nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
Accident tolerant fuel thermal hydraulic behaviors evaluation during loss of coolant accident in CPR1000
|
Yu, Honghao |
|
|
139 |
C |
p. |
artikel |
2 |
A fuzzy-PID composite controller for core power control of liquid molten salt reactor
|
Zeng, Wenjie |
|
|
139 |
C |
p. |
artikel |
3 |
A methodology for digital mockup update based on the 3D scanned spatial information for the automated dismantling of nuclear facilities
|
Kim, Ikjune |
|
|
139 |
C |
p. |
artikel |
4 |
Analytical study of SPERT-CDC test 859 using fuel performance codes FEMAXI-8 and RANNS
|
Taniguchi, Yoshinori |
|
|
139 |
C |
p. |
artikel |
5 |
An experimental study of two-phase flow instability in a multi-loop natural circulation system
|
Abbati, Zahraddeen |
|
|
139 |
C |
p. |
artikel |
6 |
Anomalous reactivity swing in the 238U-233U system
|
Wallenius, Janne |
|
|
139 |
C |
p. |
artikel |
7 |
Application of Cuckoo Search algorithm to Loading Pattern Optimization problems
|
Meneses, Anderson Alvarenga de Moura |
|
|
139 |
C |
p. |
artikel |
8 |
A Serpent2-SUBCHANFLOW-TRANSURANUS coupling for pin-by-pin depletion calculations in Light Water Reactors
|
García, Manuel |
|
|
139 |
C |
p. |
artikel |
9 |
Assembly pin factor parameterization method based on the proper orthogonal decomposition
|
Li, Zhuo |
|
|
139 |
C |
p. |
artikel |
10 |
A subgroup method based on the equivalent Dancoff-factor cell technique in APOLLO3® for thermal reactor calculations
|
Mao, Li |
|
|
139 |
C |
p. |
artikel |
11 |
A two-step neutron spectrum unfolding method for fission reactors based on artificial neural network
|
Cao, Chenglong |
|
|
139 |
C |
p. |
artikel |
12 |
Basic design parameter optimization on water cooled thorium breeder reactor
|
Permana, Sidik |
|
|
139 |
C |
p. |
artikel |
13 |
Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo
|
Alhassan, E. |
|
|
139 |
C |
p. |
artikel |
14 |
Benchmark calculations for verification of thermo-fluid analysis codes using simplified model of the OECD/NEA MHTGR-350 core design
|
Lee, Sung Nam |
|
|
139 |
C |
p. |
artikel |
15 |
Deep learning approach to nuclear fuel transmutation in a fuel cycle simulator
|
Bae, Jin Whan |
|
|
139 |
C |
p. |
artikel |
16 |
Design and analysis of improved two-phase natural circulation systems with thermoelectric generator
|
Wang, Dongqing |
|
|
139 |
C |
p. |
artikel |
17 |
Development and validation of a coupled neutron diffusion-thermal hydraulic calculation procedure for fast reactor applications
|
Zhang, Xuebei |
|
|
139 |
C |
p. |
artikel |
18 |
Editorial Board
|
|
|
|
139 |
C |
p. |
artikel |
19 |
Effect of diamond additive on the fission gas release in UO2 fuel irradiated to 7.2 GWd/tHM
|
Medvedev, Pavel |
|
|
139 |
C |
p. |
artikel |
20 |
ERMSAR 2019 conference of NUGENIA TA2/SARNET on research on severe accidents in nuclear power plants
|
Herranz, Luís Enrique |
|
|
139 |
C |
p. |
artikel |
21 |
Experimental investigation on condensation heat transfer for bundle tube heat exchanger of the PCCS (Passive Containment Cooling System)
|
Bae, Byoung-Uhn |
|
|
139 |
C |
p. |
artikel |
22 |
Experimental study on eutectic reaction between fuel debris and reactor structure using simulant materials
|
Xiong, Zhihong |
|
|
139 |
C |
p. |
artikel |
23 |
Experimental study on the vibration behavior of the pebble bed in PB-FHR
|
Chen, Xingwei |
|
|
139 |
C |
p. |
artikel |
24 |
Fitting-based resonance database method for resonance self-shielding calculations of large-scale task considering depletion and intra-pin distribution
|
Qin, Shuai |
|
|
139 |
C |
p. |
artikel |
25 |
Global sensitivity analysis of LOFT large break loss of coolant accident with optimized moment-independent method
|
Xiong, Qingwen |
|
|
139 |
C |
p. |
artikel |
26 |
Impact of grain size on performance degradation of TREAT LEU
|
Schunert, Sebastian |
|
|
139 |
C |
p. |
artikel |
27 |
Implementation and performance study of lpCMFD acceleration method for multi-energy group k-eigenvalue neutron transport problem in hexagonal geometry
