| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Acceleration of 3D pin-by-pin calculations based on the heterogeneous variational nodal method
|
Zhang, Tengfei
|
|
2018
|
114 |
C |
p. 165-174
|
artikel
|
| 2 |
A critical heat flux model for saturated flow boiling on the downward curved heated surface
|
Hu, Qiang
|
|
2018
|
114 |
C |
p. 458-463
|
artikel
|
| 3 |
Adjoint neutron flux calculations with Tripoli-4®: Verification and comparison to deterministic codes
|
Terranova, Nicholas
|
|
2018
|
114 |
C |
p. 136-148
|
artikel
|
| 4 |
An Adjoint Proper Orthogonal Decomposition method for a neutronics reduced order model
|
Lorenzi, Stefano
|
|
2018
|
114 |
C |
p. 245-258
|
artikel
|
| 5 |
Analysis of nuclear fire safety by dynamic complex algorithm of fuzzy theory and system dynamics
|
Ho Woo, Tae
|
|
2018
|
114 |
C |
p. 149-153
|
artikel
|
| 6 |
Analysis of wall temperature jump of China Generation IV SFR Steam Generator
|
Zhong, Xianping
|
|
2018
|
114 |
C |
p. 510-517
|
artikel
|
| 7 |
Analytical solution of diffusion adjoint equation for homogeneous bare critical reactor
|
Hayashi, Masatoshi
|
|
2018
|
114 |
C |
p. 569-570
|
artikel
|
| 8 |
An angular biasing method using arbitrary convex polyhedra for Monte Carlo radiation transport calculations
|
Kulesza, Joel A.
|
|
2018
|
114 |
C |
p. 437-450
|
artikel
|
| 9 |
An improved target velocity sampling algorithm for free gas elastic scattering
|
Romano, Paul K.
|
|
2018
|
114 |
C |
p. 318-324
|
artikel
|
| 10 |
A non-equilibrium multiphase model for pressure escalation in fuel coolant interaction during explosion
|
Zhong, Mingjun
|
|
2018
|
114 |
C |
p. 74-85
|
artikel
|
| 11 |
A two-dimensional experimental investigation on the sloshing behavior in a water pool
|
Cheng, Songbai
|
|
2018
|
114 |
C |
p. 66-73
|
artikel
|
| 12 |
CAD modeling study on FLUKA and OpenMC for accelerator driven system simulation
|
Li, Jin-Yang
|
|
2018
|
114 |
C |
p. 329-341
|
artikel
|
| 13 |
Comparative neutronic study of homogeneous and heterogeneous thorium fuel based core design in a lead-cooled fast reactor
|
Juárez-Martínez, Luis-Carlos
|
|
2018
|
114 |
C |
p. 102-109
|
artikel
|
| 14 |
Comparison of HfB2 and ZrB2 behaviors for using in nuclear industry
|
Nasseri, Mohammad Mehdi
|
|
2018
|
114 |
C |
p. 603-606
|
artikel
|
| 15 |
Continuous-energy perturbation methods in the MORET 5 code
|
Jinaphanh, A.
|
|
2018
|
114 |
C |
p. 395-406
|
artikel
|
| 16 |
Detailed neutronic analysis of a MOX-fueled metal-cooled reactor
|
Jamil, Zeeshan
|
|
2018
|
114 |
C |
p. 427-436
|
artikel
|
| 17 |
Development and assessment of a parallel computing implementation of the Coarse Mesh Radiation Transport (COMET) method
|
Remley, Kyle
|
|
2018
|
114 |
C |
p. 288-300
|
artikel
|
| 18 |
Editorial Board
|
|
|
2018
|
114 |
C |
p. ii
|
artikel
|
| 19 |
Effect and treatment of angular dependency of multi-group total cross section and anisotropic scattering in fine-mesh transport calculation
|
Xia, Fan
|
|
2018
|
114 |
C |
p. 110-121
|
artikel
|
| 20 |
Effect of surface modification of silica nanoparticles by silane coupling agent on decontamination foam stability
|
Sonn, Jong Suk
|
|
2018
|
114 |
C |
p. 11-18
|
artikel
|
| 21 |
Efficient simultaneous solution of multi-physics multi-scale nonlinear coupled system in HTR reactor based on nonlinear elimination method
|
Zhang, Han
|
|
2018
|
114 |
C |
p. 301-310
|
artikel
|
| 22 |
Experimental study on aerosol scrubbing efficiency of self-priming venturi scrubber submerged in water pool
|
Lee, Jongchan
|
|
2018
|
114 |
C |
p. 571-585
|
artikel
|
| 23 |
Experimental study on 1/28 scaled NGNP HTGR reactor building test facility response to depressurization event
|
Yang, Se Ro
|
|
2018
|
114 |
C |
p. 154-164
|
artikel
|
| 24 |
