| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A calculation method for transient flow distribution of SCWR(CSR1000)
|
Chen, Juan
|
|
2017
|
110 |
C |
p. 541-546
|
artikel
|
| 2 |
A computerized method (UPPREC) for quantitative analysis of irradiated nuclear fuel assemblies with gamma emission tomography at the Halden reactor
|
Andersson, P.
|
|
2017
|
110 |
C |
p. 88-97
|
artikel
|
| 3 |
Added mass effect for tip-over analysis of dry cask composite structures at two different scales
|
Champiri, Masoud Dehghani
|
|
2017
|
110 |
C |
p. 126-139
|
artikel
|
| 4 |
Adjoint-based constant-mass partial derivatives
|
Favorite, Jeffrey A.
|
|
2017
|
110 |
C |
p. 1052-1059
|
artikel
|
| 5 |
Advanced modeling techniques of a spent fuel pool with both RELAP5 and MELCOR and associated accident analysis
|
Zhang, Z.W.
|
|
2017
|
110 |
C |
p. 160-170
|
artikel
|
| 6 |
A fuzzy expectation maximization based method for estimating the parameters of a multi-state degradation model from imprecise maintenance outcomes
|
Cannarile, F.
|
|
2017
|
110 |
C |
p. 739-752
|
artikel
|
| 7 |
Algorithms of solving the burnup equation with external feed
|
Li, Jian
|
|
2017
|
110 |
C |
p. 412-417
|
artikel
|
| 8 |
Alternative method for determination of specific activity of plutonium present in the irradiated fuel solution
|
Dhamodharan, K.
|
|
2017
|
110 |
C |
p. 1197-1201
|
artikel
|
| 9 |
A method for predicting fuel maintenance in once-through MSRs
|
Ridley, Gavin
|
|
2017
|
110 |
C |
p. 265-281
|
artikel
|
| 10 |
Analysis of dynamic reactivity by Monte Carlo methods: The impact of nuclear data
|
Zoia, Andrea
|
|
2017
|
110 |
C |
p. 11-24
|
artikel
|
| 11 |
Analysis of primary bleed and feed strategies for selected SBLOCA sequences in a German Konvoi PWR using ASTEC V2.0
|
Gómez-García-Toraño, Ignacio
|
|
2017
|
110 |
C |
p. 818-832
|
artikel
|
| 12 |
Analysis on LOCA for CSR1000
|
Chen, Juan
|
|
2017
|
110 |
C |
p. 903-908
|
artikel
|
| 13 |
An arbitrary geometry finite element method for the adjoint neutron transport equation
|
Yousefi, Mostafa
|
|
2017
|
110 |
C |
p. 511-525
|
artikel
|
| 14 |
An assessment of heat transfer models of water flow in helically coiled tubes based on selected experimental datasets
|
Gou, Junli
|
|
2017
|
110 |
C |
p. 648-667
|
artikel
|
| 15 |
An efficient evaluation of depletion uncertainty for a GBC-32 dry storage cask with PLUS7 fuel assemblies using the Monte Carlo uncertainty sampling method
|
Yun, Hyungju
|
|
2017
|
110 |
C |
p. 679-691
|
artikel
|
| 16 |
A new and rigorous SPN theory – Part II: Generalization to GSPN
|
Chao, Yung-An
|
|
2017
|
110 |
C |
p. 1176-1196
|
artikel
|
| 17 |
A new derivation of the multigroup transport equations via homogeneity and isotropy restoration theory
|
Cho, Nam Zin
|
|
2017
|
110 |
C |
p. 798-804
|
artikel
|
| 18 |
A new nonlinear iterative method for SPN theory
|
Pan, Qingquan
|
|
2017
|
110 |
C |
p. 920-927
|
artikel
|
| 19 |
A new procedure for solving steady-state and transient-state nonlinear radial conduction problems of nuclear fuel rods
|
Tang, Jiannan
|
|
2017
|
110 |
C |
p. 492-500
|
artikel
|
| 20 |
A Newton-based Jacobian-free approach for neutronic-Monte Carlo/thermal-hydraulic static coupled analysis
|
Mylonakis, Antonios G.
|
|
2017
|
110 |
C |
p. 709-725
|
artikel
|
| 21 |
An experimental study of pool entrainment with side exit
|
Zhang, Peng
|
|
2017
|
110 |
C |
p. 406-411
|
artikel
|
| 22 |
A novel method to improve dose assessment due to severe NPP accidents based on field measurements and particle swarm optimization
|
Pereira, Cláudio M.N.A.
