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                             47 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A comparative study of leakage and diffusion coefficient models for few-group cross section generation with the Monte Carlo method Dorval, E.
 2016
 90 C p. 353-363
11 p.
 artikel
2 Advanced operation strategy for feed-and-bleed operation in an OPR1000 Kim, Bo Gyung
 2016
 90 C p. 32-43
12 p.
 artikel
3 Analysis of LBLOCA using best estimate plus uncertainties for three-loop nuclear power plant power uprate Kang, Dong Gu
 2016
 90 C p. 318-330
13 p.
 artikel
4 Analysis of oxidation influence on steam explosion energetics Leskovar, Matjaž
 2016
 90 C p. 441-449
9 p.
 artikel
5 A novel domain overlapping strategy for the multiscale coupling of CFD with 1D system codes with applications to transient flows Grunloh, T.P.
 2016
 90 C p. 422-432
11 p.
 artikel
6 Application of melt and refining procedures in the CANDLE reactor concept Karim, Julia Abdul
 2016
 90 C p. 275-283
9 p.
 artikel
7 Application of the inverse generalized perturbation theory to the optimization of fuel assembly design Dall’Osso, Aldo
 2016
 90 C p. 417-421
5 p.
 artikel
8 Assessment of fission product inventory considering axial burnup of a fuel assembly Jeong, Hae Sun
 2016
 90 C p. 240-246
7 p.
 artikel
9 A statistical analysis in the BWR fuel lattice design Casillo-Méndez, José Alejandro
 2016
 90 C p. 83-92
10 p.
 artikel
10 Calculation and updating of Common Cause Failure unavailability by using alpha factor model Zubair, Muhammad
 2016
 90 C p. 106-114
9 p.
 artikel
11 Conjugate heat transfer investigation of core damage propagation during total instantaneous blockage in SFR fuel subassembly Ravi, L.
 2016
 90 C p. 371-388
18 p.
 artikel
12 Criticality calculations of the Very High Temperature Reactor Critical Assembly benchmark with Serpent and SCALE/KENO-VI Bostelmann, Friederike
 2016
 90 C p. 343-352
10 p.
 artikel
13 Determination of the power density distribution in a PWR reactor based on neutron flux measurements at fixed reactor incore detectors Dias, A.M.
 2016
 90 C p. 148-156
9 p.
 artikel
14 Determining the axial power profile of partly flooded fuel in a compact core assembled in reactor LR-0 Košťál, Michal
 2016
 90 C p. 450-458
9 p.
 artikel
15 Developing a safe and high performance fuel management optimization for MTRs using stochastic knowledge base searches Hedayat, Afshin
 2016
 90 C p. 157-174
18 p.
 artikel
16 Editorial board 2016
 90 C p. IFC-
1 p.
 artikel
17 Effective temperatures and scattering cross sections in water mixtures determined by Deep Inelastic Neutron Scattering Dawidowski, J.
 2016
 90 C p. 247-255
9 p.
 artikel
18 Efficient reduction and modularization for large fault trees stored by pages Chen, Shanqi
 2016
 90 C p. 22-25
4 p.
 artikel
19 Experimental study on the effect of wall-subcooling on condensation heat transfer in the presence of noncondensable gases in a horizontal tube Xu, Huiqiang
 2016
 90 C p. 9-21
13 p.
 artikel
20 Fault diagnosis of Pakistan Research Reactor-2 with data-driven techniques Jamil, Farhan
 2016
 90 C p. 433-440
8 p.
 artikel
21 Fuel-steel mixing and radial mesh effects in power excursion simulations Chen, X.-N.
 2016
 90 C p. 26-31
6 p.
 artikel
22 Galerkin partial least-square SN (GpLS–SN) method for fixed source problems in the neutron transport theory Araujo, Lenilson M.
 2016
 90 C p. 175-190
16 p.
 artikel
23 Improved methods of online monitoring and prediction in condensate and feed water system of nuclear power plant Wang, Hang
 2016
 90 C p. 44-53
10 p.
 artikel
24 Investigation on sloshing and vibration mitigation of water storage tank of AP1000 Zhao, Chunfeng
 2016
 90 C p. 331-342
12 p.
 artikel
25 Investigation on thermal stratification and turbulent penetration in a pressurizer surge line with an overall out-surge flow Zhang, Y.
