| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A deep-learning representation of multi-group cross sections in lattice calculations
|
Chan, Yi Meng
|
|
|
195 |
C |
p.
|
artikel
|
| 2 |
A gamma spectroscopy-based non-destructive approach for pebble bed reactor safeguards
|
Mulyana, Dany
|
|
|
195 |
C |
p.
|
artikel
|
| 3 |
A high-order and efficient numerical technique for the nonlocal neutron diffusion equation representing neutron transport in a nuclear reactor
|
Wang, Wan
|
|
|
195 |
C |
p.
|
artikel
|
| 4 |
A method for predicting the breakup of gas column in a decaying swirling liquid field
|
Zhang, Jiarong
|
|
|
195 |
C |
p.
|
artikel
|
| 5 |
Analysis of a parallel-channel natural circulation loop in the passive residual heat removal system of the NHR200-II reactor
|
Yiwa, Geng
|
|
|
195 |
C |
p.
|
artikel
|
| 6 |
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad
|
Ihn, Namgung
|
|
|
195 |
C |
p.
|
artikel
|
| 7 |
Assessment of cladding ballooning during DBA-LOCAs with FRAPTRAN
|
Feria, F.
|
|
|
195 |
C |
p.
|
artikel
|
| 8 |
A thermal-hydraulic and control model for a Pb-Bi micro reactor
|
Lu, Shuaijie
|
|
|
195 |
C |
p.
|
artikel
|
| 9 |
Atmospheric 137Cs dispersion following the Fukushima Daiichi nuclear accident: Local-scale simulations using CALMET and LAPMOD
|
Yang, Li
|
|
|
195 |
C |
p.
|
artikel
|
| 10 |
Boundary dependent physics-informed neural network for solving neutron transport equation
|
Xie, Yuchen
|
|
|
195 |
C |
p.
|
artikel
|
| 11 |
Coded-Aperture imaging based on random code and Backpropagation neural network
|
Wang, Zeyu
|
|
|
195 |
C |
p.
|
artikel
|
| 12 |
Comparison of BANDI-60 core designs using Pyrex burnable absorber and annular fuel embedding gadolinia wire
|
Kim, Dokyun
|
|
|
195 |
C |
p.
|
artikel
|
| 13 |
Computation time reduction of nuclear fuel burnup calculations with the predictor–corrector method using low-order model
|
Miyazawa, Fuga
|
|
|
195 |
C |
p.
|
artikel
|
| 14 |
Cross-scale coupling analysis method for OTSG in SFR and its application
|
Zhang, Zhenguo
|
|
|
195 |
C |
p.
|
artikel
|
| 15 |
Design on cladding of central measuring shroud against thermal shock in FR based on elastoplastic model
|
Zheng, Shu
|
|
|
195 |
C |
p.
|
artikel
|
| 16 |
Development and benchmarking of SIMULATE5-K-VVER
|
Dawn, William C.
|
|
|
195 |
C |
p.
|
artikel
|
| 17 |
Development of a clogging probability model in simplified geometry for fast reactor flow blockage analysis
|
Cheng, Songbai
|
|
|
195 |
C |
p.
|
artikel
|
| 18 |
Development of a formulation to predict molten core spreading in an LWR severe accident
|
Sahboun, Nassim
|
|
|
195 |
C |
p.
|
artikel
|
| 19 |
Development of online validation and monitoring system for the thermal performance of nuclear power plant in service
|
Zhang, Xun
|
|
|
195 |
C |
p.
|
artikel
|
| 20 |
Direct simulation method for estimating the concentration of nuclides undergoing transmutations
|
Omar, M.R.
|
|
|
195 |
C |
p.
|
artikel
|
| 21 |
Dynamic simulation of SMR steam turbine speed response in an isolated network mode of distributed energy resources microgrids
|
Wang, Jieling
|
|
|
195 |
C |
p.
|
artikel
|
| 22 |
Editorial Board
|
|
|
|
195 |
C |
p.
|
artikel
|
| 23 |
Effects of multi-recycling of uranium reprocessed from spent nuclear fuel on the proliferation resistance of plutonium and uranium
|
Saito, Masaki
|
|
|
195 |
C |
p.
|
artikel
|
| 24 |
Evaluation on 131I production based on molten salt reactor off-gas extraction
|
Chen, Liang
|
|
|
195 |
C |
p.
|
artikel
|
| 25 |
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement
|
Zhu, Weicong
|
|
|
195 |
C |
p.
|
artikel
|
| 26 |
Experimental and numerical study of an innovative twined tube HX design
|
Ali Khan, Muhammad
|
|
|
195 |
C |
p.
|
artikel
|
| 27 |
Geometric optimization of a novel passive flow limiter for nuclear heating reactors
|
Song, Lei
|
|
|
195 |
C |
p.
|
artikel
|
| 28 |
High-fidelity simulations of the run-in process for a pebble-bed reactor
|
Stewart, Ryan
|
|
|
195 |
C |
p.
|
artikel
|
| 29 |
High-temperature rupture failure of high-burnup LWR-MOX fuel under a reactivity-initiated accident condition
|
Taniguchi, Yoshinori
|
|
|
195 |
C |
p.
