| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
An experimental test facility to support development of the fluoride-salt-cooled high-temperature reactor
|
Yoder Jr., Graydon L.
|
|
2014
|
64 |
C |
p. 511-517
7 p.
|
artikel
|
| 2 |
Application of safety analysis code SIMMER-IV to blockage accidents in FASTEF subcritical core
|
Kriventsev, V.
|
|
2014
|
64 |
C |
p. 114-121
8 p.
|
artikel
|
| 3 |
A preliminary approach to the MSFR control issues
|
Guerrieri, Claudia
|
|
2014
|
64 |
C |
p. 472-484
13 p.
|
artikel
|
| 4 |
A quantitative CFD benchmark for Sodium Fast Reactor fuel assembly modeling
|
Fricano, J.W.
|
|
2014
|
64 |
C |
p. 32-42
11 p.
|
artikel
|
| 5 |
Assessment of passive safety system performance under main steam line break accident
|
Lim, J.
|
|
2014
|
64 |
C |
p. 287-294
8 p.
|
artikel
|
| 6 |
Bat algorithm for the fuel arrangement optimization of reactor core
|
Kashi, S.
|
|
2014
|
64 |
C |
p. 144-151
8 p.
|
artikel
|
| 7 |
Contributions to the inverse problem of radiation transport
|
Difilippo, Felix C.
|
|
2014
|
64 |
C |
p. 212-219
8 p.
|
artikel
|
| 8 |
Coupled study of the Molten Salt Fast Reactor core physics and its associated reprocessing unit
|
Doligez, X.
|
|
2014
|
64 |
C |
p. 430-440
11 p.
|
artikel
|
| 9 |
Criticality calculations of the HTR-10 pebble-bed reactor with SCALE6/CSAS6 and MCNP5
|
Wang, Meng-Jen
|
|
2014
|
64 |
C |
p. 1-7
7 p.
|
artikel
|
| 10 |
Design of a passive residual heat removal system for the FUJI-233Um molten salt reactor system
|
Ishiguro, T.
|
|
2014
|
64 |
C |
p. 398-407
10 p.
|
artikel
|
| 11 |
2D full-core Monte Carlo pin-by-pin burnup calculations with the RMC code
|
She, Ding
|
|
2014
|
64 |
C |
p. 201-205
5 p.
|
artikel
|
| 12 |
Direct Doppler broadening in Monte Carlo simulations using the multipole representation
|
Forget, Benoit
|
|
2014
|
64 |
C |
p. 78-85
8 p.
|
artikel
|
| 13 |
Discontinuous finite element formulations for neutron transport in spherical geometry
|
Mercimek, Mehmet
|
|
2014
|
64 |
C |
p. 244-255
12 p.
|
artikel
|
| 14 |
Editorial board
|
|
|
2014
|
64 |
C |
p. IFC-
1 p.
|
artikel
|
| 15 |
Effect of rolling motion on transient flow resistance of two-phase flow in a narrow rectangular duct
|
Jin, Guangyuan
|
|
2014
|
64 |
C |
p. 135-143
9 p.
|
artikel
|
| 16 |
Exact analytical solution of time-independent neutron transport equation, and its applications to systems with a point source
|
Mikata, Y.
|
|
2014
|
64 |
C |
p. 152-155
4 p.
|
artikel
|
| 17 |
Flow blockage accident or loss of flow accident by using comparative approach of NK/TH coupling codes and RELAP5 code
|
Khan, Salah Ud-Din
|
|
2014
|
64 |
C |
p. 311-319
9 p.
|
artikel
|
| 18 |
Flow instability analysis in U-tubes of steam generator under rolling movement
|
Hao, Jianli
|
|
2014
|
64 |
C |
p. 295-300
6 p.
|
artikel
|
| 19 |
Foreword of the Guest-editors
|
Kloosterman, Jan Leen
|
|
2014
|
64 |
C |
p. 343-
1 p.
