| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A blueprint for GNEP advanced burner reactor startup fuel fabrication facility
|
Khericha, S.T.
|
|
2011
|
241 |
1 |
p. 386-394
9 p.
|
artikel
|
| 2 |
A diagnostic system for identifying accident conditions in a nuclear reactor
|
Santhosh, T.V.
|
|
2011
|
241 |
1 |
p. 177-184
8 p.
|
artikel
|
| 3 |
Aerosol retention in the flooded steam generator bundle during SGTR
|
Lind, Terttaliisa
|
|
2011
|
241 |
1 |
p. 357-365
9 p.
|
artikel
|
| 4 |
Air-ingress analysis: Part 2—Computational fluid dynamic models
|
Oh, Chang H.
|
|
2011
|
241 |
1 |
p. 213-225
13 p.
|
artikel
|
| 5 |
Air-ingress analysis: Part 1. Theoretical approach
|
Oh, Chang H.
|
|
2011
|
241 |
1 |
p. 203-212
10 p.
|
artikel
|
| 6 |
A possibility of miniaturized fusion and fission hybrid reaction core with positive fusion yield
|
Mayburd, Anatoly
|
|
2011
|
241 |
1 |
p. 59-66
8 p.
|
artikel
|
| 7 |
Behavior of HPC nuclear waste disposal structures in leaching environment
|
Sellier, A.
|
|
2011
|
241 |
1 |
p. 402-414
13 p.
|
artikel
|
| 8 |
CFD modeling and thermal-hydraulic analysis for the passive decay heat removal of a sodium-cooled fast reactor
|
Hung, T.C.
|
|
2011
|
241 |
1 |
p. 425-432
8 p.
|
artikel
|
| 9 |
Comparative study of fast critical burner reactors and subcritical accelerator driven systems and the impact on transuranics inventory in a regional fuel cycle
|
Romanello, V.
|
|
2011
|
241 |
1 |
p. 433-443
11 p.
|
artikel
|
| 10 |
Comparison of advanced fast reactor pool and loop configurations from the viewpoint of construction cost
|
Chikazawa, Yoshitaka
|
|
2011
|
241 |
1 |
p. 378-385
8 p.
|
artikel
|
| 11 |
Concept and safety studies of an integrated pyroprocess facility
|
You, Gil-Sung
|
|
2011
|
241 |
1 |
p. 415-424
10 p.
|
artikel
|
| 12 |
Delayed gamma power measurement for sodium-cooled fast reactors
|
Coulon, R.
|
|
2011
|
241 |
1 |
p. 339-348
10 p.
|
artikel
|
| 13 |
Development of an integrated methodology in support of remaining life assessment of Co-60 based gamma irradiation facilities
|
Varde, P.V.
|
|
2011
|
241 |
1 |
p. 328-338
11 p.
|
artikel
|
| 14 |
Dynamics of droplet breakup through a grid spacer in a rod bundle
|
Cheung, F.B.
|
|
2011
|
241 |
1 |
p. 236-244
9 p.
|
artikel
|
| 15 |
Effect of TRU fuel loading on core performance and plutonium production of FBR
|
Permana, Sidik
|
|
2011
|
241 |
1 |
p. 101-117
17 p.
|
artikel
|
| 16 |
Effects of slip and separation on seismic SSI response of nuclear reactor building
|
Saxena, Navjeev
|
|
2011
|
241 |
1 |
p. 12-17
6 p.
|
artikel
|
| 17 |
Evaluation of prestress losses in nuclear reactor containments
|
Lundqvist, Peter
|
|
2011
|
241 |
1 |
p. 168-176
9 p.
|
artikel
|
| 18 |
Experimental investigation on self-leveling behavior in debris beds
|
Zhang, Bin
|
|
2011
|
241 |
1 |
p. 366-377
12 p.
|
artikel
|
| 19 |
Finite integral transform method to solve asymmetric heat conduction in a multilayer annulus with time-dependent boundary conditions
|
Singh, Suneet
|
|
2011
|
241 |
1 |
p. 144-154
11 p.
|
artikel
|
| 20 |
Fluid–structure interaction analysis for pressurizer surge line subjected to thermal stratification
|
Kang, Dong Gu
|
|
2011
|
241 |
1 |
p. 257-269
13 p.
|
artikel
|
| 21 |
Fuel rod-to-support contact pressure and stress measurement for CHASNUPP-1(PWR) fuel
|
Waseem,
|
|
2011
|
241 |
1 |
p. 32-38
7 p.
|
artikel
|
| 22 |
Gamma spectrometry inspection of TRIGA MARK II fuel using caesium isotopes
|
Karimzadeh, S.
|
|
2011
|
241 |
1 |
p. 118-123
6 p.
|
artikel
|
| 23 |
How to effectively compute the reliability of a thermal–hydraulic nuclear passive system
|
Zio, E.
|
|
2011
|
241 |
1 |
p. 310-327
18 p.
|
artikel
|
| 24 |
Improvement of the one-dimensional dissolved-solute convection equation using the QUICKEST–ULTIMATE algorithm
|
Bertolotto, D.
|
|
2011
|
241 |
1 |
p. 245-256
12 p.
