| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
ADORE: Alternative detector layout optimization for ROP system of CANDU reactors
|
Kastanya, Doddy Y.F.
|
|
2011
|
|
6 |
p. 708-716
9 p.
|
artikel
|
| 2 |
Advanced ePrometheus™ GNF fuel cycle optimization tool
|
Yilmaz, Serkan
|
|
2011
|
|
6 |
p. 562-565
4 p.
|
artikel
|
| 3 |
Advances on the research on nonlinear phenomena in boiling natural circulation loop
|
Goswami, N.
|
|
2011
|
|
6 |
p. 673-697
25 p.
|
artikel
|
| 4 |
A minimum hot excess core design strategy for ESBWR
|
Karve, Atul A.
|
|
2011
|
|
6 |
p. 571-582
12 p.
|
artikel
|
| 5 |
Analysis of flow coastdown for an MTR-pool type research reactor
|
Farhadi, Kazem
|
|
2010
|
|
6 |
p. 573-579
7 p.
|
artikel
|
| 6 |
Analysis of Ledinegg flow instability in natural circulation at supercritical pressure
|
Yu, Jiyang
|
|
2011
|
|
6 |
p. 775-779
5 p.
|
artikel
|
| 7 |
Analytical investigation and experimental application of the source modulation technique to measure ρ/β eff
|
Baeten, P.
|
|
2006
|
|
6 |
p. 550-558
9 p.
|
artikel
|
| 8 |
An MCNPX accelerator beam source
|
Durkee Jr., Joe W.
|
|
2010
|
|
6 |
p. 544-554
11 p.
|
artikel
|
| 9 |
A probabilistic study of the influence of parameter uncertainty on solutions of the neutron transport equation
|
Eaton, Matthew
|
|
2010
|
|
6 |
p. 580-588
9 p.
|
artikel
|
| 10 |
Benchmark of Advanced Burner Test Reactor model using MCNPX 2.6.0 and ERANOS 2.1
|
Allen, Kenneth
|
|
2011
|
|
6 |
p. 633-644
12 p.
|
artikel
|
| 11 |
Burnup-dependent core neutronics analysis and calculation of actinide and fission product inventories in discharged fuel of a material test research reactor
|
Ahmad, Siraj-ul-Islam
|
|
2006
|
|
6 |
p. 599-616
18 p.
|
artikel
|
| 12 |
BWR in-core fuel management optimization using parallel simulated annealing in FORMOSA-B
|
Hays, Ross
|
|
2011
|
|
6 |
p. 600-606
7 p.
|
artikel
|
| 13 |
BWR stability analyses with SIMULATE-3K benchmark against measured plant data
|
Grandi, Gerardo
|
|
2011
|
|
6 |
p. 583-592
10 p.
|
artikel
|
| 14 |
Comparison of thorium-based fuels with different fissile components in existing boiling water reactors
|
Insulander Björk, Klara
|
|
2011
|
|
6 |
p. 618-625
8 p.
|
artikel
|
| 15 |
COPERNICUS: A multi-cycle optimization code for nuclear fuel based on parallel simulated annealing with mixing of states
|
Kropaczek, David J.
|
|
2011
|
|
6 |
p. 554-561
8 p.
|
artikel
|
| 16 |
Cost efficiency analysis of disposal alternatives in Korea
|
Kim, S.K.
|
|
2011
|
|
6 |
p. 722-728
7 p.
|
artikel
|
| 17 |
Current status on the nuclear back-end fuel cycle R&D in Korea
|
Hwang, Y.S.
|
|
2007
|
|
6 |
p. 463-472
10 p.
|
artikel
|
| 18 |
Description of the shuffle design software MARLA
|
Knott, Dave
|
|
2011
|
|
6 |
p. 607-617
11 p.
|
artikel
|
| 19 |
Design and optimization of an equilibrium reload with MOX fuel with minor actinides
|
François, Juan-Luis
|
|
2011
|
|
6 |
p. 566-570
5 p.
