fuels using orthogonal collocation method Esmaili, H.
 2019
 134 C p. 77-87
 article
38 Quantification of system uncertainties in activation experiments at nuclear research reactors MacConnachie, Elizabeth Laurel
 2019
 134 C p. 432-440
 article
39 Reduced-order modeling of parameterized multi-group diffusion k-eigenvalue problems German, Péter
 2019
 134 C p. 144-157
 article
40 Sensor fault detection in nuclear power plants using symbolic dynamic filter Mandal, Shyamapada
 2019
 134 C p. 390-400
 article
41 SiC coating on HTR graphite spheres prepared by fluidized-bed chemical vapor deposition Yang, Hui
 2019
 134 C p. 11-19
 article
42 Solution of 3D linearly anisotropic scattering, fixed-source multigroup xyz reactor problems by the A N Boundary Element – Response Matrix method Giusti, V.
 2019
 134 C p. 205-225
 article
43 Solution of the neutron survival probability equation using k-eigenmode expansion O’Rourke, Patrick F.
 2019
 134 C p. 178-192
 article
44 Structural integrity assessment of secondary support structure and reactor pressure vessel following drop impact of core barrel assembly Li, Yanhui
 2019
 134 C p. 38-46
 article
45 SuperMC cloud for nuclear design and safety evaluation Hu, Liqin
 2019
 134 C p. 424-431
 article
46 The adjoint problem as physical heuristic for loading pattern optimization Tal, O.
 2019
 134 C p. 226-234
 article
47 The transport and decay of radioactive aerosols in a wall-bounded turbulent flow Gu, Weiguo
 2019
 134 C p. 125-133
 article
                             47 results found
 
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