| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accurate reflective boundary condition in the PN method
|
Yousefi, Mostafa
|
|
2017
|
109 |
C |
p. 583-599
|
artikel
|
| 2 |
A CFD-based simulation of fluid flow and heat transfer in the Intermediate Heat Exchanger of sodium-cooled fast reactor
|
Zhang, Xiaolong
|
|
2017
|
109 |
C |
p. 529-537
|
artikel
|
| 3 |
A computational study of re-cycling the MTR research reactors with MOX fuel mixed with 241Am, 242Am and 243Am as burnable absorbers actinides using the MCNP4C code
|
Shaaban, Ismail
|
|
2017
|
109 |
C |
p. 626-634
|
artikel
|
| 4 |
Analysis of single phase flow instability in U-tubes of steam generator
|
Yang, Bo
|
|
2017
|
109 |
C |
p. 180-184
|
artikel
|
| 5 |
Analytical solution of the Telegraph Point Reactor Kinetics model during the cold start-up of a nuclear reactor
|
Altahhan, Muhammad Ramzy
|
|
2017
|
109 |
C |
p. 574-582
|
artikel
|
| 6 |
An automatic marine-organism monitoring system for the intake water of the nuclear power plant
|
Tang, Zhihong
|
|
2017
|
109 |
C |
p. 208-211
|
artikel
|
| 7 |
A new cross section adjustment method of removing systematic errors in fast reactors
|
Takeda, Toshikazu
|
|
2017
|
109 |
C |
p. 698-704
|
artikel
|
| 8 |
A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding
|
Cinbiz, M. Nedim
|
|
2017
|
109 |
C |
p. 396-404
|
artikel
|
| 9 |
A review of research progress in heat exchanger tube rupture accident of heavy liquid metal cooled reactors
|
Wang, Gang
|
|
2017
|
109 |
C |
p. 1-8
|
artikel
|
| 10 |
Assessment of spent nuclear fuel amounts to be managed based on disposal option in Republic of Korea
|
Park, Byung Heung
|
|
2017
|
109 |
C |
p. 199-207
|
artikel
|
| 11 |
A study of photon interaction parameters in barium compounds
|
Manjunatha, H.C.
|
|
2017
|
109 |
C |
p. 310-317
|
artikel
|
| 12 |
ATWS boron analysis for a BWR using the FNPK equation
|
Polo-Labarrios, M.A.
|
|
2017
|
109 |
C |
p. 173-179
|
artikel
|
| 13 |
Benchmark and demonstration of the CHD code for transient analysis of fast reactor systems
|
Hellesen, C.
|
|
2017
|
109 |
C |
p. 712-719
|
artikel
|
| 14 |
Calculation of resonance self-shielding factors in a round disk using the enlarged Doppler Broadening Function
|
Palma, Daniel A.P.
|
|
2017
|
109 |
C |
p. 380-384
|
artikel
|
| 15 |
Capability of RELAP5 code to simulate the thermal-hydraulic characteristics of open natural circulation
|
Hou, Xiaofan
|
|
2017
|
109 |
C |
p. 612-625
|
artikel
|
| 16 |
Characteristics and mechanism of bubble breakup in a bubble generator developed for a small TMSR
|
Sun, Licheng
|
|
2017
|
109 |
C |
p. 69-81
|
artikel
|
| 17 |
Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor
|
Wang, Chenglong
|
|
2017
|
109 |
C |
p. 458-468
|
artikel
|
| 18 |
Conceptual design of thorium based epithermal spectrum reactor
|
Choi, Hong Yeop
|
|
2017
|
109 |
C |
p. 61-68
|
artikel
|
| 19 |
Coupled neutronics and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSY
|
Hu, Tianliang
|
|
2017
|
109 |
C |
p. 260-276
|
artikel
|
| 20 |
Coupled neutronics/thermal-hydraulics analysis of a full PWR core using RMC and CTF
|
Guo, Juanjuan
|
|
2017
|
109 |
C |
p. 327-336
|
artikel
|
| 21 |
Design analysis of DC electromagnetic pump for liquid sodium–CO2 reaction experimental characterization
|
Lee, Geun Hyeong
|
|
2017
|
109 |
C |
p. 490-497
|
artikel
|
| 22 |
Design of comprehensive diagnosis system in nuclear power plant
|
Li, Wei
|
|
2017
|
109 |
C |
p. 92-102
|
artikel
|
| 23 |
Design review and controllability assessment of the SMART-ITL secondary system for the SMART design with experimental investigation
|
Yun, Eunkoo
|
|
2017
|
109 |
C |
p. 538-547
|
artikel
|
| 24 |
Detection model of accidental control rod drop in PWR reactors with in-core and ex-core nuclear instrumentation using Delaunay triangulation
|
Souza, T.J.
|
|
2017
|
109 |
C |
p. 249-259
|
artikel
|
| 25 |
Development and analysis of a regime map for predicting debris bed formation behavior
|
Cheng, Songbai
|
|
2017
|
109 |
C |
p. 658-666
|
artikel
|
| 26 |
Diffusion theory model of the neutron number probability distribution in a subcritical multiplying assembly
|
Saxby, J.E.M.
