| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A fully analytic space-time depletion benchmark for fixed-source and eigenvalue calculations and its application to Monte Carlo simulation
|
Kooreman, Gabriel
|
|
2019
|
127 |
C |
p. 99-110
|
artikel
|
| 2 |
A Monte Carlo technique for sensitivity analysis of alpha-eigenvalue with the differential operator sampling method
|
Yamamoto, Toshihiro
|
|
2019
|
127 |
C |
p. 178-187
|
artikel
|
| 3 |
An advanced experimental design for modified burst testing of nuclear fuel cladding materials during transient loading
|
Cinbiz, M. Nedim
|
|
2019
|
127 |
C |
p. 30-38
|
artikel
|
| 4 |
Analysis of natural circulation frictional resistance characteristics in rod bundle channel
|
Zhang, Yinxing
|
|
2019
|
127 |
C |
p. 79-86
|
artikel
|
| 5 |
Analysis of the radioactive atmospheric dispersion induced by ship nuclear power plant severe accident
|
Ouyang, Kehan
|
|
2019
|
127 |
C |
p. 395-399
|
artikel
|
| 6 |
An approach for radiological consequence assessment under unified temporal and spatial coordinates considering multi-reactor accidents
|
Ding, Hongchun
|
|
2019
|
127 |
C |
p. 450-458
|
artikel
|
| 7 |
A new framework for sampling-based uncertainty quantification of the six-group reactor kinetic parameters
|
Radaideh, Majdi I.
|
|
2019
|
127 |
C |
p. 1-11
|
artikel
|
| 8 |
Application of Differential Evolution algorithms to multi-objective optimization problems in mixed-oxide fuel assembly design
|
Charles, Alan
|
|
2019
|
127 |
C |
p. 165-177
|
artikel
|
| 9 |
A quasi-static Monte Carlo algorithm for the simulation of sub-prompt critical transients
|
Trahan, Travis J.
|
|
2019
|
127 |
C |
p. 257-267
|
artikel
|
| 10 |
A stochastic method in simulating particles transport and deposition in wall-bounded turbulent flow
|
Gu, Weiguo
|
|
2019
|
127 |
C |
p. 12-18
|
artikel
|
| 11 |
A study on the density wave oscillation relative stability turning point of uniform and cosine heat flux profiles in parallel channels
|
Ma, Zaiyong
|
|
2019
|
127 |
C |
p. 111-119
|
artikel
|
| 12 |
Atmospheric dispersion modeling and radiological safety assessment for expected operation of Baiji nuclear power plant potential site
|
Mohammed Saeed, Ismael Mohammed
|
|
2019
|
127 |
C |
p. 156-164
|
artikel
|
| 13 |
Best Estimate Plus Uncertainty analysis of a large break LOCA on Generation III reactor with RELAP5
|
Yang, Jun
|
|
2019
|
127 |
C |
p. 326-340
|
artikel
|
| 14 |
Concept of breed and burn reactor with spiral fuel shuffling
|
Kuwagaki, Kazuki
|
|
2019
|
127 |
C |
p. 130-138
|
artikel
|
| 15 |
Controller tuning constants for the Advanced Power Reactor 1400 Feedwater Control System based on Ms-Constrained Integral Gain Optimization Method
|
Tran, Thanh Cong
|
|
2019
|
127 |
C |
p. 39-52
|
artikel
|
| 16 |
Control rod treatment for FEM based radiation transport methods
|
Schunert, Sebastian
|
|
2019
|
127 |
C |
p. 293-302
|
artikel
|
| 17 |
Convex shaped FBR core with graded size pins to prevent re-criticality during Core Disruptive Accident
|
Chitose, Keiko
|
|
2019
|
127 |
C |
p. 364-371
|
artikel
|
| 18 |
Corrosion resistance of candidate cladding materials for supercritical water reactor
|
Guo, Xianglong
|
|
2019
|
127 |
C |
p. 351-363
|
artikel
|
| 19 |
Coupled neutronic/thermal-hydraulic hot channel analysis of high power density civil marine SMR cores
|
Alam, Syed Bahauddin
|
|
2019
|
127 |
C |
p. 400-411
|
artikel
|
| 20 |
Coupling scheme of multicomponent sectional equations and Mason equations via transition rate matrix of hygroscopic growth applied to international standard problem No. 44
|
Lee, Yoonhee
|
|
2019
|
127 |
C |
p. 437-449
|
artikel
|
| 21 |
Development and validation of a thermal hydraulic transient analysis code for offshore floating nuclear reactor based on RELAP5/SCDAPSIM/MOD3.4
|
Cheng, Kun
|
|
2019
|
127 |
C |
p. 215-226
|
artikel
|
| 22 |
Development of 3-D HCMFD algorithm for efficient pin-by-pin reactor analysis
|
Kim, Jaeha
|
|
2019
|
127 |
C |
p. 87-98
|
artikel
|
| 23 |
Editorial Board
|
|
|
2019
|
127 |
C |
p. ii
|
artikel
|
| 24 |
Effects of the operating strategies of filtered containment venting system on Cesium-137 releases during severe accidents
