| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A Bayesian approach for probabilistic safety assessment of HLW repository
|
Lee, Youn-Myoung
|
|
|
138 |
C |
p.
|
artikel
|
| 2 |
Analysis of loss of cooling and loss of coolant severe accident scenarios in VVER-1000/V446 spent fuel pool
|
Omidifard, P.
|
|
|
138 |
C |
p.
|
artikel
|
| 3 |
An application study of response surface method on axial gadolinium designs of BWR fuel assemblies
|
Tung, Wu-Hsiung
|
|
|
138 |
C |
p.
|
artikel
|
| 4 |
An artificial neural network based neutron field reconstruction method for reactor
|
Pei, Cao
|
|
|
138 |
C |
p.
|
artikel
|
| 5 |
An efficient Monte Carlo fission source convergence acceleration strategy adapted from the survival biasing technique
|
Omar, M.R.
|
|
|
138 |
C |
p.
|
artikel
|
| 6 |
A new procedure for solving neutron transfer problems
|
Tang, Jiannan
|
|
|
138 |
C |
p.
|
artikel
|
| 7 |
A Rayleigh quotient method for criticality eigenvalue problems in neutron transport
|
Ortega, M.I.
|
|
|
138 |
C |
p.
|
artikel
|
| 8 |
Assessment of the fractional neutron point kinetic equation to simulate core transients with Newtonian temperature feedback
|
Polo-Labarrios, M.A.
|
|
|
138 |
C |
p.
|
artikel
|
| 9 |
Asymptotic convergence of the angular discretization error in the scalar flux computed from the particle transport equation with the method of discrete ordinates
|
Hu, Xiaoyu
|
|
|
138 |
C |
p.
|
artikel
|
| 10 |
A theoretical and experimental study on subcooled flow boiling under passive IVR-ERVC conditions
|
Wang, Fan
|
|
|
138 |
C |
p.
|
artikel
|
| 11 |
Best estimate plus uncertainty analysis of small break loss of coolant accidents with different break sizes for CPR1000
|
Xiong, Qingwen
|
|
|
138 |
C |
p.
|
artikel
|
| 12 |
Comparison of the performance of heterogeneous variational nodal method and 2D/1D-MOC on pin-resolved neutron transport calculations of PWR
|
Wang, Yongping
|
|
|
138 |
C |
p.
|
artikel
|
| 13 |
Construction and quantification of a fire probabilistic safety assessment model using support system initiating event fault trees
|
Jung, Yong Hun
|
|
|
138 |
C |
p.
|
artikel
|
| 14 |
Covariance comparisons between ENDF/B-VII.1 and ENDF/B-VIII.0 with application for the UAM-LWR exercises
|
Wan, Chenghui
|
|
|
138 |
C |
p.
|
artikel
|
| 15 |
Design of a Small Modular Nuclear Reactor with dual cooled annular fuel and investigation of the fuel inner radius effect on the power peaking factor and natural circulation parameters
|
Zaidabadi Nejad, M.
|
|
|
138 |
C |
p.
|
artikel
|
| 16 |
Detection of subcriticality changes by Simmons-King and Sjöstrand methods
|
Kitamura, Yasunori
|
|
|
138 |
C |
p.
|
artikel
|
| 17 |
Development and assessment of a new rod-bundle CHF correlation for China fuel assemblies
|
Liu, Wei
|
|
|
138 |
C |
p.
|
artikel
|
| 18 |
Development and validation of the depletion capability of the high-fidelity neutronics code NECP-X
|
Wen, Xingjian
|
|
|
138 |
C |
p.
|
artikel
|
| 19 |
Development and validation of thermo-mechanical analysis code of metallic fuel under steady-state conditions in LMFR
|
Sun, Hongping
|
|
|
138 |
C |
p.
|
artikel
|
| 20 |
Development of phenomena identification and ranking tables (PIRTs) to implement research reactor-specific capability in SPACE code
|
Kim, Hyeonil
|
|
|
138 |
C |
p.
|
artikel
|
| 21 |
Diagnosis of operational failures and on-demand failures in nuclear power plants: An approach based on dynamic Bayesian networks
|
Zhao, Yunfei
|
|
|
138 |
C |
p.
|
artikel
|
| 22 |
Dimensioning of the emergency draining tank for a molten salt reactor through analytical modeling
|
Massone, M.
|
|
|
138 |
C |
p.
|
artikel
|
| 23 |
Dynamic characteristics of the capacitance control rod position measurement sensor system in NHR-200
|
Hu, Guang
|
|
|
138 |
C |
p.
|
artikel
|
| 24 |
Editorial Board
|
|
|
|
138 |
C |
p.
|
artikel
|
| 25 |
Exergy analysis of supersonic steam jet condensed into subcooled water
|
Li, Wenjun
|
|
|
138 |
C |
p.
|
artikel
|
| 26 |
Experimental and theoretical research on the effect of branch size on the gas entrainment
|
Shen, Geyu
|
|
|
138 |
C |
p.
|
artikel
|
| 27 |
Experimental research on heat transfer behavior of large scale two-layer salt melt pool based on COPRA facility
|
Zhou, Yukun
|
|
|
138 |
C |
p.