|
|
2017
|
109 |
C |
p. 507-528
|
artikel
|
| 27 |
Dynamic modeling of AP1000 steam generator for control system design and simulation
|
Wan, Jiashuang
|
|
2017
|
109 |
C |
p. 648-657
|
artikel
|
| 28 |
Editorial board
|
|
|
2017
|
109 |
C |
p. IFC
|
artikel
|
| 29 |
Effect of power uprate on core damage frequency in a MBLOCA with multiple operator actions
|
Chen, Y.M.
|
|
2017
|
109 |
C |
p. 350-358
|
artikel
|
| 30 |
Effects of Gadolinium in Fe based amorphous ribbons with high boron contents on the neutron shielding efficiency
|
Park, Ji-Sung
|
|
2017
|
109 |
C |
p. 365-369
|
artikel
|
| 31 |
Energy Production Demonstrator and Material Testing Station optimization for Megawatt proton beams
|
Pronskikh, Vitaly S.
|
|
2017
|
109 |
C |
p. 692-697
|
artikel
|
| 32 |
Evaluation of an IVR-ERVC strategy for a high power reactor using MELCOR 2.1
|
Lim, Kukhee
|
|
2017
|
109 |
C |
p. 337-349
|
artikel
|
| 33 |
Evaluation of cooling capacity with more fuel stored in the spent fuel pool of the Kuosheng plant
|
Chen, Yen-Shu
|
|
2017
|
109 |
C |
p. 120-134
|
artikel
|
| 34 |
Evaluation of dose rate variation during very long term storage of RBMK-1500 reactor used fuel
|
Šmaižys, A.
|
|
2017
|
109 |
C |
p. 192-198
|
artikel
|
| 35 |
Evaluation of spent fuel pool temperature and water level during SBO
|
Mochizuki, Hiroyasu
|
|
2017
|
109 |
C |
p. 548-556
|
artikel
|
| 36 |
Experimental analysis of steam mixing and thermal stratification phenomena related to small steel containment studies
|
Wang, Shengfei
|
|
2017
|
109 |
C |
p. 103-112
|
artikel
|
| 37 |
Experimental and numerical study on the circumferential pressure distribution on the wall of a 90° elbow pipe with circular section
|
Wang, Shiming
|
|
2017
|
109 |
C |
p. 419-430
|
artikel
|
| 38 |
Experimental investigation on transient heat transfer in 2×2 bundle during depressurization from supercritical pressure
|
Li, Hongbo
|
|
2017
|
109 |
C |
p. 237-248
|
artikel
|
| 39 |
Finite volume lattice Boltzmann scheme for neutron/radiative transfer on unstructured mesh
|
Wang, Yahui
|
|
2017
|
109 |
C |
p. 227-236
|
artikel
|
| 40 |
Fission yield covariance matrices for the main neutron-induced fissioning systems contained in the JEFF-3.1.1 library
|
Terranova, N.
|
|
2017
|
109 |
C |
p. 469-489
|
artikel
|
| 41 |
Fluoride salt coolant properties for nuclear reactor applications: A review
|
Romatoski, R.R.
|
|
2017
|
109 |
C |
p. 635-647
|
artikel
|
| 42 |
Geometry pretreatment method for the 3D modular characteristic method based on AutoCAD
|
Liu, Zhouyu
|
|
2017
|
109 |
C |
p. 440-450
|
artikel
|
| 43 |
Hydrogen distribution and Passive Autocatalytic Recombiner (PAR) mitigation in a PWR-KWU containment type
|
Lopez-Alonso, Emma
|
|
2017
|
109 |
C |
p. 600-611
|
artikel
|
| 44 |
Influence of reflector materials and core coolant on the characteristics of accelerator driven systems
|
Panza, F.
|
|
2017
|
109 |
C |
p. 162-172
|
artikel
|
| 45 |
Investigation of density wave instability in once-through superheated steam generators using SIGHT
|
Tang, Yang
|
|
2017
|
109 |
C |
p. 41-51
|
artikel
|
| 46 |
Investigation of radiation shielding of the Containment Filtered Venting System for the various operating condition
|
Kim, Minhwa
|
|
2017
|
109 |
C |
p. 220-226
|
artikel
|
| 47 |
Modeling and experimental studies on air buoyant jets for application to small containments
|
Ma, Tengfei
|
|
2017
|
109 |
C |
p. 212-219
|
artikel
|
| 48 |
Multiphysics modeling of novel UO2-BeO sandwich fuel performance in a light water reactor
|
Liu, Rong
|
|
2017
|
109 |
C |
p. 298-309
|
artikel
|
| 49 |
Multiplication factors of single pin hexagonal cells and VVER-1000 reactor assembly
|
Prabha, Hem
|
|
2017
|
109 |
C |
p. 720-725
|
artikel
|
| 50 |
Neutronic calculations of the IAEA 10MW MTR benchmark reactor via finite element method using COMSOL multiphysics code
|
Xoubi, Ned
|
|
2017
|
109 |
C |
p. 277-283
|
artikel
|
| 51 |
Neutronic modeling and calculations of the ETRR-2 MTR reactor using COMSOL multiphysics code
|
Xoubi, Ned
|
|
2017
|
109 |
C |
p. 667-674
|
artikel
|
| 52 |
Numerical investigation of passive thermal-hydraulic performance of spent fuel dry-storage system for HTR-PM
|
Wang, Bing
|
|
2017
|
109 |
C |
p. 135-150
|
artikel
|
| 53 |
Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5
|
Feng, Tangtao
|
|
2017
|
109 |
C |
p. 318-326
|
artikel
|
| 54 |
Numerical studies of a helical coil once-through steam generator
|
Xia, Genglei
|
|
2017
|
109 |
C |
p. 52-60
|
artikel
|
| 55 |
Onset of Nucleate Boiling for subcooled flow through a one-side heated narrow rectangular channel
|
Al-Yahia, Omar S.
