| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A comparative study of WIMSLIB group constants processed through NJOY'99 from ENDF/B-VI and JENDL-3.3 for 20Ca, 12Mg, 15P, 16S, 14Si, 22Ti, and 23V
|
Sarker, M.M.
|
|
2007
|
|
7 |
p. 529-533
5 p.
|
artikel
|
| 2 |
Activities for 4S USNRC licensing
|
Ishii, Kyoko
|
|
2011
|
|
7 |
p. 831-834
4 p.
|
artikel
|
| 3 |
Adaptive fuzzy system for degradation study in nuclear power plants' passive components
|
Guimarães, Antônio César Ferreira
|
|
2006
|
|
7 |
p. 655-663
9 p.
|
artikel
|
| 4 |
A model for release of fission products from a breached fuel plate under wet storage
|
Terremoto, L.A.A.
|
|
2008
|
|
7 |
p. 818-827
10 p.
|
artikel
|
| 5 |
A model for the analysis of pump start-up transients in Tehran Research Reactor
|
Farhadi, Kazem
|
|
2007
|
|
7 |
p. 499-510
12 p.
|
artikel
|
| 6 |
Analytical solution for two-group diffusion equations in a multilayered slab using Laplace Transform Technique
|
Lemos, R.S.M.
|
|
2008
|
|
7 |
p. 747-756
10 p.
|
artikel
|
| 7 |
An approach for evaluating fuel system applied in innovative nuclear energy system
|
Nakae, Nobuo
|
|
2011
|
|
7 |
p. 1039-1044
6 p.
|
artikel
|
| 8 |
A new algorithm for evaluation of the simplified gamma-ray shielding formulas
|
Guseinov, I.I.
|
|
2006
|
|
7 |
p. 680-685
6 p.
|
artikel
|
| 9 |
A novel method for transuranic fuel design
|
Guzmán, J.R.
|
|
2010
|
|
7 |
p. 689-697
9 p.
|
artikel
|
| 10 |
An overview of Eulerian–Lagrangian schemes applied to radionuclide transport in unsaturated porous media
|
Aquino, J.
|
|
2008
|
|
7 |
p. 774-787
14 p.
|
artikel
|
| 11 |
A numerical study of impact force caused by liquid droplet impingement onto a rigid wall
|
Li, Rui
|
|
2011
|
|
7 |
p. 881-885
5 p.
|
artikel
|
| 12 |
A parallel genetic algorithm with niching technique applied to a nuclear reactor core design optimization problem
|
Pereira, Cláudio M.N.A.
|
|
2008
|
|
7 |
p. 740-746
7 p.
|
artikel
|
| 13 |
Assessment of on-line burnup monitoring of pebble bed reactor fuel by passive neutron counting
|
Su, Bingjing
|
|
2006
|
|
7 |
p. 686-702
17 p.
|
artikel
|
| 14 |
Basic evaluation on material attractiveness of isotopic plutonium barrier
|
Permana, Sidik
|
|
2011
|
|
7 |
p. 958-963
6 p.
|
artikel
|
| 15 |
Choosing suitable type of research reactor for Mongolia
|
Odmaa, Sambuu
|
|
2011
|
|
7 |
p. 921-924
4 p.
|
artikel
|
| 16 |
Comparative studies of CERCER and CERMET fuels for EFIT from the viewpoint of core performance and safety
|
Chen, Xue-Nong
|
|
2011
|
|
7 |
p. 855-861
7 p.
|
artikel
|
| 17 |
Compatibility of FBR structural materials with supercritical carbon dioxide
|
Furukawa, T.
|
|
2011
|
|
7 |
p. 1050-1055
6 p.
|
artikel
|
| 18 |
Consistent multipoint kinetics for source-driven systems
|
Dulla, S.
|
|
2006
|
|
7 |
p. 617-628
12 p.
|
artikel
|
| 19 |
Control strategies for transients of hydrogen production plant in VHTR cogeneration systems
|
Sato, Hiroyuki
|
|
2011
|
|
7 |
p. 1009-1016
8 p.
|
artikel
|
| 20 |
Corrosion behavior of heat-treated Fe–Al coated steel in lead–bismuth eutectic under loading
|
Yamaki-Irisawa, Eriko
|
|
2011
|
|
7 |
p. 1066-1072
7 p.