|
artikel
|
| 20 |
Design of a permanent epithermal neutron irradiation site in the Syrian MNSR
|
Shaaban, Ismail.
|
|
2010
|
|
6 |
p. 569-572
4 p.
|
artikel
|
| 21 |
Design study of a modular dry storage facility for typical PWR spent fuel
|
Iqbal, Masood
|
|
2006
|
|
6 |
p. 487-494
8 p.
|
artikel
|
| 22 |
Development of a Visual System Analyzer based on reactor system analysis codes
|
Kim, Kyung Doo
|
|
2007
|
|
6 |
p. 452-462
11 p.
|
artikel
|
| 23 |
Editorial
|
Maldonado, G. Ivan
|
|
2011
|
|
6 |
p. 553-
1 p.
|
artikel
|
| 24 |
Editorial Board
|
|
|
2007
|
|
6 |
p. IFC-
1 p.
|
artikel
|
| 25 |
Editorial Board
|
|
|
2010
|
|
6 |
p. IFC-
1 p.
|
artikel
|
| 26 |
Editorial Board
|
|
|
2011
|
|
6 |
p. IFC-
1 p.
|
artikel
|
| 27 |
Evaluation of nuclide release scenarios for a hypothetical LILW repository
|
Lee, Youn-Myoung
|
|
2011
|
|
6 |
p. 760-774
15 p.
|
artikel
|
| 28 |
Exposing America: Comparative assessments of ionizing radiation doses to U.S. populations from nuclear and non-nuclear industries
|
Pennington, Charles W.
|
|
2007
|
|
6 |
p. 473-485
13 p.
|
artikel
|
| 29 |
Feynman-alpha experiment with stationary multiple emission sources
|
Kitamura, Y.
|
|
2006
|
|
6 |
p. 569-577
9 p.
|
artikel
|
| 30 |
Flow regime identification and volume fraction prediction in multiphase flows by means of gamma-ray attenuation and artificial neural networks
|
Salgado, César Marques
|
|
2010
|
|
6 |
p. 555-562
8 p.
|
artikel
|
| 31 |
Gain scheduled dynamic sliding mode control for nuclear steam generators
|
Ansarifar, G.R.
|
|
2011
|
|
6 |
p. 651-663
13 p.
|
artikel
|
| 32 |
Heat transfer of laminar flow in a channel in rolling motion
|
Yan, B.H.
|
|
2010
|
|
6 |
p. 596-600
5 p.
|
artikel
|
| 33 |
High-fidelity system modeling of advanced nuclear energy systems approaching a zero-nuclear-waste limit
|
Ames II, David E.
|
|
2011
|
|
6 |
p. 626-632
7 p.
|
artikel
|
| 34 |
Irradiation temperature, flux and spectrum effects
|
Ballesteros, A.
|
|
2011
|
|
6 |
p. 756-759
4 p.
|
artikel
|
| 35 |
Modelling and control strategy of the Italian LBE-XADS
|
Cammi, Antonio
|
|
2006
|
|
6 |
p. 578-589
12 p.
|
artikel
|
| 36 |
Modified COBRA-EN code to investigate thermal-hydraulic analysis of the Iranian VVER-1000 core
|
Safaei Arshi, S.
|
|
2010
|
|
6 |
p. 589-595
7 p.
|
artikel
|
| 37 |
Neutronics and material attractiveness for PWR thorium systems using monte carlo techniques
|
Trellue, Holly R.
|
|
2011
|
|
6 |
p. 698-707
10 p.
|
artikel
|
| 38 |
Neutronics assessment of the use of thorium fuels in current pressurized water reactors
|
Tsige-Tamirat, Haileyesus
|
|
2011
|
|
6 |
p. 717-721
5 p.
|
artikel
|
| 39 |
Nuclear nonproliferation and the future expansion of nuclear power
|
Yim, Man-Sung
|
|
2006
|
|
6 |
p. 504-524
21 p.
|
artikel
|
| 40 |
Nuclear power development in China and uranium demand forecast: Based on analysis of global current situation
|
Yan, Qiang
|
|
2011
|
|
6 |
p. 742-747
6 p.
