| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accelerated polynomial axial expansions for full 3D neutron transport MOC in the APOLLO3® code system as applied to the ASTRID fast breeder reactor
|
Santandrea, Simone
|
|
2018
|
113 |
C |
p. 194-236
|
artikel
|
| 2 |
Accuracy and analysis of the iteratively coupling 2D/3D method for the three-dimensional transport calculations
|
Liu, Zhouy
|
|
2018
|
113 |
C |
p. 130-138
|
artikel
|
| 3 |
AETIUS solutions for Kobayashi 3D benchmarks with the first collision source method on the volume source and unstructured tetrahedral mesh
|
Kim, Jong Woon
|
|
2018
|
113 |
C |
p. 446-469
|
artikel
|
| 4 |
Analysis of delayed neutrons’ contribution for the maximum to average flux ratio in an annular pulsed reactor by Finite Volume Method
|
da Silva, Mário Augusto Bezerra
|
|
2018
|
113 |
C |
p. 118-121
|
artikel
|
| 5 |
Analysis on hydrogen control system in AP1000 NPP
|
Lyu, Xuefeng
|
|
2018
|
113 |
C |
p. 279-285
|
artikel
|
| 6 |
A new model with Serpent for the first criticality benchmarks of the TRIGA Mark II reactor
|
Castagna, Christian
|
|
2018
|
113 |
C |
p. 171-176
|
artikel
|
| 7 |
An improved simplified method of evaluating severe accident source term in the containment of AP1000
|
Sun, Xiaohui
|
|
2018
|
113 |
C |
p. 55-64
|
artikel
|
| 8 |
Artificial neural network approximations of linear fractional neutron models
|
Vyawahare, Vishwesh A.
|
|
2018
|
113 |
C |
p. 75-88
|
artikel
|
| 9 |
Assessment of primary and secondary bleed and feed procedures during a Station Blackout in a German Konvoi PWR using ASTECV2.0
|
Gómez-García-Toraño, Ignacio
|
|
2018
|
113 |
C |
p. 476-492
|
artikel
|
| 10 |
Beta-effective sensitivity and uncertainty analysis of MYRRHA reactor for possible use in nuclear data validation and improvement
|
Kodeli, Ivan A.
|
|
2018
|
113 |
C |
p. 425-435
|
artikel
|
| 11 |
CALLISTO-SPK: A Stochastic Point Kinetics code for performing low source nuclear power plant start-up and power ascension calculations
|
Cooling, C.M.
|
|
2018
|
113 |
C |
p. 319-331
|
artikel
|
| 12 |
CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor
|
Chen, Jing
|
|
2018
|
113 |
C |
p. 256-269
|
artikel
|
| 13 |
Concentration-dependent activity coefficients of lanthanides in liquid bismuth for the FHR primary coolant cleanup
|
Wang, Yafei
|
|
2018
|
113 |
C |
p. 89-95
|
artikel
|
| 14 |
Criticality and uncertainty assessment of assembly misloading in BWR transportation cask
|
Radaideh, Majdi I.
|
|
2018
|
113 |
C |
p. 1-14
|
artikel
|
| 15 |
Development and validation of the BERKUT fuel rod module of the EUCLID/V1 integrated computer code
|
Veprev, D.P.
|
|
2018
|
113 |
C |
p. 237-245
|
artikel
|
| 16 |
Development of a new empirical correlation for steam condensation rates in the presence of air outside vertical smooth tube
|
Fan, Guangming
|
|
2018
|
113 |
C |
p. 139-146
|
artikel
|
| 17 |
Discontinuous Galerkin spatial discretisation of the neutron transport equation with pyramid finite elements and a discrete ordinate (SN) angular approximation
|
O’Malley, B.
|
|
2018
|
113 |
C |
p. 526-535
|
artikel
|
| 18 |
Editorial Board
|
|
|
2018
|
113 |
C |
p. ii
|
artikel
|
| 19 |
Effects of downward-facing surface type and inclination on critical heat flux during pool boiling
|
Gong, H.
|
|
2018
|
113 |
C |
p. 344-352
|
artikel
|
| 20 |
Evaluation of an accident management strategy using an emergency water injection in a reference PWR SFP
|
Ahn, Kwang-Il
|
|
2018
|
113 |
C |
p. 353-379
|
artikel
|
| 21 |
Experimental investigation of boiling heat transfer in helically coiled tubes at high pressure
|
Xiao, Yao
|
|
2018
|
113 |
C |
p. 409-419
|
artikel
|
| 22 |
Fault detection, identification and reconstruction of sensors in nuclear power plant with optimized PCA method
|
Li, Wei
|
|
2018
|
113 |
C |
p. 105-117
|
artikel
|
| 23 |
Four-bar linkage modeling and kinematics analysis of an in-vessel transfer system for Prototype Gen-IV Sodium-cooled Fast Reactor
|
Lim, Dong-Won
|
|
2018
|
113 |
C |
p. 493-505
|
artikel
|
| 24 |
Fourier analysis of the RELAP5/3D adaptive time-stepping scheme on a natural circulation loop
|
Braz Filho, Francisco A.
