nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
Advanced heat exchanger development for molten salts
|
Sabharwall, Piyush |
|
2014 |
280 |
C |
p. 42-56 15 p. |
artikel |
2 |
A feasibility study on the criticality control method using radioactive vitrified forms for spent fuel storage
|
Kim, Song Hyun |
|
2014 |
280 |
C |
p. 644-650 7 p. |
artikel |
3 |
Analysis of steady turbulent triple jet flow with temperature difference
|
Nouali, Nassira |
|
2014 |
280 |
C |
p. 8-20 13 p. |
artikel |
4 |
An analysis on the severe accident progression with operator recovery actions
|
Vo, T.H. |
|
2014 |
280 |
C |
p. 429-439 11 p. |
artikel |
5 |
Application of RCC-MR for the structural design of tube sheet of intermediate heat exchanger for a sodium cooled fast reactor
|
Gupta, Suman |
|
2014 |
280 |
C |
p. 181-200 20 p. |
artikel |
6 |
A review of modern advances in analyses and applications of single-phase natural circulation loop in nuclear thermal hydraulics
|
Basu, Dipankar N. |
|
2014 |
280 |
C |
p. 326-348 23 p. |
artikel |
7 |
A review of the current thermal-hydraulic modeling of the Jules Horowitz Reactor: A loss of flow accident analysis
|
Pegonen, R. |
|
2014 |
280 |
C |
p. 294-304 11 p. |
artikel |
8 |
Automatic X-ray inspection for the HTR-PM spherical fuel elements
|
Yi, DU |
|
2014 |
280 |
C |
p. 144-149 6 p. |
artikel |
9 |
Brittle fracture of T91 steel in liquid lead–bismuth eutectic alloy
|
Ye, Changqing |
|
2014 |
280 |
C |
p. 680-685 6 p. |
artikel |
10 |
Burn-up credit in criticality safety of PWR spent fuel
|
Mahmoud, Rowayda F. |
|
2014 |
280 |
C |
p. 628-633 6 p. |
artikel |
11 |
CMFD and GPU acceleration on method of characteristics for hexagonal cores
|
Han, Yu |
|
2014 |
280 |
C |
p. 210-222 13 p. |
artikel |
12 |
Comparative CFD analyses of liquid metal cooled reactor for lunar surface power
|
Schriener, Timothy M. |
|
2014 |
280 |
C |
p. 105-121 17 p. |
artikel |
13 |
Correlation for steam–graphite reaction
|
Stempniewicz, M.M. |
|
2014 |
280 |
C |
p. 285-293 9 p. |
artikel |
14 |
Corrosion behaviour of 12Cr-ODS steel in molten lead
|
Di Gabriele, Fosca |
|
2014 |
280 |
C |
p. 69-75 7 p. |
artikel |
15 |
Creep-rupture tests on chromium-containing conventional and ODS steels in oxygen-controlled Pb and air at 650°C
|
Yurechko, Mariya |
|
2014 |
280 |
C |
p. 686-696 11 p. |
artikel |
16 |
Cross section systematics of (d,p) reactions at 8.5MeV
|
Yiğit, M. |
|
2014 |
280 |
C |
p. 37-41 5 p. |
artikel |
17 |
Design features and cost reduction potential of JSFR
|
Katoh, Atsushi |
|
2014 |
280 |
C |
p. 586-597 12 p. |
artikel |
18 |
Development of a mixed oxide fuel pin performance analysis code “CEDAR”: Models and analyses of fuel pin irradiation behavior
|
Uwaba, Tomoyuki |
|
2014 |
280 |
C |
p. 27-36 10 p. |
artikel |
19 |
Effect of thermal aging on the leak-before-break analysis of nuclear primary pipes
|
Lv, Xuming |
|
2014 |
280 |
C |
p. 493-500 8 p. |
artikel |
20 |
Effects of fracture toughness curves of ASME Section XI–Appendix G on a reactor pressure vessel under pressure–temperature limit operation
|
Chou, Hsoung-Wei |
|
2014 |
280 |
C |
p. 404-412 9 p. |
artikel |
21 |
Effects of RCP trip when recovering HPSI during LOCA in a Westinghouse PWR
|
Montero-Mayorga, Javier |
|
2014 |
280 |
C |
p. 389-403 15 p. |
artikel |
22 |
Estimation of reactor protection system software failure probability considering undetected faults
|
Khalaquzzaman, M. |
|
2014 |
280 |
C |
p. 201-209 9 p. |
artikel |
23 |
Experimental investigation of countercurrent flow limitation (CCFL) in a large-diameter hot-leg geometry: A detailed description of CCFL mechanisms, flow patterns and high-quality HSC imaging of the interfacial structure in a 1/3.9 scale of PWR geometry
|
Al Issa, S. |
|
2014 |
280 |
C |
p. 550-563 14 p. |
artikel |
24 |