|
artikel
|
| 30 |
Inverted fuel geometry implementation for a fast reactor: Potential improvements in neutronic and thermalhydraulic performance
|
Khandaq, Muhammad Farid
|
|
|
195 |
C |
p.
|
artikel
|
| 31 |
Methods for the radioactive release estimation under DEC-A conditions
|
Kaliatka, Tadas
|
|
|
195 |
C |
p.
|
artikel
|
| 32 |
Minimal requirements to thermal-hydraulics/3D-neutron kinetics clustering for BWR transient analysis
|
Nikitin, K.
|
|
|
195 |
C |
p.
|
artikel
|
| 33 |
Minimum dose path planning method for virtual nuclear facilities based on navigation mesh
|
Zheng, Anran
|
|
|
195 |
C |
p.
|
artikel
|
| 34 |
Model-free adaptive control of average coolant temperature in a novel marine small lead–bismuth-cooled reactor
|
Qian, Hong
|
|
|
195 |
C |
p.
|
artikel
|
| 35 |
Monte Carlo analysis of BWR geometries using a cycle check-up methodology
|
Hursin, Mathieu
|
|
|
195 |
C |
p.
|
artikel
|
| 36 |
Multiphase simulation of hyperbaric steam-water jet inside liquid Pb-Bi eutectic environment
|
Yu, Qifan
|
|
|
195 |
C |
p.
|
artikel
|
| 37 |
Noise term modeling of dynamic Monte Carlo using stochastic differential equations
|
Hajas, Tamas Zoltan
|
|
|
195 |
C |
p.
|
artikel
|
| 38 |
Nonlinear analysis of coupled neutronic-thermohydraulic stability characteristics of supercritical water-cooled reactor
|
Shankar, Daya
|
|
|
195 |
C |
p.
|
artikel
|
| 39 |
Numerical investigation of air–steam condensation in a vertically enhanced tube with dimples and protrusions
|
Zheng, Jiyu
|
|
|
195 |
C |
p.
|
artikel
|
| 40 |
Numerical investigation on characteristics of the onset of nucleate boiling in petal-shape fuel rod bundle assembly
|
Du, Lipeng
|
|
|
195 |
C |
p.
|
artikel
|
| 41 |
Numerical simulation of the early startup period of heat pipe cooled reactor system from the room temperature state
|
Guo, Yuchuan
|
|
|
195 |
C |
p.
|
artikel
|
| 42 |
Prediction of spent nuclear fuel isotopic composition for the VVER-1000 reactor utilizing regression tree
|
Tarequzzaman, Md.
|
|
|
195 |
C |
p.
|
artikel
|
| 43 |
Radial basis function neural network controller for power control of molten salt breeder reactor of nuclear power plant
|
Naha, Sulakshan
|
|
|
195 |
C |
p.
|
artikel
|
| 44 |
Remote dismantling system using a digital manufacturing system and workpiece localization for nuclear facility decommissioning
|
Hyun, Dongjun
|
|
|
195 |
C |
p.
|
artikel
|
| 45 |
Research on neutron diffusion equation and nuclear thermal coupling method based on gradient updating finite volume method
|
Li, Xiangyu
|
|
|
195 |
C |
p.
|
artikel
|
| 46 |
Selection of a nickel-specific DNA aptamer and development of a protocol for radioactive nickel removal
|
Hyuk Jang, Dae
|
|
|
195 |
C |
p.
|
artikel
|
| 47 |
Simulation of the effect of pulsatile flow on flow features dynamics during abrupt contraction into two parallel rectangular jets
|
Ala, Ayodeji A.
|
|
|
195 |
C |
p.
|
artikel
|
| 48 |
Sloshing damping assessment and structural dynamic analysis of perforated structures for heavy liquid metal under seismic excitation
|
Chen, Yalou
|
|
|
195 |
C |
p.
|
artikel
|
| 49 |
Solution of nonlinear fractional-order models of nuclear reactor with parallel computing: Implementation on GPU platform
|
Keluskar, Yugesh C.
|
|
|
195 |
C |
p.
|
artikel
|
| 50 |
Subcritical neutron noise measurements for plutonium systems with varying geometry and mass
|
Hutchinson, Jesson
|
|
|
195 |
C |
p.
|
artikel
|
| 51 |
UA-CRD, a computational framework for uncertainty analysis of control rod drop with time-variant epistemic uncertain parameters
|
Yang, Yuxiang
|
|
|
195 |
C |
p.
|
artikel
|
| 52 |
Underlying mathematical relations for efficient COMET response expansion coefficient and core calculations
|
Zhang, Dingkang
|
|
|
195 |
C |
p.
|
artikel
|
| 53 |
Validation of the fast reactor plant dynamics analysis code Super-COPD using FFTF loss of flow without scram test #13
|
Hamase, Erina
|
|
|
195 |
C |
p.
|
artikel
|
| 54 |
WWR-K reactor LEU core design optimization for improving the experimental characteristics
|
Shaimerdenov, A.
|
|
|
195 |
C |
p.
|
artikel
|
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