|
artikel
|
| 21 |
Corrosion resistance of ceramics SiC and Si3N4 in flowing lead-bismuth eutectic
|
Takahashi, Minoru
|
|
2011
|
|
7 |
p. 1061-1065
5 p.
|
artikel
|
| 22 |
Cost estimation of the canisters for an HLW repository in Korea
|
Kim, S.K.
|
|
2007
|
|
7 |
p. 555-566
12 p.
|
artikel
|
| 23 |
Coupled thermal-hydraulics and neutron-physics analysis of SCWR with mixed spectrum core
|
Liu, X.J.
|
|
2010
|
|
7 |
p. 640-647
8 p.
|
artikel
|
| 24 |
Curing time effect on compressive strength and incremental leaching rates of 137Cs and 60Co in cement immobilized sludge
|
Plećaš, I.
|
|
2006
|
|
7 |
p. 629-633
5 p.
|
artikel
|
| 25 |
Current status and future plans of Advanced ORIENT Cycle strategy
|
Koyama, Shin-ichi
|
|
2011
|
|
7 |
p. 980-987
8 p.
|
artikel
|
| 26 |
Current status and innovative improvement of small commercial reactor in China
|
Shentu, Jun
|
|
2011
|
|
7 |
p. 842-845
4 p.
|
artikel
|
| 27 |
Densification of magnesia-based inert matrix fuels using asbestos waste-derived materials as a sintering additive
|
Miwa, Shuhei
|
|
2011
|
|
7 |
p. 1045-1049
5 p.
|
artikel
|
| 28 |
Design Study on Pb-208 Cooled CANDLE Burning Reactors toward Practical Application for Future Nuclear Energy Source
|
Okawa, Tsuyoshi
|
|
2011
|
|
7 |
p. 886-890
5 p.
|
artikel
|
| 29 |
Development of a comprehensive set of drift-flux constitutive models for pipes of various hydraulic diameters
|
Schlegel, Joshua
|
|
2010
|
|
7 |
p. 666-677
12 p.
|
artikel
|
| 30 |
Development of high temperature gas-cooled reactor (HTGR) fuel in Japan
|
Ueta, Shohei
|
|
2011
|
|
7 |
p. 788-793
6 p.
|
artikel
|
| 31 |
Development of hybrid reprocessing technology based on solvent extraction and pyro-chemical electrolysis
|
Ohmura, Hisao
|
|
2011
|
|
7 |
p. 940-943
4 p.
|
artikel
|
| 32 |
Dose rate reduction in the Pakistan Research Reactor-1 by the utilization of high-density low enriched uranium fuel
|
Ahmed, Rizwan
|
|
2006
|
|
7 |
p. 634-646
13 p.
|
artikel
|
| 33 |
Editorial Board
|
|
|
2007
|
|
7 |
p. IFC-
1 p.
|
artikel
|
| 34 |
Editorial Board
|
|
|
2008
|
|
7 |
p. IFC-
1 p.
|
artikel
|
| 35 |
Editorial Board
|
|
|
2010
|
|
7 |
p. IFC-
1 p.
|
artikel
|
| 36 |
Editorial Board
|
|
|
2011
|
|
7 |
p. IFC-
1 p.
|
artikel
|
| 37 |
Effect of minor actinides doping on plutonium produced in large-scale FBR blanket
|
Meiliza, Yoshitalia
|
|
2011
|
|
7 |
p. 964-968
5 p.
|
artikel
|
| 38 |
Energy sustainability and economic stability with Breed and Burn reactors
|
Greenspan, Ehud
|
|
2011
|
|
7 |
p. 794-799
6 p.
|
artikel
|
| 39 |
Estimation of self-control capability of a sodium-cooled fast reactor
|
Seong, Seung-Hwan
|
|
2010
|
|
7 |
p. 655-665
11 p.
|
artikel
|
| 40 |
Evaluation of implementation of thorium fuel cycle with LWR and MSR
|
Kamei, Takashi
|
|
2011
|
|
7 |
p. 820-824
5 p.
|
artikel
|
| 41 |
Evolutionary design of reactor vessel assembly for liquid metal cooled battery
|
Son, Hyung Min
|
|
2011
|
|
7 |
p. 825-830
6 p.