Feasibility study for detection of reactor state changes during severe accidents via external gamma radiation measurements
|
Konheiser, Jörg
|
|
2018
|
114 |
C |
p. 175-180
|
artikel
|
| 25 |
Flooding prediction of counter-current flow in a vertical tube with non-axisymmetric disturbance waves
|
Zhang, Xiaobin
|
|
2018
|
114 |
C |
p. 616-623
|
artikel
|
| 26 |
Fuel cycle analysis of molten salt reactors based on coupled neutronics and thermal-hydraulics calculations
|
Zhou, Shengcheng
|
|
2018
|
114 |
C |
p. 369-383
|
artikel
|
| 27 |
Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: Analysis of reactor performance and safety characteristics
|
Lu, Cihang
|
|
2018
|
114 |
C |
p. 277-287
|
artikel
|
| 28 |
Hilbert spectrum analysis of unsteady characteristics in centrifugal pump operation under cavitation status
|
Sun, Hui
|
|
2018
|
114 |
C |
p. 607-615
|
artikel
|
| 29 |
Improving the efficiency of shielding container design calculations
|
Kastanya, Doddy
|
|
2018
|
114 |
C |
p. 586-591
|
artikel
|
| 30 |
Incorporation TACOM and SPAR-H into the operating procedure of nuclear power plants
|
Zhao, Xiaosong
|
|
2018
|
114 |
C |
p. 451-457
|
artikel
|
| 31 |
Introduction to Moltres: An application for simulation of Molten Salt Reactors
|
Lindsay, Alexander
|
|
2018
|
114 |
C |
p. 530-540
|
artikel
|
| 32 |
Magnetic variation and power density of gravity driven liquid metal magnetohydrodynamic generators
|
Ryan, Drew
|
|
2018
|
114 |
C |
p. 325-328
|
artikel
|
| 33 |
Modal analysis of the helical tube in a small nuclear reactor’s steam generator using a finite element method
|
Guo, Xin
|
|
2018
|
114 |
C |
p. 354-358
|
artikel
|
| 34 |
Neutronic/thermal-hydraulic coupling analysis of natural circulation IPWR under ocean conditions
|
Xia, Genglei
|
|
2018
|
114 |
C |
p. 92-101
|
artikel
|
| 35 |
Neutron noise simulation in the nuclear reactor core based on the average current nodal expansion method
|
Abed, A.
|
|
2018
|
114 |
C |
p. 482-494
|
artikel
|
| 36 |
Nuclide depletion capabilities in the Shift Monte Carlo code
|
Davidson, Gregory G.
|
|
2018
|
114 |
C |
p. 259-276
|
artikel
|
| 37 |
Numerical analysis of the 2D C5G7 MOX benchmark using P L equations and a nodal collocation method
|
Capilla, M.T.
|
|
2018
|
114 |
C |
p. 32-41
|
artikel
|
| 38 |
Numerical investigation of natural convection inside the containment with recovering passive containment cooling system using GASFLOW-MPI
|
Li, Yabing
|
|
2018
|
114 |
C |
p. 1-10
|
artikel
|
| 39 |
Numerical investigation on the bubble separation in a gas-liquid separator applied in TMSR
|
Yin, Junlian
|
|
2018
|
114 |
C |
p. 122-128
|
artikel
|
| 40 |
Numerical simulation of drainage performance in a drain device of steam generator
|
Mei, Yong
|
|
2018
|
114 |
C |
p. 311-317
|
artikel
|
| 41 |
Numerical study on temperature fluctuation of upper plenum in FBR with a more realistic model
|
Cao, Qiong
|
|
2018
|
114 |
C |
p. 214-226
|
artikel
|
| 42 |
On a various soft computing algorithms for reconstruction of the neutron noise source in the nuclear reactor cores
|
Hosseini, Seyed Abolfazl
|
|
2018
|
114 |
C |
p. 19-31
|
artikel
|
| 43 |
Penn State University TRIGA Reactor Digital Reactivity Computer: Development and Testing
|
Turso, James A.
|
|
2018
|
114 |
C |
p. 561-568
|
artikel
|
| 44 |
Quantification of control rod worth uncertainties propagated from nuclear data via a hybrid high-order perturbation and efficient sampling method
|
Hao, Chen
|
|
2018
|
114 |
C |
p. 227-235
|
artikel
|
| 45 |
Reactivity determination using the hybrid transport point kinetics and the area method
|
Picca, Paolo
|
|
2018
|
114 |
C |
p. 191-197
|
artikel
|
| 46 |
Reactor power monitoring using Cherenkov radiation transmitted through a small-bore metallic tube
|
Bentoumi, G.