Experimental investigation on the natural convection flow in pool boiling
|
Kim, Seok |
|
2014 |
280 |
C |
p. 349-361 13 p. |
artikel |
25 |
Experimental study on heat transfer of supercritical Freon flowing upward in a circular tube
|
Zhang, Siyu |
|
2014 |
280 |
C |
p. 305-315 11 p. |
artikel |
26 |
Experimental study on the transient response of passive decay heat removal system
|
Vinod, V. |
|
2014 |
280 |
C |
p. 564-569 6 p. |
artikel |
27 |
Finite element modelling of the effect of temperature and neutron dose on the fracture behaviour of nuclear reactor graphite bricks
|
Wadsworth, M. |
|
2014 |
280 |
C |
p. 1-7 7 p. |
artikel |
28 |
Fretting of fuel cladding materials for Pb cooled fast reactors—Approach to long term prediction using fretting maps
|
Del Giacco, Mattia |
|
2014 |
280 |
C |
p. 697-703 7 p. |
artikel |
29 |
FSI effects and seismic performance evaluation of water storage tank of AP1000 subjected to earthquake loading
|
Zhao, Chunfeng |
|
2014 |
280 |
C |
p. 372-388 17 p. |
artikel |
30 |
Global variance reduction for Monte Carlo reactor physics calculations
|
Zhang, Qiong |
|
2014 |
280 |
C |
p. 76-85 10 p. |
artikel |
31 |
Influence of surface roughness on the corrosion behavior of Alloy 690TT in PWR primary water
|
Seo, Myung Ji |
|
2014 |
280 |
C |
p. 62-68 7 p. |
artikel |
32 |
Integrated deterministic and probabilistic safety assessment: Concepts, challenges, research directions
|
Zio, Enrico |
|
2014 |
280 |
C |
p. 413-419 7 p. |
artikel |
33 |
Integrity analysis of a reactor pressure vessel with quasi laminar flaws subjected to pressurized thermal shocks
|
González-Albuixech, Vicente Francisco |
|
2014 |
280 |
C |
p. 464-472 9 p. |
artikel |
34 |
International benchmark study of advanced thermal hydraulic safety analysis codes against measurements on IEA-R1 research reactor
|
Hainoun, A. |
|
2014 |
280 |
C |
p. 233-250 18 p. |
artikel |
35 |
Long term operation of nuclear power plants – IAEA SALTO peer review service and its results
|
Krivanek, Robert |
|
2014 |
280 |
C |
p. 99-104 6 p. |
artikel |
36 |
Material challenges for advanced reactors
|
Riznic, Jovica |
|
2014 |
280 |
C |
p. 651- 1 p. |
artikel |
37 |
Memory effect and recoverability of passive film degradation of Alloy 800 in simulated crevice chemistry
|
Fan, Hongqiang |
|
2014 |
280 |
C |
p. 57-61 5 p. |
artikel |
38 |
Modification and application of water film model in COCOSYS for PWR's passive containment cooling
|
Huang, Xi |
|
2014 |
280 |
C |
p. 251-261 11 p. |
artikel |
39 |
New gadolinium based glasses for gamma-rays shielding materials
|
Kaewjang, S. |
|
2014 |
280 |
C |
p. 21-26 6 p. |
artikel |
40 |
Numerical investigation on a jet pump evolving liquid lead for GEN-IV reactors
|
Mangialardo, Andrea |
|
2014 |
280 |
C |
p. 608-618 11 p. |
artikel |
41 |
Numerical simulation of flow and mixing in ROCOM facility using uniform and non-uniform inlet flow velocity profiles
|
Boumaza, M. |
|
2014 |
280 |
C |
p. 362-371 10 p. |
artikel |
42 |
On applicability of plate and shell heat exchangers for steam generation in naval PWR
|
Freire, Luciano Ondir |
|
2014 |
280 |
C |
p. 619-627 9 p. |
artikel |
43 |
On-power detection of wall-thinned defects using lock-in infrared thermography
|
Yoo, Kwae Hwan |
|
2014 |
280 |
C |
p. 542-549 8 p. |
artikel |
44 |
Oxidation behavior of austenitic stainless steels as fuel cladding candidate materials for SCWR in superheated steam
|
Abe, Hiroshi |
|
2014 |
280 |
C |
p. 652-660 9 p. |
artikel |
45 |
Oxidation/dissolution of ferritic ODS steels in static lead with various oxygen content at 650°C
|
Tsisar, Valentyn |
|
2014 |
280 |
C |
p. 673-679 7 p. |
artikel |
46 |
Particle Swarm Optimization to the U-tube steam generator in the nuclear power plant
|
Ibrahim, Wesam Zakaria |
|
2014 |
280 |
C |
p. 94-98 5 p. |
artikel |
47 |