|
|
2018
|
113 |
C |
p. 65-74
|
artikel
|
| 25 |
“High risk non-initiating insider” identification based on EEG analysis for enhancing nuclear security
|
Suh, Young-A
|
|
2018
|
113 |
C |
p. 308-318
|
artikel
|
| 26 |
Investigation of droplet behaviors for spray cooling using level set method
|
Shahmohammadi Beni, Mehrdad
|
|
2018
|
113 |
C |
p. 162-170
|
artikel
|
| 27 |
Investigation of thermal hydraulic behavior of SBLOCA tests in SMART-ITL facility
|
Kim, Yeon-Sik
|
|
2018
|
113 |
C |
p. 25-36
|
artikel
|
| 28 |
Investigation of the thermal characteristics of condensers in nuclear power plant by simulation with zoning model
|
Sun, Ji-Lin
|
|
2018
|
113 |
C |
p. 37-47
|
artikel
|
| 29 |
Machine learning based system performance prediction model for reactor control
|
Zeng, Yuyun
|
|
2018
|
113 |
C |
p. 270-278
|
artikel
|
| 30 |
Measurements of the total neutron cross sections of 93Nb by using the filtered neutron beams
|
Anh, Tran Tuan
|
|
2018
|
113 |
C |
p. 420-424
|
artikel
|
| 31 |
Multigroup Monte Carlo on GPUs: Comparison of history- and event-based algorithms
|
Hamilton, Steven P.
|
|
2018
|
113 |
C |
p. 506-518
|
artikel
|
| 32 |
Multi-scale analysis of an ATLAS-MSLB test using the coupled CUPID/MARS code
|
Park, Ik Kyu
|
|
2018
|
113 |
C |
p. 332-343
|
artikel
|
| 33 |
Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors
|
Naceur, A.
|
|
2018
|
113 |
C |
p. 147-161
|
artikel
|
| 34 |
Neutronic properties of high-temperature gas-cooled reactors with thorium fuel
|
Shamanin, I.V.
|
|
2018
|
113 |
C |
p. 286-293
|
artikel
|
| 35 |
Neutron noise simulation using ACNEM in the hexagonal geometry
|
Hosseini, Seyed Abolfazl
|
|
2018
|
113 |
C |
p. 246-255
|
artikel
|
| 36 |
Nonlinear dynamic model of Molten-Salt Reactor Experiment – Validation and operational analysis
|
Singh, Vikram
|
|
2018
|
113 |
C |
p. 177-193
|
artikel
|
| 37 |
Numerical comparison of bubbling in a waste glass melter
|
Guillen, Donna Post
|
|
2018
|
113 |
C |
p. 380-392
|
artikel
|
| 38 |
Numerical optimization of Rhodium Self-Powered Neutron Detector
|
Zhang, Qingmin
|
|
2018
|
113 |
C |
p. 519-525
|
artikel
|
| 39 |
Numerical simulation of external inertia and compressibility effects on the dynamic instabilities of two-phase boiling flows in horizontal parallel channels
|
Bakhshan, Y.
|
|
2018
|
113 |
C |
p. 294-307
|
artikel
|
| 40 |
Reactor design strategy to support spectral variability within a sodium-cooled fast spectrum materials testing reactor
|
Scherr, Jonathan
|
|
2018
|
113 |
C |
p. 15-24
|
artikel
|
| 41 |
Rod insertion method analysis – A methodology update and comparison to boron dilution method
|
Merljak, Vid
|
|
2018
|
113 |
C |
p. 96-104
|
artikel
|
| 42 |
Stochastic uncertainty quantification for safety verification applications in nuclear power plants
|
Boafo, Emmanuel
|
|
2018
|
113 |
C |
p. 399-408
|
artikel
|
| 43 |
The evolution of PBIL algorithm when used to solve the nuclear reload optimization problem
|
da Silva, Márcio Henrique
|
|
2018
|
113 |
C |
p. 393-398
|
artikel
|
| 44 |
Thorium as an additive for improved neutronic properties in boiling water reactor fuel
|
Insulander Björk, Klara
|
|
2018
|
113 |
C |
p. 470-475
|
artikel
|
| 45 |
Validation of SuperMC code by simulating a Metal-cooled fast reactor – BFS-62-3A
|
Jamil, Zeeshan
|
|
2018
|
113 |
C |
p. 122-129
|
artikel
|
| 46 |
Validation of the MCU-PTR computational model of beryllium poisoning using selected experiments at the IRT-T research reactor
|
Shchurovskaya, M.V.
|
|
2018
|
113 |
C |
p. 436-445
|
artikel
|
| 47 |
Verification of SuperMC for MNSRs core analysis: The case of Ghana Research Reactor-I
|
Baidoo, I.K.
|
|
2018
|
113 |
C |
p. 48-54
|
artikel
|
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