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                             28 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A 3-D simulation tool for hydrogen detonation during severe accident and its application Huang, T.
2017
104 C p. 113-123
artikel
2 A forward-backward coupled source term estimation for nuclear power plant accident: A case study of loss of coolant accident scenario Sun, Sida
2017
104 C p. 64-74
artikel
3 An experimental validation of Feynman-Alpha Method’s Bunching Technique in the IPEN/MB-01 Nuclear Reator Alves, L.F.M.
2017
104 C p. 243-246
artikel
4 A proposal on multi-response CADIS method to optimize reduction of regional variances in hybrid Monte Carlo simulation Kim, Do Hyun
2017
104 C p. 282-290
artikel
5 Comparison and analysis on transient characteristics of integral pressurized water reactors Zhang, Guoxu
2017
104 C p. 91-102
artikel
6 Conceptual design of a sub-critical Pb-cooled Accelerator Driven System (ADS) fuelled by (Th-LEU) Glinatsis, G.
2017
104 C p. 1-8
artikel
7 Covariance matrices of the hydrogen neutron cross sections bound in light water for the JEFF-3.1.1 neutron library Noguere, G.
2017
104 C p. 132-145
artikel
8 Determining the minimum required uranium carbide content for HTGR UCO fuel kernels McMurray, Jacob W.
2017
104 C p. 237-242
artikel
9 Developing and investigating a pure Monte-Carlo module for transient neutron transport analysis Mylonakis, Antonios G.
2017
104 C p. 103-112
artikel
10 Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs Deng, Yangbin
2017
104 C p. 146-156
artikel
11 Development of whole core pin-by-pin transport theory model in hexagonal geometry Khan, Suhail Ahmad
2017
104 C p. 214-228
artikel
12 3D numerical study of LBE-cooled fuel assembly in MYRRHA using SIMMER-IV code Li, Rui
2017
104 C p. 42-52
artikel
13 Editorial board 2017
104 C p. IFC
artikel
14 FITXS: A fast and flexible burn-up scheme based on the fitting of one-group cross-sections Halász, Máté
2017
104 C p. 267-281
artikel
15 Improving fuel utilization in SmAHTR with spectral shift control design: Proof of concept Kotlyar, D.
2017
104 C p. 53-63
artikel
16 Integrated CFD investigation of heat transfer enhancement using multi-tray core catcher in SFR Rakhi,
2017
104 C p. 256-266
artikel
17 Investigation of flow through multi-stage restricting orifices Araoye, Abdulrazaq A.
2017
104 C p. 75-90
artikel
18 MCNP6 simulated performance of Micro-Pocket Fission Detectors (MPFDs) in the Transient REActor Test (TREAT) facility Patel, Vishal K.
2017
104 C p. 191-196
artikel
19 Methods of applying nuclear simulation technology to the dynamic site testing of digital I&C system—Ⅱ: DCS-testing methods Lin, Meng
2017
104 C p. 166-177
artikel
20 Methods of applying nuclear simulation technology to the dynamic site testing of digital I&C system—I: Scheme of OLVT Li, Yankai
2017
104 C p. 157-165
artikel
21 Natural frequencies of a CANDU fuel string Fadaee, M.
2017
104 C p. 247-255
artikel
22 On the solution of the SN multigroup kinetics equations in multilayer slabs Segatto, C.F.
2017
104 C p. 229-236
artikel
23 Study on flow characteristics in an open two-phase natural circulation loop Yan, Xiao
2017
104 C p. 291-300
artikel
24 The effect of the advanced drift-flux model of ASSERT-PV on critical heat flux, flow and void distributions in CANDU bundle subchannels Hammouda, N.
2017
104 C p. 197-213
artikel
25 Three dimensional thermal hydraulic characteristic analysis of reactor core based on porous media method Chen, Ronghua
2017
104 C p. 178-190
artikel
26 Uncertainty analysis of assembly and core-level calculations with application to CASMO-4E and SIMULATE-3 Pusa, Maria
2017
104 C p. 124-131
artikel
27 Uncertainty and sensitivity analysis for the simulation of a station blackout scenario in the Jules Horowitz Reactor Ghione, Alberto
2017
104 C p. 28-41
artikel
28 Verification of AP1000® low-margin PRA sequences based on best-estimate calculations Queral, C.
2017
104 C p. 9-27
artikel
                             28 gevonden resultaten
 
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