|
artikel
|
| 42 |
Extension of the FRAPCON-3.3 creep model to dry storage conditions
|
Herranz, L.E.
|
|
2010
|
|
7 |
p. 634-639
6 p.
|
artikel
|
| 43 |
Extension of the SIMMER cross-section processing scheme for core degradation analyses of thermal systems
|
Gabrielli, F.
|
|
2011
|
|
7 |
p. 867-873
7 p.
|
artikel
|
| 44 |
Extraction mechanisms of uranyl ions by 1-butyl-3-methylimidazolium nonafluorobutanesulfonate containing N-dodecyl-2-pyrrolidone
|
Asanuma, Noriko
|
|
2011
|
|
7 |
p. 944-947
4 p.
|
artikel
|
| 45 |
Fabrication and characterization of silicon nitride-based inert matrix fuels sintered with magnesium silicates
|
Usuki, Toshiyuki
|
|
2011
|
|
7 |
p. 1078-1081
4 p.
|
artikel
|
| 46 |
Feasibility of uranium spallation target in accelerator-driven system
|
Ismailov, Kairat
|
|
2011
|
|
7 |
p. 925-929
5 p.
|
artikel
|
| 47 |
Gamma-ray shielding properties of concrete including barite at different energies
|
Akkurt, I.
|
|
2010
|
|
7 |
p. 620-623
4 p.
|
artikel
|
| 48 |
Generalized discrete ordinates methods for neutral particle transport problems in slab geometry
|
Segatto, Cynthia F.
|
|
2008
|
|
7 |
p. 788-794
7 p.
|
artikel
|
| 49 |
Improved lumped model for thermal analysis of high burn-up nuclear fuel rods
|
Pontedeiro, Auro C.
|
|
2008
|
|
7 |
p. 767-773
7 p.
|
artikel
|
| 50 |
Improvement in deuterium recovery from water–isotopes mixture by thermal diffusion in the concentric-tube device of branch columns
|
Yeh, Ho-Ming
|
|
2010
|
|
7 |
p. 628-633
6 p.
|
artikel
|
| 51 |
In-situ observation technique of electrodeposition reaction by X-ray from synchrotron source
|
Matsuura, Haruaki
|
|
2011
|
|
7 |
p. 930-934
5 p.
|
artikel
|
| 52 |
Irradiation analysis of U, Am samples irradiated in experimental fast reactor “Joyo” for protected plutonium production in fast breeder reactor blanket
|
Sagara, Hiroshi
|
|
2011
|
|
7 |
p. 952-957
6 p.
|
artikel
|
| 53 |
Light Water Breeding with Nitride Fuel
|
Feng, Bo
|
|
2011
|
|
7 |
p. 862-866
5 p.
|
artikel
|
| 54 |
Lithium isotope effects upon electrochemical lithium insertion to host material from ionic liquid medium
|
Saito, Shun
|
|
2011
|
|
7 |
p. 999-1004
6 p.
|
artikel
|
| 55 |
Loss of coolant accident analyses on Tehran research reactor by RELAP5/MOD3.2 code
|
Hedayat, Afshin
|
|
2007
|
|
7 |
p. 511-528
18 p.
|
artikel
|
| 56 |
Mathematical modelling of immobilization of radionuclides 137Cs and 60Co in concrete matrix
|
Plecas, I.B.
|
|
2010
|
|
7 |
p. 685-688
4 p.
|
artikel
|
| 57 |
Mutual separation of strontium, cerium, and uranium using pressure-driven flow in 100nm-sized nanofluidic channels
|
Tsukahara, Takehiko
|
|
2011
|
|
7 |
p. 935-939
5 p.
|
artikel
|
| 58 |
Nuclear burning wave in fast reactor with mixed Th-U fuel
|
Fomin, S.P.
|
|
2011
|
|
7 |
p. 800-805
6 p.
|
artikel
|
| 59 |
Nuclear carbonization and gasification of biomass for effective removal of atmospheric CO2
|
Hori, Masao
|
|
2011
|
|
7 |
p. 1022-1026
5 p.
|
artikel
|
| 60 |
Nuclear power technologies at the stage of sustainable nuclear power development
|
Toshinsky, G.I.
|
|
2011
|
|
7 |
p. 782-787
6 p.