|
artikel
|
| 28 |
Experimental study on sloshing characteristics in a pool with stratified liquids
|
Cheng, Songbai
|
|
|
138 |
C |
p.
|
artikel
|
| 29 |
Fuel performance analysis of BEAVRS benchmark Cycle 1 depletion with MCS/FRAPCON coupled system
|
Yu, Jiankai
|
|
|
138 |
C |
p.
|
artikel
|
| 30 |
Introduction to the non-orthogonal gradient-based finite volume method for three-dimensional neutron diffusion calculations with application to the rectangular reactor core configurations
|
Vagheian, Mehran
|
|
|
138 |
C |
p.
|
artikel
|
| 31 |
Investigation of thermosyphon characteristics in a vertical narrow annulus closed at top with external forced convection cooling
|
Xiao, Yao
|
|
|
138 |
C |
p.
|
artikel
|
| 32 |
Irradiation tensile property and fracture toughness evaluation study of A508-3 steel based on multi-scale approach
|
Liu, Yunpeng
|
|
|
138 |
C |
p.
|
artikel
|
| 33 |
Least squares linear source approach in method of characteristics
|
Liang, Liang
|
|
|
138 |
C |
p.
|
artikel
|
| 34 |
Modeling and simulation of feedwater control system with multiple once-through steam generators in a sodium-cooled fast reactor (I): Dynamic model development
|
Sun, Peiwei
|
|
|
138 |
C |
p.
|
artikel
|
| 35 |
Modelling guidelines for safety analysis of Station Black Out sequences based on experiments at the PKL test facility
|
Freixa, J.
|
|
|
138 |
C |
p.
|
artikel
|
| 36 |
Monte Carlo shielding design with a large perturbation calculation method
|
Tan, Wanbin
|
|
|
138 |
C |
p.
|
artikel
|
| 37 |
Nuclear data sensitivity and uncertainty analysis of critical VENUS-F cores with the Serpent Monte Carlo code
|
Fridman, E.
|
|
|
138 |
C |
p.
|
artikel
|
| 38 |
Numerical study on the thermal stratification characteristics in the upper plenum of sodium-cooled fast reactor (SFR)
|
Wang, Mingjun
|
|
|
138 |
C |
p.
|
artikel
|
| 39 |
One-dimensional ex-vessel coolability analysis of debris beds formed in OPR1000 pre-flooded reactor cavity
|
Na, Hanbee
|
|
|
138 |
C |
p.
|
artikel
|
| 40 |
One-dimensional model of hydrogen distribution in confined space based on Froude number
|
Tong, L.L.
|
|
|
138 |
C |
p.
|
artikel
|
| 41 |
Parametric studies on startup transients in multiple parallel channels of a natural circulation boiling system
|
Saikia, Kiran
|
|
|
138 |
C |
p.
|
artikel
|
| 42 |
Razorback – A reactor transient analysis code for large rapid reactivity additions in a natural circulation research reactor
|
Talley, Darren G.
|
|
|
138 |
C |
p.
|
artikel
|
| 43 |
RELAP5/MOD3.4 calculation and model evaluation based on upper plenum entrainment experiment in AP1000
|
Song, Gongle
|
|
|
138 |
C |
p.
|
artikel
|
| 44 |
Research of quasi 2-D refined simulation and modeling for deaerator in nuclear power plant
|
Gong, Meijie
|
|
|
138 |
C |
p.
|
artikel
|
| 45 |
Response function generation for Cerenkov radiation production and transport in a TRIGA coolant channel
|
Hearne, Jason A.
|
|
|
138 |
C |
p.
|
artikel
|
| 46 |
Self-shielding effect of double heterogeneity for plutonium burner HTGR design
|
Fukaya, Y.
|
|
|
138 |
C |
p.
|
artikel
|
| 47 |
Semi-empirical analysis of the spatial variation of Pu quality ratio in a reactor core for application in pyroprocessing of used nuclear fuel
|
Min Woo, Seung
|
|
|
138 |
C |
p.
|
artikel
|
| 48 |
Sensitivity of an (α,n) neutron source to (α,n) cross sections and stopping powers
|
Favorite, Jeffrey A.
|
|
|
138 |
C |
p.
|
artikel
|
| 49 |
Study of the impact of decay heat on the in-containment temperature and pressure evolution following a hypothetical severe accident in a SFR
|
Patel, Parthkumar Rajendrabhai
|
|
|
138 |
C |
p.
|
artikel
|
| 50 |
Study of transmutation, gas production, and displacement damage in chromium for fusion neutron spectrum
|
Rajput, Mayank
|
|
|
138 |
C |
p.
|
artikel
|
| 51 |
Thermo kinetic studies on chemical denitration of simulated waste solution
|
Mishra, Satyabrata
|
|
|
138 |
C |
p.
|
artikel
|
| 52 |
Transition to thorium fuel cycle in a small modular molten salt reactor based on a batch reprocessing mode
|
Zou, Chunyan
|
|
|
138 |
C |
p.
|
artikel
|
| 53 |
Treatment of the implicit effect in Shark-X
|
Hursin, Mathieu
|
|
|
138 |
C |
p.
|
artikel
|
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