|
artikel
|
| 41 |
Nuclear power plant commissioning experience
|
Zerger, Benoît
|
|
2011
|
|
6 |
p. 668-672
5 p.
|
artikel
|
| 42 |
On the basic properties of an iron-based simulated cermet inert matrix fuel, synthesized by a dry route in oxidizing conditions
|
Kamel, N.
|
|
2006
|
|
6 |
p. 590-598
9 p.
|
artikel
|
| 43 |
Optimum in-core power sharing with multicycle coupling effect
|
Yamamoto, Akio
|
|
2011
|
|
6 |
p. 593-599
7 p.
|
artikel
|
| 44 |
Performance evaluation/analysis of Pakistan Research Reactor-1 (PARR-1) current core configuration
|
Mahmood, Tayyab
|
|
2011
|
|
6 |
p. 729-735
7 p.
|
artikel
|
| 45 |
Recovery of deuterium from H–D gas mixture by thermal diffusion in the Frazier scheme
|
Yeh, Ho-Ming
|
|
2011
|
|
6 |
p. 645-650
6 p.
|
artikel
|
| 46 |
Reduced feed and discharge inventory strategy and proliferation resistance in natural uranium fueled research reactors
|
Khan, Mohammad Javed
|
|
2006
|
|
6 |
p. 477-486
10 p.
|
artikel
|
| 47 |
Review of research on flow instabilities in natural circulation boiling systems
|
Durga Prasad, Gonella V.
|
|
2007
|
|
6 |
p. 429-451
23 p.
|
artikel
|
| 48 |
Role of passive systems in advanced reactors
|
Nayak, A.K.
|
|
2007
|
|
6 |
p. 486-498
13 p.
|
artikel
|
| 49 |
Small PWR core design with coated particle based fuel with a novel composition
|
Hussain, Anwar
|
|
2010
|
|
6 |
p. 531-535
5 p.
|
artikel
|
| 50 |
Software safety analysis application of safety-related I&C systems in installation phase
|
Huang, Hui-Wen
|
|
2011
|
|
6 |
p. 736-741
6 p.
|
artikel
|
| 51 |
The neutronic aspects of U–9Mo as a LEU fuel for Low-power reactors
|
Albarhoum, M.
|
|
2010
|
|
6 |
p. 541-543
3 p.
|
artikel
|
| 52 |
Theoretical models of turbulent flow in rolling motion
|
Yan, Bing-huo
|
|
2010
|
|
6 |
p. 563-568
6 p.
|
artikel
|
| 53 |
The results of the irradiation experiment HELIOS
|
D’Agata, E.
|
|
2011
|
|
6 |
p. 748-755
8 p.
|
artikel
|
| 54 |
Thermal hydraulic analysis of the thorium-based advanced CANDU Reactor fuel channel
|
Yu, Jiyang
|
|
2006
|
|
6 |
p. 559-568
10 p.
|
artikel
|
| 55 |
Thermalhydraulics and safety aspects of the use of monolithic U-9Mo LEU fuel in the low-power reactors
|
Albarhoum, M.
|
|
2010
|
|
6 |
p. 536-540
5 p.
|
artikel
|
| 56 |
Time–scale BWR stability analysis using wavelet-based method
|
Nuñez-carrera, A.
|
|
2006
|
|
6 |
p. 540-549
10 p.
|
artikel
|
| 57 |
Treatment of UO2 pellets used for preparing fuel elements of HTR-10 followed by supercritical fluid extraction
|
Duan, Wuhua
|
|
2011
|
|
6 |
p. 664-667
4 p.
|
artikel
|
| 58 |
Two stochastic optimization algorithms applied to nuclear reactor core design
|
Sacco, Wagner F.
|
|
2006
|
|
6 |
p. 525-539
15 p.
|
artikel
|
| 59 |
Utilization of bentonite and zeolite in cementation of dry radioactive evaporator concentrate
|
Plecas, I.
|
|
2006
|
|
6 |
p. 495-503
9 p.
|
artikel
|
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