|
artikel
|
| 20 |
Fuel cycle advantages and dynamics features of liquid fueled MSR
|
Křepel, Jiří
|
|
2014
|
64 |
C |
p. 380-397
18 p.
|
artikel
|
| 21 |
Fuel element and full core thermal–hydraulic analysis of the AHTR for the evaluation of the LOFC transient
|
Avigni, P.
|
|
2014
|
64 |
C |
p. 499-510
12 p.
|
artikel
|
| 22 |
Gamma ray and neutron shielding properties of some alloy materials
|
Singh, Vishwanath P.
|
|
2014
|
64 |
C |
p. 301-310
10 p.
|
artikel
|
| 23 |
Hybrid particle swarm optimization algorithm and its application in nuclear engineering
|
Liu, C.Y.
|
|
2014
|
64 |
C |
p. 276-286
11 p.
|
artikel
|
| 24 |
Implementation of a phenomenological DNB prediction model based on macroscale boiling flow processes in PWR fuel bundles
|
Mohitpour, Maryam
|
|
2014
|
64 |
C |
p. 176-190
15 p.
|
artikel
|
| 25 |
Influence of boron carbide on core degradation during severe accidents in LWRs
|
Steinbrück, Martin
|
|
2014
|
64 |
C |
p. 43-49
7 p.
|
artikel
|
| 26 |
Investigating flow and heat transfer characteristics in a fuel bundle with split-vane pair grids by CFD methodology
|
Tseng, Y.S.
|
|
2014
|
64 |
C |
p. 93-99
7 p.
|
artikel
|
| 27 |
Investigation of flow pulsation characteristic in single-phase forced circulation under rolling motion
|
Wang, Chang
|
|
2014
|
64 |
C |
p. 50-56
7 p.
|
artikel
|
| 28 |
Metal oxide aerosol dry deposition in laminar pipe flow at high thermal gradients and comparison with SOPHAEROS module of ASTEC reactor accident analysis code
|
Modi, R.
|
|
2014
|
64 |
C |
p. 107-113
7 p.
|
artikel
|
| 29 |
Modelling and analysis of the MSFR transient behaviour
|
Fiorina, Carlo
|
|
2014
|
64 |
C |
p. 485-498
14 p.
|
artikel
|
| 30 |
Molten salt actinide recycler and transforming system without and with Th–U support: Fuel cycle flexibility and key material properties
|
Ignatiev, V.
|
|
2014
|
64 |
C |
p. 408-420
13 p.
|
artikel
|
| 31 |
NEMSQR: A 3-D multi group diffusion theory code based on nodal expansion method for square geometry
|
Singh, Tej
|
|
2014
|
64 |
C |
p. 230-243
14 p.
|
artikel
|
| 32 |
Neutron capture cross section measurement for the 174Yb(n,γ)175Yb reaction at 0.0372eV energy
|
Belouadah, N.
|
|
2014
|
64 |
C |
p. 264-269
6 p.
|
artikel
|
| 33 |
Neutronic analysis of the Geological Survey TRIGA Reactor
|
Shugart, Nicolas
|
|
2014
|
64 |
C |
p. 122-134
13 p.
|
artikel
|
| 34 |
Neutron shielding studies on an advanced molten salt fast reactor design
|
Merk, Bruno
|
|
2014
|
64 |
C |
p. 441-448
8 p.
|
artikel
|
| 35 |
Nodal synthetic kernel (N-SKN) method for solving neutron transport equation in one- and two-dimensional X–Y geometries
|
Altac, Zekeriya
|
|
2014
|
64 |
C |
p. 320-332
13 p.
|
artikel
|
| 36 |
Non-linear simulation and control of xenon induced oscillations in Advanced Heavy Water Reactor
|
Munje, R.K.
|
|
2014
|
64 |
C |
p. 191-200
10 p.
|
artikel
|
| 37 |
Numerical simulation of the flow instability between two heated parallel channels with supercritical water
|
Xi, Xi
|
|
2014
|
64 |
C |
p. 57-66
10 p.