|
|
2017
|
110 |
C |
p. 148-159
|
artikel
|
| 23 |
Application of the CAB evaluation of thermal scattering law for heavy water to ZED-2 critical benchmarks at room temperature
|
Roubtsov, D.
|
|
2017
|
110 |
C |
p. 958-972
|
artikel
|
| 24 |
A review of recent numerical and experimental research progress on CDA safety analysis of LBE-/lead-cooled fast reactors
|
Wang, Gang
|
|
2017
|
110 |
C |
p. 1139-1147
|
artikel
|
| 25 |
A scaling method for generating floor response spectra
|
Jiang, Wei
|
|
2017
|
110 |
C |
p. 613-632
|
artikel
|
| 26 |
Assessment of a simplified set of momentum closure relations for low volume fraction regimes in STAR-CCM+ and OpenFOAM
|
Sugrue, Rosemary
|
|
2017
|
110 |
C |
p. 79-87
|
artikel
|
| 27 |
Assessment of post-LOCA long term cooling considering the in-vessel downstream effect
|
Amin, Shah Asad Ullah
|
|
2017
|
110 |
C |
p. 63-72
|
artikel
|
| 28 |
A study of China’s uranium resources security issues: Based on analysis of China’s nuclear power development trend
|
Xing, Wanli
|
|
2017
|
110 |
C |
p. 1156-1164
|
artikel
|
| 29 |
Axial crack resistance of cladding tubes for fast reactors
|
Sanyal, G.
|
|
2017
|
110 |
C |
p. 459-474
|
artikel
|
| 30 |
Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores
|
Li, J.
|
|
2017
|
110 |
C |
p. 1023-1029
|
artikel
|
| 31 |
BWR stability analysis with sub-diffusive and feedback effects
|
Vyawahare, Vishwesh. A.
|
|
2017
|
110 |
C |
p. 349-361
|
artikel
|
| 32 |
CFD/Monte-Carlo neutron transport coupling scheme, application to TRIGA reactor
|
Henry, R.
|
|
2017
|
110 |
C |
p. 36-47
|
artikel
|
| 33 |
Comparative analysis of proton and light ion beams for energy amplification in subcritical systems
|
Baldin, A.A.
|
|
2017
|
110 |
C |
p. 973-978
|
artikel
|
| 34 |
Computationally-generated nuclear forensic characteristics of early production reactors with an emphasis on sensitivity and uncertainty
|
Redd, Evan M.
|
|
2017
|
110 |
C |
p. 941-947
|
artikel
|
| 35 |
Critical heat flux for downward-facing pool boiling on CANDU calandria vessel
|
Behdadi, Azin
|
|
2017
|
110 |
C |
p. 768-778
|
artikel
|
| 36 |
Cross section adjustment for fast reactor design: ATCROSS code and its application
|
Vrban, Branislav
|
|
2017
|
110 |
C |
p. 928-940
|
artikel
|
| 37 |
α-Cut method based importance measure for criticality analysis in fuzzy probability – Based fault tree analysis
|
Purba, Julwan Hendry
|
|
2017
|
110 |
C |
p. 234-243
|
artikel
|
| 38 |
Development of a Nodal Expansion Method based space-time kinetics code for hexagonal geometry
|
Singh, Tej
|
|
2017
|
110 |
C |
p. 584-602
|
artikel
|
| 39 |
Development of continuous-energy sensitivity analysis capability in OpenMC
|
Peng, Xingjie
|
|
2017
|
110 |
C |
p. 362-383
|
artikel
|
| 40 |
Dimensionality reducibility for multi-physics reduced order modeling
|
Huang, Dongli
|
|
2017
|
110 |
C |
p. 526-540
|
artikel
|
| 41 |
3D space-time analysis of ATWS in compact high temperature reactor with integrated thermal-hydraulic model in code ARCH-TH
|
Dwivedi, D.K.
|
|
2017
|
110 |
C |
p. 306-316
|
artikel
|
| 42 |
Editorial board
|
|
|
2017
|
110 |
C |
p. IFC
|
artikel
|
| 43 |
Effect of water entrainment on the coolability of a debris bed surrounded by a by-pass: Integral reflood experiments and modelling
|
Chikhi, N.