Performance of 9% Cr steels in flowing lead-bismuth eutectic at 450 and 550°C, and 10−6 mass% dissolved oxygen
|
Schroer, Carsten |
|
2014 |
280 |
C |
p. 661-672 12 p. |
artikel |
48 |
Process heat cogeneration using a high temperature reactor
|
Alonso, Gustavo |
|
2014 |
280 |
C |
p. 137-143 7 p. |
artikel |
49 |
Radiation shielding and effective atomic number studies in different types of shielding concretes, lead base and non-lead base glass systems for total electron interaction: A comparative study
|
Kurudirek, Murat |
|
2014 |
280 |
C |
p. 440-448 9 p. |
artikel |
50 |
Radioactive airborne effluents and the environmental impact assessment of CAP1400 nuclear power plant under normal operation
|
Zhang, Qiong |
|
2014 |
280 |
C |
p. 579-585 7 p. |
artikel |
51 |
Reactivity control system of a passively safe thorium breeder pebble bed reactor
|
Wols, F.J. |
|
2014 |
280 |
C |
p. 598-607 10 p. |
artikel |
52 |
Reliability study of a special decay heat removal system of a gas-cooled fast reactor demonstrator
|
Burgazzi, Luciano |
|
2014 |
280 |
C |
p. 473-480 8 p. |
artikel |
53 |
Robust filtering for dynamic compensation of self-powered neutron detectors
|
Peng, Xingjie |
|
2014 |
280 |
C |
p. 122-129 8 p. |
artikel |
54 |
Safety goals for seismic and tsunami risks: Lessons learned from the Fukushima Daiichi disaster
|
Saji, Genn |
|
2014 |
280 |
C |
p. 449-463 15 p. |
artikel |
55 |
SCANAIR: A transient fuel performance code
|
Moal, Alain |
|
2014 |
280 |
C |
p. 150-171 22 p. |
artikel |
56 |
SCANAIR a transient fuel performance code Part two: Assessment of modelling capabilities
|
Georgenthum, Vincent |
|
2014 |
280 |
C |
p. 172-180 9 p. |
artikel |
57 |
Short-term pressure and temperature MSLB response analyses for large dry containment of the Maanshan nuclear power station
|
Dai, Liang-Che |
|
2014 |
280 |
C |
p. 86-93 8 p. |
artikel |
58 |
Signal de-noising methods for fault diagnosis and troubleshooting at CANDU® stations
|
Nasimi, Elnara |
|
2014 |
280 |
C |
p. 481-492 12 p. |
artikel |
59 |
Sodium-cooled fast reactor (SFR) fuel assembly design with graphite-moderating rods to reduce the sodium void reactivity coefficient
|
Won, Jong Hyuck |
|
2014 |
280 |
C |
p. 223-232 10 p. |
artikel |
60 |
Structural integrity assessment and stress measurement of CHASNUPP-1 fuel assembly
|
Waseem, |
|
2014 |
280 |
C |
p. 130-136 7 p. |
artikel |
61 |
Structural performance of an IP2 package in free drop test conditions: Numerical and experimental evaluations
|
Lo Frano, Rosa |
|
2014 |
280 |
C |
p. 634-643 10 p. |
artikel |
62 |
Study of clad ballooning and rupture behavior of fuel pins of Indian PHWR under simulated LOCA condition
|
Sawarn, Tapan K. |
|
2014 |
280 |
C |
p. 501-510 10 p. |
artikel |
63 |
Surface energy equation for heat transfer process in a pebble fuel
|
Espinosa-Paredes, G. |
|
2014 |
280 |
C |
p. 269-284 16 p. |
artikel |
64 |
The challenge of modeling fuel–coolant interaction: Part II – Steam explosion
|
Meignen, Renaud |
|
2014 |
280 |
C |
p. 528-541 14 p. |
artikel |
65 |
The challenge of modeling fuel–coolant interaction: Part I – Premixing
|
Meignen, Renaud |
|
2014 |
280 |
C |
p. 511-527 17 p. |
artikel |
66 |
The thermal performance of a loop-type heat pipe for passively removing residual heat from spent fuel pool
|
Xiong, Zhenqin |
|
2014 |
280 |
C |
p. 262-268 7 p. |
artikel |
67 |
Transient dryout prediction using a computationally efficient method for sub-channel film-flow analysis
|
Adamsson, C. |
|
2014 |
280 |
C |
p. 316-325 10 p. |
artikel |
68 |
Transient refractory material dissolution by a volumetrically-heated melt
|
Seiler, Jean Marie |
|
2014 |
280 |
C |
p. 420-428 9 p. |
artikel |
69 |
Zinc corrosion after loss-of-coolant accidents in pressurized water reactors – Physicochemical effects
|
Kryk, Holger |
|
2014 |
280 |
C |
p. 570-578 9 p. |
artikel |