|
artikel
|
| 61 |
Numerical analysis of supercritical water heat transfer in horizontal circular tube
|
Zhang, Bo
|
|
2010
|
|
7 |
p. 678-684
7 p.
|
artikel
|
| 62 |
Numerical investigation of bent pipe flows at transitional Reynolds number
|
Pellegrini, Marco
|
|
2011
|
|
7 |
p. 916-920
5 p.
|
artikel
|
| 63 |
Numerical studies of nuclear traveling waves in a supercritical water cooled fast reactor
|
Zhang, Dalin
|
|
2011
|
|
7 |
p. 806-813
8 p.
|
artikel
|
| 64 |
On the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems
|
Neto, M. Mattar
|
|
2008
|
|
7 |
p. 800-817
18 p.
|
artikel
|
| 65 |
Open issues in reactor dosimetry
|
Ballesteros, A.
|
|
2010
|
|
7 |
p. 615-619
5 p.
|
artikel
|
| 66 |
Optimization of the neutronics design of MNSRs
|
Albarhoum, M.
|
|
2010
|
|
7 |
p. 624-627
4 p.
|
artikel
|
| 67 |
Options for the interim storage of IEA-R1 research reactor spent fuels
|
Silva, A.T.
|
|
2008
|
|
7 |
p. 836-844
9 p.
|
artikel
|
| 68 |
Performance analysis of active carbon recycling energy system
|
Kato, Yukitaka
|
|
2011
|
|
7 |
p. 1017-1021
5 p.
|
artikel
|
| 69 |
Phenomenological prediction of CHF under boiling water reactor (BWR) conditions
|
Chandraker, D.K.
|
|
2011
|
|
7 |
p. 874-880
7 p.
|
artikel
|
| 70 |
Plant designing of ion exchange chemical uranium enrichment and its non-proliferation aspects
|
Kawakami, Fumiaki
|
|
2011
|
|
7 |
p. 974-979
6 p.
|
artikel
|
| 71 |
Polonium decontamination performance of stainless steel mesh filter for lead alloy-cooled reactors
|
Obara, Toru
|
|
2011
|
|
7 |
p. 1056-1060
5 p.
|
artikel
|
| 72 |
Power control of CANDLE reactor by coolant flow rate
|
Nakayama, Shinsuke
|
|
2011
|
|
7 |
p. 891-894
4 p.
|
artikel
|
| 73 |
Precipitation ability to U(IV) and stability of 1,3-dimethyl-2-imidazolidone for selective precipitation of U(VI) in nitric acid media
|
Nogami, Masanobu
|
|
2011
|
|
7 |
p. 948-951
4 p.
|
artikel
|
| 74 |
Preface
|
Barros, Ricardo C.
|
|
2008
|
|
7 |
p. 729-
1 p.
|
artikel
|
| 75 |
Preface
|
Sekimoto, Hiroshi
|
|
2011
|
|
7 |
p. 781-
1 p.
|
artikel
|
| 76 |
Prevention and mitigation of severe accident developments and recriticalities in advanced fast reactor systems
|
Maschek, Werner
|
|
2011
|
|
7 |
p. 835-841
7 p.
|
artikel
|
| 77 |
Qualification program of research reactor fuels manufactured at IPEN–CNEN/SP
|
Silva, A.T.
|
|
2008
|
|
7 |
p. 795-799
5 p.
|
artikel
|
| 78 |
Radiotoxicity of transuranics recycling in heterogeneous fuel assemblies for boiling water reactors
|
Guzmán, J.R.
|
|
2010
|
|
7 |
p. 698-706
9 p.
|
artikel
|
| 79 |
Reactivity enhancement of chemical materials used in packed bed reactor of chemical heat pump
|
Tae Kim, Seon
|
|
2011
|
|
7 |
p. 1027-1033
7 p.
|
artikel
|
| 80 |
Reactivity feedback and control margins in natural uranium fueled and heavy water moderated nuclear research reactors
|
Khan, Mohammad Javed
|
|
2006
|
|
7 |
p. 647-654
8 p.
|
artikel
|
| 81 |
Reactor physics ideas for large scale utilization of thorium in gas cooled reactors
|
Srivastava, Argala
|
|
2011
|
|
7 |
p. 814-819
6 p.