|
|
2017
|
110 |
C |
p. 418-437
|
artikel
|
| 44 |
Effects of seismic action and material properties variations on seismic responses of base-isolated nuclear containment structure
|
Zhuang, Chu-Li
|
|
2017
|
110 |
C |
p. 909-919
|
artikel
|
| 45 |
Expanding the applicable duration for shrink fitting of the ultrathin-walled reactor coolant pump rotor-can
|
Li, Ruiqin
|
|
2017
|
110 |
C |
p. 1217-1223
|
artikel
|
| 46 |
Experimental analysis of the thermal field and heat transfer characteristics of a pebble-bed core in a high-temperature gas-cooled reactor
|
Chen, Leisheng
|
|
2017
|
110 |
C |
p. 338-348
|
artikel
|
| 47 |
Experimental and numerical study on fluctuations and distributions of fluid temperature under rolling motion conditions
|
Yu, Shengzhi
|
|
2017
|
110 |
C |
p. 384-399
|
artikel
|
| 48 |
Experimental and theoretical investigations on effect of U-tube inlet and secondary temperatures on reverse flow inside UTSG
|
Chu, Xi
|
|
2017
|
110 |
C |
p. 1073-1080
|
artikel
|
| 49 |
Experimental investigation of effect of spacer on single phase turbulent mixing rate on simulated subchannel of Advanced Heavy Water Reactor
|
Verma, Shashi Kant
|
|
2017
|
110 |
C |
p. 186-195
|
artikel
|
| 50 |
Experimental investigation on the unsteady pressure pulsation of reactor coolant pumps with non-uniform inflow
|
Long, Yun
|
|
2017
|
110 |
C |
p. 501-510
|
artikel
|
| 51 |
Experimental studies of condensing vapor bubbles in subcooled pool water using visual and acoustic analysis methods
|
Jo, Hongrae
|
|
2017
|
110 |
C |
p. 171-185
|
artikel
|
| 52 |
Experimental study on breakdown voltage of high pressure and high temperature helium gas between parallel electrodes
|
Liu, Xingnan
|
|
2017
|
110 |
C |
p. 1224-1231
|
artikel
|
| 53 |
Fabrication and testing of a 5-node micro-pocket fission detector array for real-time, spatial, iron-wire port neutron-flux monitoring
|
Reichenberger, Michael A.
|
|
2017
|
110 |
C |
p. 995-1001
|
artikel
|
| 54 |
Fast spectrum reactor fuel assembly sensitivity analysis
|
Stewart, Ryan
|
|
2017
|
110 |
C |
p. 1091-1097
|
artikel
|
| 55 |
Fast-thermal coupled cores in zero power reactors: A demonstration of feasibility and pertinence for the ZEPHYR project
|
Ros, Paul
|
|
2017
|
110 |
C |
p. 290-305
|
artikel
|
| 56 |
Heat transfer characteristics of oscillating flow in a narrow channel under rolling motion
|
Chen, Chong
|
|
2017
|
110 |
C |
p. 668-678
|
artikel
|
| 57 |
Hermeticity and tensile experiment of small plate-type SiC ceramic composites for advanced reactor applications
|
Zhuo, Weiqian
|
|
2017
|
110 |
C |
p. 1098-1106
|
artikel
|
| 58 |
Heterogeneous neutron-leakage model for PWR pin-by-pin calculation
|
Li, Yunzhao
|
|
2017
|
110 |
C |
p. 443-452
|
artikel
|
| 59 |
High accuracy boronometer design developed for light water reactors
|
Jo, Yunki
|
|
2017
|
110 |
C |
p. 25-30
|
artikel
|
| 60 |
High-fidelity multi-physics coupling for determination of hydride distribution in Zr-4 cladding
|
Davis, Ian
|
|
2017
|
110 |
C |
p. 475-485
|
artikel
|
| 61 |
Immobilization of Cs-trapping ceramic filters within glass-ceramic waste forms
|
Yang, Jae Hwan
|
|
2017
|
110 |
C |
p. 1121-1126
|
artikel
|
| 62 |
Impact of inert gas injection rate on reducing hydrogen risk during AP1000 post-inerting
|
Lyu, Xuefeng
|
|
2017
|
110 |
C |
p. 230-233
|
artikel
|
| 63 |
Implications of alpha-decay for long term storage of advanced heavy water reactor fuels
|
Pencer, J.
|
|
2017
|
110 |
C |
p. 400-405
|
artikel
|
| 64 |
Improving variance estimation in Monte Carlo eigenvalue simulations
|
Jin, Lei
|
|
2017
|
110 |
C |
p. 692-708
|
artikel
|
| 65 |
Investigation on transient behavior of residual heat removal pumps in 1000MW nuclear power plant using a 1D-3D coupling methodology during start-up period
|
Zhou, Banglun
|
|
2017
|
110 |
C |
p. 560-569
|
artikel
|
| 66 |
Key conclusions from UK strategic assessment studies of fast reactor fuel cycles
|
Hesketh, Kevin
|
|
2017
|
110 |
C |
p. 330-337
|
artikel
|
| 67 |
Lattice optimization for graphite moderated molten salt reactors using low-enriched uranium fuel
|
Moser, Dallas
|
|
2017
|
110 |
C |
p. 1-10
|
artikel
|
| 68 |
Manufacturing low enriched uranium metal by magnesiothermic reduction of UF4
|
Durazzo, M.
