| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Activation product interpretation of structural material for fast critical assemblies
|
Keith, Corey
|
|
2018
|
119 |
C |
p. 98-105
|
artikel
|
| 2 |
A new and rigorous SPN theory – Part III: A succinct summary of the GSPN theory, the P3 equivalent GSP 3 ( 3 ) and implementation issues
|
Chao, Yung-An
|
|
2018
|
119 |
C |
p. 310-321
|
artikel
|
| 3 |
Application of implicit Roe-type scheme and Jacobian-Free Newton-Krylov method to two-phase flow problems
|
Hu, Guojun
|
|
2018
|
119 |
C |
p. 180-190
|
artikel
|
| 4 |
Applying conformal mapping method to Hybrid Nodal Green’s Function Method for two-dimensional simplified HTTR core calculation
|
Lin, Tzung-Yi
|
|
2018
|
119 |
C |
p. 419-426
|
artikel
|
| 5 |
ASTEC-Na code: Thermal-hydraulic model validation and benchmarking with other codes
|
Bandini, G.
|
|
2018
|
119 |
C |
p. 427-439
|
artikel
|
| 6 |
A theoretical model for the vibration of fuel rod with multi spans supported by springs
|
Yan, B.H.
|
|
2018
|
119 |
C |
p. 257-263
|
artikel
|
| 7 |
Autonomous operation algorithm for safety systems of nuclear power plants by using long-short term memory and function-based hierarchical framework
|
Lee, Daeil
|
|
2018
|
119 |
C |
p. 287-299
|
artikel
|
| 8 |
Bubble behavior and its contribution to heat transfer of subcooled flow boiling in a vertical rectangular channel
|
Yuan, Dewen
|
|
2018
|
119 |
C |
p. 191-202
|
artikel
|
| 9 |
Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage
|
Arkoma, Asko
|
|
2018
|
119 |
C |
p. 129-138
|
artikel
|
| 10 |
Comparative study on nuclear characteristics of APR1400 between 100% MOX core and UO2 core
|
Salam, Mahrus
|
|
2018
|
119 |
C |
p. 374-381
|
artikel
|
| 11 |
Derivation of radiological source term of Korean Design System-Integrated Modular Advanced ReacTor (SMART)
|
Mehboob, Khurram
|
|
2018
|
119 |
C |
p. 148-161
|
artikel
|
| 12 |
Determination of thorium fission rate based on 135I in thorium oxide cylinder bombarded by D-T fusion neutrons
|
Zheng, Lei
|
|
2018
|
119 |
C |
p. 264-270
|
artikel
|
| 13 |
Deterministically estimated fission source distributions for Monte Carlo k-eigenvalue problems
|
Biondo, Elliott D.
|
|
2018
|
119 |
C |
p. 7-22
|
artikel
|
| 14 |
Development and assessment of ASTEC-Na fuel pin thermo-mechanical models performed in the European JASMIN project
|
Perez-Martin, S.
|
|
2018
|
119 |
C |
p. 454-473
|
artikel
|
| 15 |
DSS application on single-phase natural circulation in a simple rectangular loop
|
Li, Xiangbin
|
|
2018
|
119 |
C |
p. 214-228
|
artikel
|
| 16 |
Editorial Board
|
|
|
2018
|
119 |
C |
p. ii
|
artikel
|
| 17 |
Effect of void propagation to sodium void reactivity in transient analyses of fast reactors with sodium-plenum
|
Takeda, Toshikazu
|
|
2018
|
119 |
C |
p. 175-179
|
artikel
|
| 18 |
Enhanced thermal conductivity accident tolerant fuels for improved reactor safety – A comprehensive review
|
Zhou, Wei
|
|
2018
|
119 |
C |
p. 66-86
|
artikel
|
| 19 |
Experimental study of supercritical water heat transfer deteriorations in different channels
|
Li, Hong-bo
|
|
2018
|
119 |
C |
p. 240-256
|
artikel
|
| 20 |
Extension of ASTEC-Na capabilities for simulating reactivity effects in Sodium Cooled Fast Reactor
|
Matuzas, V.
|
|
2018
|
119 |
C |
p. 440-453
|
artikel
|
| 21 |
Extension of the reactor dynamics code DYN3D to SFR applications – Part III: Validation against the initial phase of the Phenix EOL natural convection test
|
Nikitin, E.
|
|
2018
|
119 |
C |
p. 390-395
|
artikel
|
| 22 |
Extension of the reactor dynamics code DYN3D to SFR applications – Part II: Validation against the Phenix EOL control rod withdrawal tests
|
Nikitin, E.