|
|
2017
|
109 |
C |
p. 30-40
|
artikel
|
| 56 |
Onset of Nucleate Boiling in narrow, rectangular channel for downward flow under low pressure
|
Song, Jung Hyun
|
|
2017
|
109 |
C |
p. 498-506
|
artikel
|
| 57 |
Performance verification of Passive Accident Mitigation Scheme (PAMS) under feedwater line break (FLB) accident
|
Shi, Er-bing
|
|
2017
|
109 |
C |
p. 151-161
|
artikel
|
| 58 |
Polyvinyl alcohol-borate hydrogel containing magnetic adsorbent for surface decontamination
|
Yang, Hee-Man
|
|
2017
|
109 |
C |
p. 359-364
|
artikel
|
| 59 |
Preliminary study of applying adjoint-based mesh optimization method to nuclear power plant safety analysis
|
Son, Seongmin
|
|
2017
|
109 |
C |
p. 405-418
|
artikel
|
| 60 |
Proposal to reload using MOX weapons grade in a BWR reactor
|
Hernandez, Hector
|
|
2017
|
109 |
C |
p. 451-457
|
artikel
|
| 61 |
Real-time simulations to enhance distributed on-line monitoring and fault detection in Pressurized Water Reactors
|
Peng, Min-jun
|
|
2017
|
109 |
C |
p. 557-573
|
artikel
|
| 62 |
RELAP5 uncertainty evaluation using ROSA/LSTF test data on PWR 17% cold leg intermediate-break LOCA with single-failure ECCS
|
Takeda, Takeshi
|
|
2017
|
109 |
C |
p. 9-21
|
artikel
|
| 63 |
Rod ejection accident analysis for AP1000 with MOX/UOX mixed core loading
|
Selim, Hala K.
|
|
2017
|
109 |
C |
p. 385-395
|
artikel
|
| 64 |
Sensitivity analysis for the weighting factor in the least-square method for the PWR on-line power-distribution monitoring
|
Li, Zhuo
|
|
2017
|
109 |
C |
p. 675-683
|
artikel
|
| 65 |
Study on operator’s SA reliability in digital NPPs. Part 3: A quantitative assessment method
|
Li, Peng-cheng
|
|
2017
|
109 |
C |
p. 82-91
|
artikel
|
| 66 |
Study on operator's SA reliability in digital NPPs. Part 2: Data-driven causality model of SA
|
Li, Peng-cheng
|
|
2017
|
109 |
C |
p. 185-191
|
artikel
|
| 67 |
Supercritical transient analysis in coupled fuel debris systems of symmetric and asymmetric geometry using integral kinetic model
|
Tuya, Delgersaikhan
|
|
2017
|
109 |
C |
p. 113-119
|
artikel
|
| 68 |
Thermal hydraulics analysis of a helical coil steam generator of a small modular reactor
|
Zaman, Fakhar Uz
|
|
2017
|
109 |
C |
p. 705-711
|
artikel
|
| 69 |
Track truncation method for improving the computational efficiency of 2D matrix MOC
|
Zheng, Yong
|
|
2017
|
109 |
C |
p. 684-691
|
artikel
|
| 70 |
Uncertainty assessment for loss of flow accident of a 5MW pool-type research reactor
|
Yum, Soo-been
|
|
2017
|
109 |
C |
p. 22-29
|
artikel
|
| 71 |
Use cases of Tucker decomposition method for reconstruction of neutron macroscopic cross-sections
|
Luu, Thi Hieu
|
|
2017
|
109 |
C |
p. 284-297
|
artikel
|
| 72 |
Validation of CFD analysis for rod bundle flow test with vaned spacer grids
|
Chen, Xi
|
|
2017
|
109 |
C |
p. 370-379
|
artikel
|
| 73 |
Verification of kinetic capabilities of the GNOMER neutron diffusion code
|
Merljak, Vid
|
|
2017
|
109 |
C |
p. 431-439
|
artikel
|
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