|
artikel
|
| 25 |
Individual pebble temperature peaking factor due to local pebble arrangement in a pebble bed reactor core
|
Sobes, Vladimir
|
|
2011
|
241 |
1 |
p. 124-133
10 p.
|
artikel
|
| 26 |
Inferring the temperature dependence of Beremin cleavage model parameters from the Master Curve
|
Cao, Yupeng
|
|
2011
|
241 |
1 |
p. 39-45
7 p.
|
artikel
|
| 27 |
Inverse of Wallin's relation for the effect of strain rate on the ASTM E-1921 reference temperature and its application to reference temperature estimation from Charpy tests
|
Sreenivasan, P.R.
|
|
2011
|
241 |
1 |
p. 67-81
15 p.
|
artikel
|
| 28 |
Investigating the burning characteristics of electric cables used in the nuclear power plant by way of 3-D transient FDS code
|
Ferng, Y.M.
|
|
2011
|
241 |
1 |
p. 88-94
7 p.
|
artikel
|
| 29 |
Load cell monitoring in Gas Centrifuge Enrichment Plants: Potentialities for improved safeguard verifications
|
Carchon, Roland
|
|
2011
|
241 |
1 |
p. 349-356
8 p.
|
artikel
|
| 30 |
Modelling heat transfer and dissolved species concentrations within PWR crud
|
Haq, Inam ul
|
|
2011
|
241 |
1 |
p. 155-162
8 p.
|
artikel
|
| 31 |
Monitoring of inside surface crack growth by strain measurement of the outside surface: A feasibility study
|
Kamaya, Masayuki
|
|
2011
|
241 |
1 |
p. 1-11
11 p.
|
artikel
|
| 32 |
New fuel rod design based on LEU/Th fuel and an assessment on in-core fuel cycle length of the MHR core
|
Shayer, Z.
|
|
2011
|
241 |
1 |
p. 185-192
8 p.
|
artikel
|
| 33 |
Nonlinear stability analysis of a reduced order model of nuclear reactors: A parametric study relevant to the advanced heavy water reactor
|
Wahi, Pankaj
|
|
2011
|
241 |
1 |
p. 134-143
10 p.
|
artikel
|
| 34 |
Numerical model for estimation of corrosion location in nuclear power plant steam generators
|
Tashakor, S.
|
|
2011
|
241 |
1 |
p. 95-100
6 p.
|
artikel
|
| 35 |
Oxidation behavior of IG and NBG nuclear graphites
|
Choi, Woong-Ki
|
|
2011
|
241 |
1 |
p. 82-87
6 p.
|
artikel
|
| 36 |
Perspectives on the application of order-statistics in best-estimate plus uncertainty nuclear safety analysis
|
Martin, Robert P.
|
|
2011
|
241 |
1 |
p. 274-284
11 p.
|
artikel
|
| 37 |
Predicting welding residual stresses in a dissimilar metal girth welded pipe using 3D finite element model with a simplified heat source
|
Deng, Dean
|
|
2011
|
241 |
1 |
p. 46-54
9 p.
|
artikel
|
| 38 |
Prediction, analysis and solution of the flow inversion phenomenon in a typical MTR-reactor with upward core cooling
|
El-Morshedy, Salah El-Din
|
|
2011
|
241 |
1 |
p. 226-235
10 p.
|
artikel
|
| 39 |
Pu recycling in a full Th-MOX PWR core. Part I: Steady state analysis
|
Fridman, E.
|
|
2011
|
241 |
1 |
p. 193-202
10 p.
|
artikel
|
| 40 |
Quantifying differences between computational results and measurements in the case of a large-scale well-confined fire scenario
|
Audouin, L.
|
|
2011
|
241 |
1 |
p. 18-31
14 p.
|
artikel
|
| 41 |
Signal reconstruction by a GA-optimized ensemble of PCA models
|
Baraldi, P.
|
|
2011
|
241 |
1 |
p. 301-309
9 p.
|
artikel
|
| 42 |
Specifications and qualification of uranium/aluminum alloy plate target for the production of fission molybdenum-99
|
Mushtaq, A.
|
|
2011
|
241 |
1 |
p. 163-167
5 p.
|
artikel
|
| 43 |
Steady-state thermal-hydraulic analysis of the Moroccan TRIGA MARK II reactor by using PARET/ANL and COOLOD-N2 codes
|
Boulaich, Y.
|
|
2011
|
241 |
1 |
p. 270-273
4 p.
|
artikel
|
| 44 |
Structured treatment of model uncertainty in complex thermal-hydraulics codes: Technical challenges, prospective and characterization
|
Pourgol-Mohamad, Mohammad
|
|
2011
|
241 |
1 |
p. 285-295
11 p.
|
artikel
|
| 45 |
Study on the LLFPs transmutation in a super-critical water-cooled fast reactor
|
Lu, Haoliang
|
|
2011
|
241 |
1 |
p. 395-401
7 p.
|
artikel
|
| 46 |
The boronizing effect on the radiation shielding and magnetization properties of AISI 316L austenitic stainless steel
|
Akkurt, Iskender
|
|
2011
|
241 |
1 |
p. 55-58
4 p.
|
artikel
|
| 47 |
The effect of low-concentration inorganic materials on the behaviour of supercritical water
|
Imre, A.R.
|
|
2011
|
241 |
1 |
p. 296-300
5 p.
|
artikel
|
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