|
|
2018
|
119 |
C |
p. 411-418
|
artikel
|
| 23 |
Extension of the reactor dynamics code DYN3D to SFR applications – Part I: Thermal expansion models
|
Nikitin, E.
|
|
2018
|
119 |
C |
p. 382-389
|
artikel
|
| 24 |
Fault detectability analysis in PCA method during condition monitoring of sensors in a nuclear power plant
|
Li, Wei
|
|
2018
|
119 |
C |
p. 342-351
|
artikel
|
| 25 |
Fuel cycle and neutronic performance of a spectral shift molten salt reactor design
|
Betzler, Benjamin R.
|
|
2018
|
119 |
C |
p. 396-410
|
artikel
|
| 26 |
Importance of parametric uncertainty in predicting probability distributions for burst wait-times in fissile systems
|
Winter, George E.
|
|
2018
|
119 |
C |
p. 117-128
|
artikel
|
| 27 |
Influence of accident tolerant fuel cladding material on the European pressurised reactor core neutronic characteristics
|
Boettcher, Agnieszka
|
|
2018
|
119 |
C |
p. 203-213
|
artikel
|
| 28 |
Investigation on reverse flow phenomena in UTSGs under two-phase natural circulation with low steam quality
|
Chu, Xi
|
|
2018
|
119 |
C |
p. 1-6
|
artikel
|
| 29 |
Monte Carlo perturbation methods using “virtual density” theory for calculating reactivity due to geometry change
|
Yamamoto, Toshihiro
|
|
2018
|
119 |
C |
p. 362-373
|
artikel
|
| 30 |
New developments in modeling sodium spray fires with ASTEC-Na
|
Lebel, Luke S.
|
|
2018
|
119 |
C |
p. 23-35
|
artikel
|
| 31 |
New developments in sodium pool fire and SFR containment aerosol modeling with ASTEC-Na
|
Lebel, Luke S.
|
|
2018
|
119 |
C |
p. 229-239
|
artikel
|
| 32 |
[No title]
|
Williams, M.M.R.
|
|
2018
|
119 |
C |
p. 162
|
artikel
|
| 33 |
Numerical analysis of 1/28 scaled NGNP HTGR reactor building test facility response to depressurization event using GOTHIC
|
Yildiz, Mustafa Alper
|
|
2018
|
119 |
C |
p. 46-65
|
artikel
|
| 34 |
Numerical study on hydrodynamic and thermal characteristics of spent fuel pool
|
Yu, Cheng-Lun
|
|
2018
|
119 |
C |
p. 139-147
|
artikel
|
| 35 |
Optimization of CABRI power transients with the SPARTE code and the URANIE uncertainty platform
|
Clamens, O.
|
|
2018
|
119 |
C |
p. 271-278
|
artikel
|
| 36 |
Overview of filtered containment venting system in Nuclear Power Plants in Asia
|
Yang, Jun
|
|
2018
|
119 |
C |
p. 87-97
|
artikel
|
| 37 |
Probability distribution for neutron density of two energy group point kinetics system
|
Aboanber, Ahmed E.
|
|
2018
|
119 |
C |
p. 300-309
|
artikel
|
| 38 |
Reactor core power mapping based on Bayesian inference
|
Peng, Xingjie
|
|
2018
|
119 |
C |
p. 322-330
|
artikel
|
| 39 |
Reducing the plutonium stockpile around the world using a new design of VVER-1200 assembly
|
Galahom, A. Abdelghafar
|
|
2018
|
119 |
C |
p. 279-286
|
artikel
|
| 40 |
Risk analysis of high level radioactive waste storage tank based on HAZOP
|
Zou, Shuliang
|
|
2018
|
119 |
C |
p. 106-116
|
artikel
|
| 41 |
Some considerations to improve the methodology to assess In-Vessel Retention strategy for high-power reactors
|
Fichot, F.
|
|
2018
|
119 |
C |
p. 36-45
|
artikel
|
| 42 |
Study on thermal fragmentation characteristics of a superheated alumina droplet
|
Zambaux, J.A.
|
|
2018
|
119 |
C |
p. 352-361
|
artikel
|
| 43 |
The digital simulation and fuzzy evaluation to reduce the likelihood of unsafe behavior in nuclear decommissioning
|
Li, Meng-kun
|
|
2018
|
119 |
C |
p. 331-341
|
artikel
|
| 44 |
Thermal analysis for the integrated spent fuel pool of the Chinshan plant in the decommissioning process
|
Chen, Yen-Shu
|
|
2018
|
119 |
C |
p. 163-174
|
artikel
|
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