|
artikel
|
| 38 |
On the non-uniqueness of the nodal mathematical adjoint
|
Müller, Erwin
|
|
2014
|
64 |
C |
p. 333-342
10 p.
|
artikel
|
| 39 |
Polynomial interpolation of few-group neutron cross sections on sparse grids
|
Botes, Danniëll
|
|
2014
|
64 |
C |
p. 156-168
13 p.
|
artikel
|
| 40 |
Power probability density function control and performance assessment of a nuclear research reactor
|
Abharian, Amir Esmaeili
|
|
2014
|
64 |
C |
p. 11-20
10 p.
|
artikel
|
| 41 |
Pre-equilibrium effects on (n,p) reactions of Gd and Dy isotopes from threshold to 20MeV
|
Pandey, Hem Chandra
|
|
2014
|
64 |
C |
p. 8-10
3 p.
|
artikel
|
| 42 |
Preliminary thermal–hydraulic core design of the Molten Salt Fast Reactor (MSFR)
|
Rouch, H.
|
|
2014
|
64 |
C |
p. 449-456
8 p.
|
artikel
|
| 43 |
Random effects on reactivity in molten salt reactors
|
Dulla, Sandra
|
|
2014
|
64 |
C |
p. 353-364
12 p.
|
artikel
|
| 44 |
Scaling modeling analysis of flow instability in U-tubes of steam generator under natural circulation
|
Hao, Jianli
|
|
2014
|
64 |
C |
p. 169-175
7 p.
|
artikel
|
| 45 |
Self-shielding models of MICROX-2 code: Review and updates
|
Hou, J.
|
|
2014
|
64 |
C |
p. 256-263
8 p.
|
artikel
|
| 46 |
Severe accident source terms for a sodium-cooled fast reactor
|
Brunett, Acacia
|
|
2014
|
64 |
C |
p. 220-229
10 p.
|
artikel
|
| 47 |
Slug behavior and pressure drop of adiabatic slug flow in a narrow rectangular duct under inclined conditions
|
Yan, Chaoxing
|
|
2014
|
64 |
C |
p. 21-31
11 p.
|
artikel
|
| 48 |
Soil mass attenuation coefficient: Analysis and evaluation
|
Costa, J.C.
|
|
2014
|
64 |
C |
p. 206-211
6 p.
|
artikel
|
| 49 |
Spectral Green’s function nodal method for multigroup SN problems with anisotropic scattering in slab-geometry non-multiplying media
|
Menezes, Welton A.
|
|
2014
|
64 |
C |
p. 270-275
6 p.
|
artikel
|
| 50 |
Steady-state and dynamic behavior of a moderated molten salt reactor
|
Nagy, K.
|
|
2014
|
64 |
C |
p. 365-379
15 p.
|
artikel
|
| 51 |
The point kinetic component of neutron noise in an MSR
|
Pázsit, I.
|
|
2014
|
64 |
C |
p. 344-352
9 p.
|
artikel
|
| 52 |
Thermal–hydraulic analyses and experimental modelling of MSFR
|
Yamaji, Bogdán
|
|
2014
|
64 |
C |
p. 457-471
15 p.
|
artikel
|
| 53 |
Thermo-mechanic behavior simulation for fuel assemblies manufactured in Mexico with FEMAXI-VI code
|
Hernandez-Lopez, Hector
|
|
2014
|
64 |
C |
p. 100-106
7 p.
|
artikel
|
| 54 |
Towards the thorium fuel cycle with molten salt fast reactors
|
Heuer, D.
|
|
2014
|
64 |
C |
p. 421-429
9 p.
|
artikel
|
| 55 |
Transmutation of minor actinides in the pressurized water reactors
|
Liu, Bin
|
|
2014
|
64 |
C |
p. 86-92
7 p.
|
artikel
|
| 56 |
Tube and shell side coupled thermal analysis of an HTGR helical tube once through steam generator using porous media method
|
Olson, Joshua Tanner
|
|
2014
|
64 |
C |
p. 67-77
11 p.
|
artikel
|
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