|
artikel
|
| 82 |
Recovery of minor actinides from spent molten salt waste and decontamination of molten salt waste
|
Suzuki, Tatsuya
|
|
2011
|
|
7 |
p. 969-973
5 p.
|
artikel
|
| 83 |
Removing Eddy-Current probe wobble noise from steam generator tubes testing using Wavelet Transform
|
Lopez, L.A.N.M.
|
|
2008
|
|
7 |
p. 828-835
8 p.
|
artikel
|
| 84 |
Scale removal oxidation behavior of metal in supercritical water modeled by cellular automaton
|
Lan, Kuan-Che
|
|
2011
|
|
7 |
p. 1034-1038
5 p.
|
artikel
|
| 85 |
Selective extraction of perrehnate anion in nitric acid solution using 2,2′-(methylimino)bis(N,N′-diethylacetamide) as an extractant
|
Ali, Mohammad C.
|
|
2011
|
|
7 |
p. 1005-1008
4 p.
|
artikel
|
| 86 |
Simulation of two regime sodium flows in a parallel plate channel during buoyancy-driven flow
|
Khakim, Azizul
|
|
2011
|
|
7 |
p. 909-915
7 p.
|
artikel
|
| 87 |
Small-sized high temperature reactor (MHR-50) for electricity generation: Plant concept and characteristics
|
Shimizu, Katsusuke
|
|
2011
|
|
7 |
p. 846-854
9 p.
|
artikel
|
| 88 |
Sol–gel preparation and characterization of Ni–YSZ cermet electrode
|
Ohga, Emi
|
|
2007
|
|
7 |
p. 546-554
9 p.
|
artikel
|
| 89 |
Static and dynamic sensitivity analysis of corrosion product activity in primary coolant circuits of pressurized water reactors
|
Mirza, Sikander M.
|
|
2010
|
|
7 |
p. 648-654
7 p.
|
artikel
|
| 90 |
Structural investigation of thorium in molten lithium–calcium fluoride mixtures for salt treatment process in molten salt reactor
|
Numakura, Masahiko
|
|
2011
|
|
7 |
p. 994-998
5 p.
|
artikel
|
| 91 |
Study of the Sm-153 seeds degradation and evaluation of the absorbed dose in rabbit's liver implants
|
Campos, Tarcísio P.R.
|
|
2008
|
|
7 |
p. 757-766
10 p.
|
artikel
|
| 92 |
Study on corrosion of welded steel for LBE-cooled fast reactors
|
Mustari, Asril Pramutadi Andi
|
|
2011
|
|
7 |
p. 1073-1077
5 p.
|
artikel
|
| 93 |
Study on fragmentation behavior of liquid lead alloy droplet in water
|
Sa, Rongyuan
|
|
2011
|
|
7 |
p. 895-901
7 p.
|
artikel
|
| 94 |
The IRIS pressurizer: Simulation of out-surge transients and optimization procedure to design scaled experiments
|
Botelho, David A.
|
|
2008
|
|
7 |
p. 730-739
10 p.
|
artikel
|
| 95 |
Thermochemical safety evaluation of tertiary pyridine resin for the application to multi-functional reprocessing process “Adv.-ORIENT cycle development”
|
Sato, Yoshihiko
|
|
2011
|
|
7 |
p. 988-993
6 p.
|
artikel
|
| 96 |
The thorium molten salt reactor: Moving on from the MSBR
|
Mathieu, L.
|
|
2006
|
|
7 |
p. 664-679
16 p.
|
artikel
|
| 97 |
TRU burning by dual tier system of LWR-SFR
|
Ikeda, Kazumi
|
|
2011
|
|
7 |
p. 902-908
7 p.
|
artikel
|
| 98 |
Uncertainty analyses of hot channel calculations – Determination of the number of failed fuel rods
|
Panka, I.
|
|
2007
|
|
7 |
p. 534-545
12 p.
|
artikel
|
| 99 |
Validation study of the Monte Carlo code MVP for analysis of two-region TCA critical experiments with PWR-type MOX fuels
|
Rahman, Mafizur
|
|
2006
|
|
7 |
p. 703-726
24 p.
|
artikel
|
| 100 |
Verification, validation and uncertainty quantification in multi-physics modeling for nuclear reactor design and safety analysis
|
Avramova, Maria N.
|
|
2010
|
|
7 |
p. 601-614
14 p.
|
artikel
|
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