|
|
2017
|
110 |
C |
p. 874-885
|
artikel
|
| 69 |
Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles
|
Leray, O.
|
|
2017
|
110 |
C |
p. 547-559
|
artikel
|
| 70 |
Minor actinides transmutation on pressurized water reactor burnable poison rods
|
Hu, Wenchao
|
|
2017
|
110 |
C |
p. 222-229
|
artikel
|
| 71 |
Model application research for liquid entrainment through ADS-4 pipe in AP1000
|
Meng, Zhaoming
|
|
2017
|
110 |
C |
p. 1043-1051
|
artikel
|
| 72 |
Module level reliability performance evaluation of digital reactor protection system considering the repair and common cause failure
|
Ma, Zhanguo
|
|
2017
|
110 |
C |
p. 805-817
|
artikel
|
| 73 |
Neutron cross section sensitivity and uncertainty analysis of candidate accident tolerant fuel concepts
|
Burns, Joseph R.
|
|
2017
|
110 |
C |
p. 1249-1255
|
artikel
|
| 74 |
Neutronics feasibility of simple and dry recycling technologies for a self-sustainable breed-and-burn fast reactor
|
Kim, Chihyung
|
|
2017
|
110 |
C |
p. 847-855
|
artikel
|
| 75 |
New calculation method for PWR control rod assemblies with APOLLO3®
|
Jouault, V.
|
|
2017
|
110 |
C |
p. 282-289
|
artikel
|
| 76 |
Nonuniform heat transfer of supercritical water in a tight rod bundle – Assessment of correlations
|
Wang, Han
|
|
2017
|
110 |
C |
p. 570-583
|
artikel
|
| 77 |
Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using SCALE
|
Bostelmann, Friederike
|
|
2017
|
110 |
C |
p. 317-329
|
artikel
|
| 78 |
Nuclear safeguards culture: Roles and responsibilities
|
Elabd, A.A.
|
|
2017
|
110 |
C |
p. 1134-1138
|
artikel
|
| 79 |
Nuclear spent fuel parameter determination using multivariate analysis of fission product gamma spectra
|
Hellesen, C.
|
|
2017
|
110 |
C |
p. 886-895
|
artikel
|
| 80 |
Numerical analysis of different break direction effect on hydrogen behavior in containment during a hypothetical LOCA
|
Wang, D.
|
|
2017
|
110 |
C |
p. 856-864
|
artikel
|
| 81 |
Numerical investigation of flow instability in parallel channels with supercritical water
|
Shitsi, Edward
|
|
2017
|
110 |
C |
p. 196-207
|
artikel
|
| 82 |
Numerical investigation on the effect of shrouds around an immersed isolation condenser on the thermal stratification in large pools
|
Kumar, Sunil
|
|
2017
|
110 |
C |
p. 109-125
|
artikel
|
| 83 |
Online sequential condition prediction method of natural circulation systems based on EOS-ELM and phase space reconstruction
|
Chen, Hanying
|
|
2017
|
110 |
C |
p. 1107-1120
|
artikel
|
| 84 |
On the comparison of two split-step methods for the numerical simulation of stochastic point kinetics equations in presence of Newtonian temperature feedback effects
|
Singh, S.
|
|
2017
|
110 |
C |
p. 865-873
|
artikel
|
| 85 |
Pin-resolved resonance self-shielding methods in LWR direct transport calculations
|
Liu, Yuxuan
|
|
2017
|
110 |
C |
p. 1165-1175
|
artikel
|
| 86 |
Potential impact of accident tolerant fuel cladding critical heat flux characteristics on the high temperature phase of reactivity initiated accidents
|
Liu, Maolong
|
|
2017
|
110 |
C |
p. 48-62
|
artikel
|
| 87 |
Prediction and uncertainty analysis of power peaking factor by cascaded fuzzy neural networks
|
Back, Ju Hyun
|
|
2017
|
110 |
C |
p. 989-994
|
artikel
|
| 88 |
Pre-test CFD simulations of the NACIE-UP BFPS test section
|
Marinari, R.
