| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A miniature integrated nuclear reactor design with gravity independent autonomous circulation
|
Zhou, Qin
|
|
2018
|
340 |
C |
p. 9-16
|
artikel
|
| 2 |
An improved Multiphase Moving Particle Semi-implicit method in bubble rising simulations with large density ratios
|
Guo, Kailun
|
|
2018
|
340 |
C |
p. 370-387
|
artikel
|
| 3 |
An improved probabilistic method for screening safety-related human actions in nuclear power plants
|
Zhang, Li
|
|
2018
|
340 |
C |
p. 415-420
|
artikel
|
| 4 |
A numerical study on slip correction factor of dust particle in HTGR
|
Sun, Qi
|
|
2018
|
340 |
C |
p. 31-39
|
artikel
|
| 5 |
A success-oriented analysis technique for operational risk supervision in sea-borne nuclear power plants
|
Jun, Yang
|
|
2018
|
340 |
C |
p. 229-239
|
artikel
|
| 6 |
Component design and accident analysis of fuel assembly for prototype GEN-IV sodium-cooled fast reactor
|
Yoon, K.H.
|
|
2018
|
340 |
C |
p. 133-145
|
artikel
|
| 7 |
Corrigendum to “The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles” [Nucl. Eng. Des. 335 (2018) 356–373]
|
Chen, S.K.
|
|
2018
|
340 |
C |
p. 414
|
artikel
|
| 8 |
Deciphering conical spouted bed hydrodynamics using high intensity microphone
|
Rao, P.T.
|
|
2018
|
340 |
C |
p. 54-61
|
artikel
|
| 9 |
Design modification and shaking table test of the drain pipes of steam generator for vibration reduction
|
Heo, Yong-Ho
|
|
2018
|
340 |
C |
p. 68-72
|
artikel
|
| 10 |
Development of a measurement technique for detailed flow characterization in fuel bundles
|
Nalín, O.C.A.
|
|
2018
|
340 |
C |
p. 146-155
|
artikel
|
| 11 |
Development of a sub-channel analysis code based on the two-fluid model and its preliminary assessment
|
Huang, Jun
|
|
2018
|
340 |
C |
p. 17-30
|
artikel
|
| 12 |
Editorial Board
|
|
|
2018
|
340 |
C |
p. ii
|
artikel
|
| 13 |
Evaluation on fuel cycle and loading scheme of the Indonesian experimental power reactor (RDE) design
|
Liem, Peng Hong
|
|
2018
|
340 |
C |
p. 245-259
|
artikel
|
| 14 |
Experimental and numerical analyses on flow-induced vibration of a nuclear engineering test reactor internal
|
Lai, Jiang
|
|
2018
|
340 |
C |
p. 335-346
|
artikel
|
| 15 |
Experimental study of sodium heat exchanger performance at high Pe number condition using STELLA-1 facility
|
Lee, Jewhan
|
|
2018
|
340 |
C |
p. 62-67
|
artikel
|
| 16 |
Fuel geometry options for a moderated low-enriched uranium kilowatt-class space nuclear reactor
|
Mencarini, Leonardo de Holanda
|
|
2018
|
340 |
C |
p. 122-132
|
artikel
|
| 17 |
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant
|
Cognini, L.
|
|
2018
|
340 |
C |
p. 240-244
|
artikel
|
| 18 |
Implementation of probabilistic assessments to support the ASTRID decay heat removal systems design process
|
Aubert, F.
|
|
2018
|
340 |
C |
p. 405-413
|
artikel
|
| 19 |
Influence of simultaneous variations in operating parameters on burnup credit criticality analysis for PWR spent fuel assemblies
|
Wu, Shang-Chien
|
|
2018
|
340 |
C |
p. 193-200
|
artikel
|
| 20 |
Jet breaker plate for suppressing gas entrainment and flow induced vibration of a CSRDM shroud tube assembly inside the control plug shell
|
Gautam, Ankit K.