|
|
2018
|
114 |
C |
p. 86-91
|
artikel
|
| 47 |
Research on the induced radioactivity of HTR-PM’s reactor pressure vessel: A comparative study between FLUKA, KORIGEN and QAD-CGA
|
Li, Wenqian
|
|
2018
|
114 |
C |
p. 129-135
|
artikel
|
| 48 |
Safe reactor depressurization windows for BWR Mark I Station Blackout accident management strategy
|
Bao, Han
|
|
2018
|
114 |
C |
p. 518-529
|
artikel
|
| 49 |
Seismic analysis of PWR control rod drop with the CRDAC scram performance code
|
Huang, Heng
|
|
2018
|
114 |
C |
p. 624-633
|
artikel
|
| 50 |
Sensitivity and uncertainty analysis for the PWR online power-distribution monitoring with NECP-ONION system
|
Li, Zhuo
|
|
2018
|
114 |
C |
p. 359-368
|
artikel
|
| 51 |
SN transport method for neutronic noise calculation in nuclear reactor systems: Comparative study between transport theory and diffusion theory
|
Bahrami, Mona
|
|
2018
|
114 |
C |
p. 236-244
|
artikel
|
| 52 |
Studies on the subcooled boiling in a fuel assembly with 5 by 5 rods using an improved wall boiling model
|
Cong, Tenglong
|
|
2018
|
114 |
C |
p. 413-426
|
artikel
|
| 53 |
The effect of eccentric loading in spent fuel pool criticality safety analyses
|
Metwally, Walid A.
|
|
2018
|
114 |
C |
p. 407-412
|
artikel
|
| 54 |
The influence of the air fraction in steam on the growth of the columnar oxide and the adjacent α-Zr(O) layer on Zry-4 fuel cladding at 1273 and 1473 K
|
Negyesi, Martin
|
|
2018
|
114 |
C |
p. 52-65
|
artikel
|
| 55 |
Thermal-hydraulic analysis of a 7-pin sodium fast reactor fuel bundle with a new pattern of helical wire wrap spacer
|
Park, Seong Dae
|
|
2018
|
114 |
C |
p. 198-205
|
artikel
|
| 56 |
Three-dimensional numerical investigation of heat transfer process in the reactor cavity of HTR-10
|
Zhao, Hangbin
|
|
2018
|
114 |
C |
p. 551-560
|
artikel
|
| 57 |
235U elastic cross-section adjustment in criticality benchmarks – Comparison between JENDL-4.0 and ENDF/-VII.1
|
Makhloul, M.
|
|
2018
|
114 |
C |
p. 541-550
|
artikel
|
| 58 |
Validation and evaluation of the ADVANTG hybrid code on the ICSBEP labyrinth benchmark experiment
|
Kotnik, Domen
|
|
2018
|
114 |
C |
p. 464-481
|
artikel
|
| 59 |
Validation of STRCS code for calculation of fission-product transport in reactor coolant system during severe accidents
|
Khaki Arani, Mehdi
|
|
2018
|
114 |
C |
p. 206-213
|
artikel
|
| 60 |
Validation of the DYN3D-Serpent code system for SFR cores using selected BFS experiments. Part II: DYN3D calculations
|
Rachamin, Reuven
|
|
2018
|
114 |
C |
p. 181-190
|
artikel
|
| 61 |
Validation of UNIST Monte Carlo code MCS for criticality safety analysis of PWR spent fuel pool and storage cask
|
Jang, Jaerim
|
|
2018
|
114 |
C |
p. 495-509
|
artikel
|
| 62 |
Verification of the multi-group diffusion code AZNHEX using the OECD/NEA UAM Sodium Fast Reactor Benchmark
|
del-Valle-Gallegos, Edmundo
|
|
2018
|
114 |
C |
p. 592-602
|
artikel
|
| 63 |
VHTR core analysis with McCARD and DeCART codes for high temperature engineering test reactor benchmark
|
Park, Jinsu
|
|
2018
|
114 |
C |
p. 42-51
|
artikel
|
| 64 |
Visual observations of flow patterns in downward air-water two-phase flows in a vertical narrow rectangular channel
|
Kim, Tae Hyeon
|
|
2018
|
114 |
C |
p. 384-394
|
artikel
|
| 65 |
Zero-dimensional transient model of large-scale cooling ponds using well-mixed approach
|
Ramadan, Ahmed
|
|
2018
|
114 |
C |
p. 342-353
|
artikel
|
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