|
Lee, Eun-Hye
|
|
2019
|
127 |
C |
p. 469-478
|
artikel
|
| 25 |
Feasibility studies for simultaneous irradiation of NBSR & MITR fuel elements in the BR2 reactor
|
Kalcheva, Silva
|
|
2019
|
127 |
C |
p. 303-318
|
artikel
|
| 26 |
Heterogeneous discontinuity factor treatment in Variational Nodal Method
|
Li, Yunzhao
|
|
2019
|
127 |
C |
p. 341-350
|
artikel
|
| 27 |
Implication of LOCA characteristics of large PWR and SMR for future development of intelligent nuclear power plant control system
|
Kim, Min-Gil
|
|
2019
|
127 |
C |
p. 237-247
|
artikel
|
| 28 |
Investigation on flow and breakdown characteristics of water film on vertical corrugated plate wall
|
Wang, Bo
|
|
2019
|
127 |
C |
p. 120-129
|
artikel
|
| 29 |
Investigation on mixing behavior and heat transfer in a horizontally arranged tee pipe under turbulent mixing of hot and cold fluid
|
Lu, Tao
|
|
2019
|
127 |
C |
p. 139-155
|
artikel
|
| 30 |
Method for determining the energy parameters in pulse reactor experiments
|
Vityuk, Vladimir
|
|
2019
|
127 |
C |
p. 196-203
|
artikel
|
| 31 |
Minor Actinides transmutation in candidate accident tolerant fuel-claddings U3Si2-FeCrAl and U3Si2-SiC
|
Chen, Shengli
|
|
2019
|
127 |
C |
p. 204-214
|
artikel
|
| 32 |
Modeling of heavy reflectors using DONJON-5
|
Taforeau, Julien
|
|
2019
|
127 |
C |
p. 319-325
|
artikel
|
| 33 |
Modified quantum evolutionary algorithm and self-regulated learning for reactor loading pattern design
|
Hsieh, Min-Sau
|
|
2019
|
127 |
C |
p. 268-277
|
artikel
|
| 34 |
Neutronic analysis for potential Accident Tolerant Fuel UO2-BeO in the light water reactor
|
Zhang, Qian
|
|
2019
|
127 |
C |
p. 278-292
|
artikel
|
| 35 |
New monitoring procedure of axial xenon oscillation in large pressurized water reactors
|
Al Nuaimi, Abdulla
|
|
2019
|
127 |
C |
p. 459-468
|
artikel
|
| 36 |
Practical Monte Carlo simulation using modified power method with preconditioning
|
Zhang, Peng
|
|
2019
|
127 |
C |
p. 372-384
|
artikel
|
| 37 |
Quantification and mechanism analysis of the k inf uncertainty propagated from nuclear data for the TRISO particle fuel pebble
|
Hao, Chen
|
|
2019
|
127 |
C |
p. 248-256
|
artikel
|
| 38 |
Reliability assessment of passive residual heat removal system of IPWR using Kriging regression model
|
Wang, Chenyang
|
|
2019
|
127 |
C |
p. 479-489
|
artikel
|
| 39 |
Safety evaluation of spent fuel road transportation based on weighted nearest neighbor method
|
Li, Zhongyang
|
|
2019
|
127 |
C |
p. 412-418
|
artikel
|
| 40 |
Second-order sensitivity analysis of uncollided particle contributions to radiation detector responses using ray-tracing
|
Favorite, Jeffrey A.
|
|
2019
|
127 |
C |
p. 490-501
|
artikel
|
| 41 |
Study of the homogeneous and heterogeneous Am transmutation in an ELFR-like reactor loaded with nitride fuel
|
Juárez, Luis-Carlos
|
|
2019
|
127 |
C |
p. 19-29
|
artikel
|
| 42 |
The coupled neutron transport calculation of Monte Carlo multi-group and continuous cross section
|
Deng, Li
|
|
2019
|
127 |
C |
p. 433-436
|
artikel
|
| 43 |
Thermal analysis of ceramic nuclear fuels for the HPLWR
|
Castro, Landy
|
|
2019
|
127 |
C |
p. 227-236
|
artikel
|
| 44 |
Thermal-hydraulic analysis code development for sodium heated once-through steam generator
|
Xu, Rongshuan
|
|
2019
|
127 |
C |
p. 385-394
|
artikel
|
| 45 |
Thermal-hydraulic modeling for deterministic safety analysis of portable equipment application in the VVER-1000 nuclear reactor during loss of ultimate heat sink accident using RELAP5/MOD3.2 code
|
Tabadar, Z.
|
|
2019
|
127 |
C |
p. 53-67
|
artikel
|
| 46 |
Thermal neutron scattering kernels for uranium mono-nitride: A potential advanced tolerant fuel candidate for light water reactors
|
Al-Qasir, Iyad
|
|
2019
|
127 |
C |
p. 68-78
|
artikel
|
| 47 |
Uncertainty quantification method for RELAP5-3D© using RAVEN and application on NACIE experiments
|
Narcisi, Vincenzo
|
|
2019
|
127 |
C |
p. 419-432
|
artikel
|
| 48 |
Validation of SARAX for the China Fast Reactor with the extrapolated experimental data
|
Wan, Chenghui
|
|
2019
|
127 |
C |
p. 188-195
|
artikel
|
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