|
|
2017
|
110 |
C |
p. 1060-1072
|
artikel
|
| 89 |
Process heat applications of HTR-PM600 in Chinese petrochemical industry: Preliminary study of adaptability and economy
|
Fang, Chao
|
|
2017
|
110 |
C |
p. 73-78
|
artikel
|
| 90 |
Proposal for the management strategy of metallic waste from the decommissioning of Kori Unit 1 by using melting and segmentation technology
|
Seo, Hyung-Woo
|
|
2017
|
110 |
C |
p. 633-647
|
artikel
|
| 91 |
Quasi-differential elastic and inelastic neutron scattering from iron in the MeV energy range
|
Daskalakis, A.M.
|
|
2017
|
110 |
C |
p. 603-612
|
artikel
|
| 92 |
RAMI comparison of two China test blanket modules
|
Jin, Xingbo
|
|
2017
|
110 |
C |
p. 438-442
|
artikel
|
| 93 |
Recent advances in the treatment of irradiated graphite: A review
|
Li, Junfeng
|
|
2017
|
110 |
C |
p. 140-147
|
artikel
|
| 94 |
Recovery of boric acid from the simulated radioactive wastewater by vacuum membrane distillation crystallization
|
Jia, Fei
|
|
2017
|
110 |
C |
p. 1148-1155
|
artikel
|
| 95 |
Reference level of the occupational radiation exposure in a deep geological disposal facility for high-level nuclear waste: A Monte Carlo study
|
Pang, Bo
|
|
2017
|
110 |
C |
p. 258-264
|
artikel
|
| 96 |
Safety evaluation of supercritical CO2 cooled micro modular reactor
|
Oh, Bong Seong
|
|
2017
|
110 |
C |
p. 1202-1216
|
artikel
|
| 97 |
Safety studies for the MYRRHA critical core with the SIMMER-III code
|
Chen, X-N.
|
|
2017
|
110 |
C |
p. 1030-1042
|
artikel
|
| 98 |
Sensitivity and uncertainty analysis for ULOF of PGSFR using PAPIRUS
|
Kang, Sarah
|
|
2017
|
110 |
C |
p. 1232-1241
|
artikel
|
| 99 |
SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data
|
Michel-Sendis, F.
|
|
2017
|
110 |
C |
p. 779-788
|
artikel
|
| 100 |
Silver phosphate glasses for immobilization of radioactive iodine
|
Yang, Jae Hwan
|
|
2017
|
110 |
C |
p. 208-214
|
artikel
|
| 101 |
Simplified load follow schemes to simulate long-term daily load follow operation
|
Rakereng, Okaeng Patrick
|
|
2017
|
110 |
C |
p. 896-902
|
artikel
|
| 102 |
Simulated response to process abnormalities during spent nuclear fuel electrorefining
|
Adams, Shannon
|
|
2017
|
110 |
C |
p. 1002-1009
|
artikel
|
| 103 |
Software hazard analysis for nuclear digital protection system by Colored Petri Net
|
Bai, Tao
|
|
2017
|
110 |
C |
p. 486-491
|
artikel
|
| 104 |
Spatial modes for the neutron diffusion equation and their computation
|
Carreño, A.
|
|
2017
|
110 |
C |
p. 1010-1022
|
artikel
|
| 105 |
Station black out concurrent with PORV failure using a Generic Pressurized Water Reactor simulator
|
Zubair, Muhammad
|
|
2017
|
110 |
C |
p. 1081-1090
|
artikel
|
| 106 |
Study of the possibility of using Europium and Pyrex alloy as burnable absorber in PWR
|
Galahom, A. Abdelghafar
|
|
2017
|
110 |
C |
p. 1127-1133
|
artikel
|
| 107 |
The calculation of the reactivity by the telegraph equation
|
Palma, Daniel A.P.
|
|
2017
|
110 |
C |
p. 31-35
|
artikel
|
| 108 |
The Doppler Broadening Function using the Kaniadakis distribution
|
Guedes, Guilherme
|
|
2017
|
110 |
C |
p. 453-458
|
artikel
|
| 109 |
The effect of homogenization on the neutronic parameters and transmutation of GFR-2400 fast reactor fuel assembly
|
Ibrahim, Amr
|
|
2017
|
110 |
C |
p. 215-221
|
artikel
|
| 110 |
The influence of blade configuration on cavitation performance of a condensate pump
|
Kang, Can
|
|
2017
|
110 |
C |
p. 789-797
|
artikel
|
| 111 |
The influence of nuclear graphite oxidation on air ingress accident of HTR-PM
|
Xu, Wei
|
|
2017
|
110 |
C |
p. 1242-1248
|
artikel
|
| 112 |
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