|
|
2018
|
340 |
C |
p. 86-104
|
artikel
|
| 21 |
Monte Carlo simulation of PKA distribution along nanowires under ion radiation
|
Yang, Yang
|
|
2018
|
340 |
C |
p. 300-307
|
artikel
|
| 22 |
Multiplication characteristics of a gas-cooled ADS with fast-thermal coupling configuration
|
Wang, Litao
|
|
2018
|
340 |
C |
p. 1-8
|
artikel
|
| 23 |
Numerical investigation on thermal status of a scaled-down suppression pool
|
Qu, Xiaohang
|
|
2018
|
340 |
C |
p. 183-192
|
artikel
|
| 24 |
Numerical simulation of bubble rising behavior in liquid LBE using diffuse interface method
|
Wang, Chuntao
|
|
2018
|
340 |
C |
p. 219-228
|
artikel
|
| 25 |
Numerical strategy for dynamic simulation of impacts on SFR fuel pins and experimental validation
|
Catterou, T.
|
|
2018
|
340 |
C |
p. 73-85
|
artikel
|
| 26 |
On-line refueling for the Advanced High Temperature Reactor (AHTR)
|
Avigni, P.
|
|
2018
|
340 |
C |
p. 166-182
|
artikel
|
| 27 |
Optimization and sensitivity analysis of the nitrogen Brayton cycle as a power conversion system for a sodium-cooled fast reactor
|
Park, Joo Hyun
|
|
2018
|
340 |
C |
p. 325-334
|
artikel
|
| 28 |
Performance of core thermocouples of FBTR – A technique for predicting accurate temperature for known transients in the presence of measurement delays
|
Sridhar, S.
|
|
2018
|
340 |
C |
p. 260-274
|
artikel
|
| 29 |
Prioritization of nuclear thermal-hydraulics researches
|
D'Auria, F.
|
|
2018
|
340 |
C |
p. 105-111
|
artikel
|
| 30 |
PRISM reference fuel design
|
Loewen, Eric
|
|
2018
|
340 |
C |
p. 40-53
|
artikel
|
| 31 |
Reactor dynamics of in-pin fuel motion in fast breeder reactors
|
Dubey, Anuj
|
|
2018
|
340 |
C |
p. 431-446
|
artikel
|
| 32 |
SARAX: A new code for fast reactor analysis part I: Methods
|
Zheng, Youqi
|
|
2018
|
340 |
C |
p. 421-430
|
artikel
|
| 33 |
Simulations of the dust behavior in the sampling and dust filters in the primary loop of HTR-10
|
Peng, Wei
|
|
2018
|
340 |
C |
p. 112-121
|
artikel
|
| 34 |
Stability characteristics of metal fueled fast reactor cores
|
Anuraj, V.L.
|
|
2018
|
340 |
C |
p. 318-324
|
artikel
|
| 35 |
STRUCTure-based URANS simulations of thermal mixing in T-junctions
|
Feng, Jinyong
|
|
2018
|
340 |
C |
p. 275-299
|
artikel
|
| 36 |
Subchannel modeling of single rod bowing in a bundle geometry
|
Mukin, Roman
|
|
2018
|
340 |
C |
p. 347-369
|
artikel
|
| 37 |
Transient boiling flow in 5 × 5 rod bundle under non-uniform rapid heating
|
Takiguchi, Hiroki
|
|
2018
|
340 |
C |
p. 447-456
|
artikel
|
| 38 |
Uncertainty analysis of condensation heat transfer benchmark using CFD code GASFLOW-MPI
|
Zhang, Han
|
|
2018
|
340 |
C |
p. 308-317
|
artikel
|
| 39 |
Validation of a closure model framework for turbulent bubbly two-phase flow in different flow situations
|
Krepper, Eckhard
|
|
2018
|
340 |
C |
p. 388-404
|
artikel
|
| 40 |
Validation of the MELCOR input model for a CANDU PHWR containment analysis by benchmarking against integrated leakage rate tests
|
Kim, Han-Chul
|
|
2018
|
340 |
C |
p. 201-218
|
artikel
|
| 41 |
Water-jacket reactor cavity cooling system concept to mitigate severe accident consequence of high temperature gas-cooled reactor
|
Lim, Hong Sik
|
|
2018
|
340 |
C |
p. 156-165
|
artikel
|
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