 2016
 90 C p. 212-233
22 p.
 artikel
26 Linear heat generation rate for breaking plastic strain limit of cladding in a BWR fuel rod type Hernandez-Lopez, Hector
 2016
 90 C p. 234-239
6 p.
 artikel
27 MELCOR 2.1 analysis of melt behavior in a BWR lower head during LOCA and SBO accident Li, Gen
 2016
 90 C p. 195-204
10 p.
 artikel
28 NAFCON-SF: A sodium spray fire code for evaluating thermal consequences in SFR containment S., Muthu Saravanan
 2016
 90 C p. 389-409
21 p.
 artikel
29 Natural convection cooling characteristics in a plate type fuel assembly of Kyoto University Research Reactor during loss of coolant accident Ito, Daisuke
 2016
 90 C p. 1-8
8 p.
 artikel
30 Neutron flux estimation using Particle- H ∞ Filter for fast transient tracking Tamboli, Prakash Kumar
 2016
 90 C p. 115-122
8 p.
 artikel
31 Neutron-induced reaction on 233U Su, Xinwu
 2016
 90 C p. 123-134
12 p.
 artikel
32 Nonoverlapping local/global iterations with 2-D/1-D fusion transport kernel and p-CMFD wrapper for transient reactor analysis—II: Parallelization and Predictor–Corrector Quasi-Static method application Cho, Bumhee
 2016
 90 C p. 284-302
19 p.
 artikel
33 Non symmetric alternating direction explicit method applied to the calculation of ADS transients Figueira, Adriano Jorge
 2016
 90 C p. 459-467
9 p.
 artikel
34 Nuclear data uncertainties propagation methods in Boltzmann/Bateman coupled problems: Application to reactivity in MTR Frosio, Thomas
 2016
 90 C p. 303-317
15 p.
 artikel
35 On the concept of neutron multiplication Pázsit, Imre
 2016
 90 C p. 480-481
2 p.
 artikel
36 Preliminary analysis of radiation characteristic at upper section of Accelerator Driven Subcritical System Li, Bin
 2016
 90 C p. 410-416
7 p.
 artikel
37 Probabilistic approach for decay heat uncertainty estimation using URANIE platform and MENDEL depletion code Tsilanizara, A.
 2016
 90 C p. 62-70
9 p.
 artikel
38 Reactor physics analysis of the SPERT III E-core with Tripoli-4® Zoia, Andrea
 2016
 90 C p. 71-82
12 p.
 artikel
39 Real variance analysis of Monte Carlo eigenvalue calculation by McCARD for BEAVRS benchmark Park, Ho Jin
 2016
 90 C p. 205-211
7 p.
 artikel
40 Remark on the neutron noise induced by propagating perturbations in an MSR Dykin, V.
 2016
 90 C p. 93-105
13 p.
 artikel
41 Sensitivity and uncertainty analyses of reactivities for PWR cells with UO 2 and MOX fuels Foad, Basma
 2016
 90 C p. 468-479
12 p.
 artikel
42 Soft computing technique for developing turbine cycle model of Chinshan Nuclear Power Plant Unit 2 Chan, Yea-Kuang
 2016
 90 C p. 364-370
7 p.
 artikel
43 Study on the relation between Doppler reactivity coefficient and resonance integrals of Thorium and Uranium in PWR fuels Dobuchi, Noboru
 2016
 90 C p. 191-194
4 p.
 artikel
44 Temperature control characteristics analysis of lead-cooled fast reactor with natural circulation Yang, Minghan
 2016
 90 C p. 54-61
8 p.
 artikel
45 Thermal–hydraulic design and analysis code development for steam generator of CFR600 Sun, Peiwei
 2016
 90 C p. 256-263
8 p.
 artikel
46 Thermal-hydraulic modelling of the Cold Neutron Source thermosiphon system Pavlou, Tom
 2016
 90 C p. 135-147
13 p.
 artikel
47 Unavailability estimation of shutdown system of a fast reactor by Monte Carlo simulation Ramakrishnan, M.
 2016
 90 C p. 264-274
11 p.
 artikel
                             47 gevonden resultaten
 
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