|
Chan, Yimeng |
|
|
139 |
C |
p. |
artikel |
28 |
Investigation of LBLOCA in VVER-1000 NPP using RELAP5/SCDAP and CONTAIN codes
|
Salehi, Mohsen |
|
|
139 |
C |
p. |
artikel |
29 |
Linear optimization for predicting material compositions in molten salt reactors
|
Wooten, Daniel |
|
|
139 |
C |
p. |
artikel |
30 |
Management of loss of offsite power avoiding reactor trip
|
Kim, Sungkyum |
|
|
139 |
C |
p. |
artikel |
31 |
MCS – A Monte Carlo particle transport code for large-scale power reactor analysis
|
Lee, Hyunsuk |
|
|
139 |
C |
p. |
artikel |
32 |
MCS/TH1D analysis of VERA whole-core multi-cycle depletion problems
|
Nguyen, Tung Dong Cao |
|
|
139 |
C |
p. |
artikel |
33 |
Measurement and analysis of neutron leakage spectrum in depleted Uranium-Polyethylene Mock-up
|
Lu, Xinxin |
|
|
139 |
C |
p. |
artikel |
34 |
MLEM reconstruction method applied to partial defect verification using simulated data
|
Shiba, Shigeki |
|
|
139 |
C |
p. |
artikel |
35 |
Modeling uncertainty of instrument and control system of nuclear power plant
|
Kaur, Raj kamal |
|
|
139 |
C |
p. |
artikel |
36 |
New delayed neutron group constants and covariances for LWR core applications, combining summation calculations and integral experiments
|
Leconte, P. |
|
|
139 |
C |
p. |
artikel |
37 |
Non-intrusive detection of gas–water interface in circular pipes inclined at various angles
|
Jo, Hongrae |
|
|
139 |
C |
p. |
artikel |
38 |
Optimal time step length and statistics in Monte Carlo burnup simulations
|
Dufek, Jan |
|
|
139 |
C |
p. |
artikel |
39 |
Pre-CHF boiling heat transfer performance on tube bundles with or without enhanced surfaces - a review
|
Ren, Shuai |
|
|
139 |
C |
p. |
artikel |
40 |
Prediction of unmeasurable parameters of NPPs using different model-free methods based on cross-correlation detection of measurable/unmeasurable parameters: A comparative study
|
Moshkbar-Bakhshayesh, Khalil |
|
|
139 |
C |
p. |
artikel |
41 |
Recent measurements on plutonium-thorium fuel by substitution experiments in the ZED-2 critical facility
|
Adams, F.P. |
|
|
139 |
C |
p. |
artikel |
42 |
Stability analysis and parametric study of natural circulation integrated self-pressurized water reactor
|
Pilehvar, A.F. |
|
|
139 |
C |
p. |
artikel |
43 |
Study of the PWR ex-core detector response simulation based on the 3D S N method
|
Xu, Longfei |
|
|
139 |
C |
p. |
artikel |
44 |
Study on strip-shaped liquid film in the corrugated plate dryer
|
Wang, Bo |
|
|
139 |
C |
p. |
artikel |
45 |
The effect of base irradiation on failure behaviors of UO2 and chromia-alumina additive fuels under simulated reactivity-initiated accidents: A comparative analysis with FEMAXI-8
|
Udagawa, Yutaka |
|
|
139 |
C |
p. |
artikel |
46 |
The safety improvement of VVER-1000 NPP against SBO accident using portable air-cooled diesel generator
|
Jabbari, M. |
|
|
139 |
C |
p. |
artikel |
47 |
The unified model for irradiation embrittlement prediction of reactor pressure vessel
|
Li, Chengliang |
|
|
139 |
C |
p. |
artikel |
48 |
Three-dimensional thermal hydraulic transient calculation of coupled cold and hot sodium pools under a loss of feedwater accident in the China experimental fast reactor
|
Xia, Zihan |
|
|
139 |
C |
p. |
artikel |
49 |
Toward the implementation of self-powered, wireless, real-time reactor power sensing
|
Turso, James |
|
|
139 |
C |
p. |
artikel |
50 |
Uncertainty quantification of fuel pebble model and its effect on the uncertainty propagation of nuclear data in pebble bed HTR
|
Cheng, Youying |
|
|
139 |
C |
p. |
artikel |
51 |
Validation of actinide nuclear data based on reactivity worth experiments in a MOX-LWR spectrum
|
Leconte, P. |
|
|
139 |
C |
p. |
artikel |
52 |
Water hammer analysis when switching of parallel pumps based on contra-motion check valve
|
Yang, Zhida |
|
|
139 |
C |
p. |
artikel |
53 |
Whole-core depletion calculation using domain decomposed continuous-energy Monte Carlo simulation via McBOX with p-CMFD acceleration and inline feedback
|
Jo, YuGwon |
|
|
139 |
C |
p. |
artikel |