| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
An exploration of the relationship between nuclear decommissioning projects characteristics and cost performance
|
Invernizzi, Diletta Colette
|
|
|
110 |
C |
p. 129-141
|
artikel
|
| 2 |
A one-dimensional code of the passive residual heat removal system for the modular high temperature gas-cooled reactor
|
Zhao, Hangbin
|
|
|
110 |
C |
p. 374-383
|
artikel
|
| 3 |
Assessment of radioactive contamination in primary circuit of WWER-440 type reactors by computer code OSCAR for the decommissioning case
|
Juodis, Laurynas
|
|
|
110 |
C |
p. 191-198
|
artikel
|
| 4 |
Assessment of the impact of diversification of uranium switching on the risk of its non-energy use
|
Glebov, Vasily
|
|
|
110 |
C |
p. 75-79
|
artikel
|
| 5 |
A study on boundary fluxes approximation in explicit nodal formulations for the solution of the two-dimensional neutron transport equation
|
Cromianski, S.R.
|
|
|
110 |
C |
p. 354-363
|
artikel
|
| 6 |
A two-phase model for simulation of MTR type research reactor during protected and unprotected LOFA
|
Talebi, S.
|
|
|
110 |
C |
p. 274-288
|
artikel
|
| 7 |
A world's dilemma ‘upon which the sun never sets’: The nuclear waste management strategy (part II): Russia, Asia and the Southern Hemisphere
|
Sanders, Mark Callis
|
|
|
110 |
C |
p. 148-169
|
artikel
|
| 8 |
Conditions for translation and scaling invariance of the neutron diffusion equation
|
Giron, Jesse F.
|
|
|
110 |
C |
p. 333-340
|
artikel
|
| 9 |
Consequence analysis of a transportation accident of radioactive spent resin waste from a heavy water-cooled reactor to a the Gyeongju radioactive waste disposal facility
|
Lee, UkJae
|
|
|
110 |
C |
p. 34-40
|
artikel
|
| 10 |
3D calculation of the lambda eigenvalues and eigenmodes of the two-group neutron diffusion equation by coarse-mesh nodal methods
|
Munoz-Cobo, J.L.
|
|
|
110 |
C |
p. 393-409
|
artikel
|
| 11 |
Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning
|
Nguyen, Tam Cong
|
|
|
110 |
C |
p. 103-109
|
artikel
|
| 12 |
Development and verification of resonance elastic scattering kernel processing module in nuclear data processing code NECP-Atlas
|
Xu, Jialong
|
|
|
110 |
C |
p. 301-310
|
artikel
|
| 13 |
Development of network-based probabilistic safety assessment: A tool for risk analyst for nuclear facilities
|
Kwag, Shinyoung
|
|
|
110 |
C |
p. 178-190
|
artikel
|
| 14 |
Editorial Board
|
|
|
|
110 |
C |
p. ii
|
artikel
|
| 15 |
Experimental investigation of fluid mixing inside a rod bundle using laser induced fluorescence
|
Li, Xing
|
|
|
110 |
C |
p. 90-102
|
artikel
|
| 16 |
Fluid-elastic instability evaluation for reactor vessel internals with structural interaction
|
Kim, Tae-Jin
|
|
|
110 |
C |
p. 41-50
|
artikel
|
| 17 |
GPU-based implementation of a real-time model for atmospheric dispersion of radionuclides
|
Santos, Marcelo C.
|
|
|
110 |
C |
p. 245-259
|
artikel
|
| 18 |
Higher orders of Magnus expansion for point kinetics telegraph model
|
Aboanber, Ahmed E.
|
|
|
110 |
C |
p. 1-12
|
artikel
|
| 19 |
High-order lattice Boltzmann method for multi-group neutron diffusion solution
|
Wang, Yahui
|
|
|
110 |
C |
p. 341-353
|
artikel
|
| 20 |
Impact of integral burnable absorbers on SMART reactor behaviour under normal and anomalous operational conditions
|
Kamalpour, Sarah
|
|
|
110 |
C |
p. 51-63
|
artikel
|
| 21 |
Laboratory-scale quartz crucible melter tests for vitrifying a high-MoO3 raffinate waste simulant
|
Riley, Brian J.
|
|
|
110 |
C |
p. 13-23
|
artikel
|
| 22 |
Margin evaluation of in-vessel melt retention for small IPWR
|
Jiang, Nan
|
|
|
110 |
C |
p. 224-235
|
artikel
|
| 23 |
Modern financial models of nuclear power plants
|
Terlikowski, Pawel
|
|
|
110 |
C |
p. 30-33
|
artikel
|
| 24 |
Monte Carlo burnup code development based on multi-group cross section method
|
Zhu, Guifeng
|
|
|
110 |
C |
p. 24-29
|
artikel
|
| 25 |
Monte Carlo simulation of Novalis Classic 6 MV accelerator using phase space generation in GATE/Geant4 code
|
Teixeira, M.S.
|
|
|
110 |
C |
p. 142-147
|
artikel
|
| 26 |
Nonlinear PI output power regulation in a light water reactor
|
Zarei, M.
|
|
|
110 |
C |
p. 80-89
|
artikel
|
| 27 |
Nuclear frames in the Irish media: Implications for conversations on nuclear power generation in the age of climate change
|
Devitt, Catherine
|
|
|
110 |
C |
p. 260-273
|
artikel
|
| 28 |
Numerical analysis of spatial discretization schemes in ARES transport code for shielding calculation
|
Zhang, Liang
|
|
|
110 |
C |
p. 236-244
|
artikel
|
| 29 |
Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors
|
Song, Ping
|
|
|
110 |
C |
p. 213-223
|
artikel
|
| 30 |
One-dimensional drift-flux correlation for vertical upward two-phase flow in a large size rectangular channel
|
Abbs, Tyler
|
|
|
110 |
C |
p. 311-324
|
artikel
|
| 31 |
Onsite power system risk assessment for nuclear power plants considering components ageing
|
Agwa, A.M.
|
|
|
110 |
C |
p. 384-392
|
artikel
|
| 32 |
Physics study of liquid hydrogen moderator of CMRR reactor cold neutron source
|
Mei, Longwei
|
|
|
110 |
C |
p. 121-128
|
artikel
|
| 33 |
Potential areas for nuclear power plants siting in Saudi Arabia: GIS-based multi-criteria decision making analysis
|
Damoom, Mohammed M.
|
|
|
110 |
C |
p. 110-120
|
artikel
|
| 34 |
Preliminary hydraulic analysis of the distribution zone in the Dual Fluid Reactor concept
|
Wang, Xiang
|
|
|
110 |
C |
p. 364-373
|
artikel
|
| 35 |
Safety culture development, research, and implementation in China: An overview
|
Wang, Bing
|
|
|
110 |
C |
p. 289-300
|
artikel
|
| 36 |
The Multi-PN approximation to neutron transport equation
|
Ghazaie, S.H.
|
|
|
110 |
C |
p. 64-74
|
artikel
|
| 37 |
The preliminary neutronics analysis for a 10 MW molten salt reactor with solid fuel
|
Li, Zhifeng
|
|
|
110 |
C |
p. 325-332
|
artikel
|
| 38 |
Transient sub-channel code development for lead-cooled fast reactor using the second-order upwind scheme
|
Cao, Liankai
|
|
|
110 |
C |
p. 199-212
|
artikel
|
| 39 |
Viability of uranium nitride (UN) as annular fuel for AP-1000
|
Hassan, Ibrahim A.
|
|
|
110 |
C |
p. 170-177
|
artikel
|
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