| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A comparative study of high and low order neutronics calculation models in microreactors
|
Li, Xiangyue
|
|
|
215 |
C |
p.
|
artikel
|
| 2 |
Adjusting JEFF-3.3 actinide data using a new, dedicated methodology for selecting suited assimilation database parameters
|
Pelloni, Sandro
|
|
|
215 |
C |
p.
|
artikel
|
| 3 |
Advanced full-core modeling of fission product release in pebble-bed high-temperature gas-cooled reactors
|
Cao, Chenghao
|
|
|
215 |
C |
p.
|
artikel
|
| 4 |
A fuzzy logic-based coordinated adaptive control method for megawatt novel nuclear power systems
|
Jiang, Qingfeng
|
|
|
215 |
C |
p.
|
artikel
|
| 5 |
An iDTMC-Assisted Predictor-Corrector Quasi-Static Monte Carlo simulation in the iMC code
|
Oh, Taesuk
|
|
|
215 |
C |
p.
|
artikel
|
| 6 |
An iterative scheme to include turbulent diffusion in advective-dominated transport of delayed neutron precursors
|
Caprais, Mathis
|
|
|
215 |
C |
p.
|
artikel
|
| 7 |
Artificial intelligence methods application for reactor dynamics predicting in the tasks of maneuverable modes safety assessment
|
Uvakin, M.A.
|
|
|
215 |
C |
p.
|
artikel
|
| 8 |
Characterization of neutron spectrum at the neutron radiography of RSG-GAS reactor using a passive single-cylindrical neutron spectrometer
|
Tursinah, Rasito
|
|
|
215 |
C |
p.
|
artikel
|
| 9 |
Comparison between EDF MAAP5.04 and ASTECV3 codes on a hypothetical severe accident on the ELSMOR project E-SMR design
|
Bittan, Jeremy
|
|
|
215 |
C |
p.
|
artikel
|
| 10 |
Computational comparison of hydrogenous molecules as a cold moderator for compact accelerator-based neutron sources
|
Abe, Y.
|
|
|
215 |
C |
p.
|
artikel
|
| 11 |
Core-wide multi-physics simulation of fuel behaviour during large-break LOCA using NEXUS
|
Peakman, Aiden
|
|
|
215 |
C |
p.
|
artikel
|
| 12 |
Design and analysis of CFETR magnet current feeder
|
Han, Quan
|
|
|
215 |
C |
p.
|
artikel
|
| 13 |
Editorial Board
|
|
|
|
215 |
C |
p.
|
artikel
|
| 14 |
Evaluation for self-powered neutron detector used in sodium-cooled fast reactor
|
Du, Sipeng
|
|
|
215 |
C |
p.
|
artikel
|
| 15 |
Experimental and numerical investigation on the hydraulic characteristics of orifice plate throttle for sodium-cooled fast reactor
|
Qin, Haiqi
|
|
|
215 |
C |
p.
|
artikel
|
| 16 |
Experimental investigation for radiation shielding performance of B2O3-TeO2-Bi2O3-ZnO-CaO glass system
|
Almuqrin, Aljawhara H.
|
|
|
215 |
C |
p.
|
artikel
|
| 17 |
High-burnup boiling water reactor steady-state operating conditions and fuel performance analysis
|
Capps, Nathan
|
|
|
215 |
C |
p.
|
artikel
|
| 18 |
Improvement on natural uranium utilisation in heavy water-moderated molten salt reactor using radial blanket
|
Putra Dwijayanto, R.Andika
|
|
|
215 |
C |
p.
|
artikel
|
| 19 |
Investigation on the packing and hydration homogeneity of bentonite pellet mixtures
|
Hu, Shixiang
|
|
|
215 |
C |
p.
|
artikel
|
| 20 |
MURR LEU structural and thermal hydraulics analyses: Part II – Impacts of irradiation thermo-mechanical behavior on thermal hydraulics safety analyses
|
Yoon, Dhongik S.
|
|
|
215 |
C |
p.
|
artikel
|
| 21 |
On the practicalities of producing a nuclear weapon using high-assay low-enriched uranium
|
Cosgrove, P.
|
|
|
215 |
C |
p.
|
artikel
|
| 22 |
Optical and spectral features of new Borax/ Li2O glass systems and calculation of radiation shielding attenuation parameters
|
Abdelmonem, A.M.
|
|
|
215 |
C |
p.
|
artikel
|
| 23 |
Optimization of core design to achieve ultra-long core life in alternative ways for modular gas cooled fast reactor
|
Islam, Shohanul
|
|
|
215 |
C |
p.
|
artikel
|
| 24 |
Performance analysis of U-50Zr helical cruciform fuel during loss-of-coolant accidents Based on MOOSE framework
|
Hou, Yandong
|
|
|
215 |
C |
p.
|
artikel
|
| 25 |
Representation of homogenized cross section data by Canonical-Polyadic decomposition
|
Nguyen, Dinh Quoc Dang
|
|
|
215 |
C |
p.
|
artikel
|
| 26 |
Source term dispersion analysis and construction of the probabilistic dispersion map around the Peach Bottom Unit-2 plant using the ASTEC and JRODOS codes
|
Murat, Onur
|
|
|
215 |
C |
p.
|
artikel
|
| 27 |
Thermal-hydraulic analysis of a 19-rod bundle LBE cooled fuel assembly with non-uniform rods power distribution by numerical simulation
|
Luo, Guanwen
|
|
|
215 |
C |
p.
|
artikel
|
| 28 |
Utilization of NEUP Data for HTGR Thermal-Fluid Code Validation: A New Resource Platform
|
Qin, Sunming
|
|
|
215 |
C |
p.
|
artikel
|
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