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                             53 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A method of estimating aerosol particle removal rates using one-dimensional two-fluid equations for venturi scrubbers in filtered containment venting Kim, Ji-Su

145 C p.
artikel
2 A method to identify an accidental control rod drop with inverse distance weighted interpolation Souza, Thiago Juncal

145 C p.
artikel
3 An adaptive regularized iterative FBP algorithm with high sharpness for irradiated fuel assembly reconstruction from few projections in FNCT Li, Sangang

145 C p.
artikel
4 Analysis of the flow noises of the nuclear main pump caused by the high temperature liquid Sodium in the two-circuit main loop liquid Sodium pump system Xie, Zhongliang

145 C p.
artikel
5 An empirical study of the personality effects on diagnosis performance of human operators in unexpected plant conditions of NPPs Kim, Tae Jin

145 C p.
artikel
6 An enhanced model for the prediction of slug flow boiling heat transfer on a downward-facing heated wall Amidu, Muritala A.

145 C p.
artikel
7 An estimation of cross-section covariance data suitable for predicting neutronics parameters uncertainty Takeda, Toshikazu

145 C p.
artikel
8 A new Cross-section calculation method in HTGR engineering simulator system based on Machine learning methods Li, Zeguang

145 C p.
artikel
9 A new integrated SSCs safety classification method and a case study on CN HCCB TES Sun, Ming

145 C p.
artikel
10 A new relocation recovery model for LWR fuel Wang, Kai-Yuan

145 C p.
artikel
11 A new three-level CMFD method based on the loosely coupled parallel strategy Liu, Zhouyu

145 C p.
artikel
12 A novel approach in exergy optimization of a WWER1000 nuclear power plant using whale optimization algorithm Ebrahimgol, H.

145 C p.
artikel
13 A research and development review of water-cooled breeding blanket for fusion reactors Ling, Qixin

145 C p.
artikel
14 A simulation of I2S-LWR selected transients Ward, Andrew M.

145 C p.
artikel
15 Assessing I2S-LWR economic competitiveness using systematic differential capital cost evaluation methodology Maronati, G.

145 C p.
artikel
16 Attenuation of neutron and photon-induced irradiation damage in pressurized water reactor pressure vessels Chen, Shengli

145 C p.
artikel
17 CFD analysis of a dry storage cask with advanced spent nuclear fuel cask additives Bae, J.

145 C p.
artikel
18 Contribution of fission products to displacement damage in fast reactor fuel cladding Chen, Shengli

145 C p.
artikel
19 Coupled fuel performance calculations in VERA and demonstration on Watts Bar unit 1, cycle 1 Stimpson, S.

145 C p.
artikel
20 Design, development and testing of a sodium submersible Annular Linear Induction Pump for application in sodium cooled fast reactor Nashine, B.K.

145 C p.
artikel
21 Development and validation of the eutectic reaction model in JUPITER code Chai, Penghui

145 C p.
artikel
22 Editorial Board
145 C p.
artikel
23 Effect of single and combined ocean motions on a small OFNP under SBO accidents Yan, Qiqi

145 C p.
artikel
24 Effects of restitution coefficient on pebble motion in a thin pebble bed – Lagrangian analysis Qi, Houbo

145 C p.
artikel
25 Establishing a neutronics design and equilibrium cycle analysis for the I2S-LWR reactor with UO2 and U3Si2 Fuel Ward, Andrew M.

145 C p.
artikel
26 Evaluation of the maximum bending stress of pre-hydrided Zircaloy-4 cladding tube after simulated loss-of-coolant-accident test Okada, Yuji

145 C p.
artikel
27 Experimental investigation of temperature and heat distribution across 220 MWe Indian PHWR channel under boil-off condition Yadav, Subodh Kumar

145 C p.
artikel
28 Experimental study on leak flow rate characteristics of high pressure subcooled water through axial and circumferential microcracks of steam generator tubes under high back pressure conditions Zhang, K.

145 C p.
artikel
29 Extension of FRAPCON-xt to hydride radial reorientation in dry storage Feria, F.

145 C p.
artikel
30 Few-group diffusion theory parameters from lattice calculations using leakage corrected collision probabilities Ray, Sherly

145 C p.
artikel
31 Influence of cross-section uncertainties on the calculated results from a thermo-hydraulics code Miglierini, Bruno

145 C p.
artikel
32 I2S-LWR microchannel heat exchanger design and experimental validation Kromer, Daniel A.

145 C p.
artikel
33 Model for radiation damage-induced grain subdivision and its influence in U3Si2 fuel swelling Marquez, Matias G.

145 C p.
artikel
34 Multidimensional multiphysics modeling of TRISO particle fuel with SiC/ZrC coating using modified fission gas release model Zhang, Cheng

145 C p.
artikel
35 Multi-objective, multi-physics optimization of 3D mixed-oxide LWR fuel assembly designs using the MOJADE algorithm Charles, Alan

145 C p.
artikel
36 On the relevance of the scattering anisotropy for a low order transport method Giusti, V.

145 C p.
artikel
37 Passive decay heat removal system design for the integral inherent safety light water reactor (I2S-LWR) Wang, Mingjun

145 C p.
artikel
38 Performance shaping factor taxonomy for human reliability analysis on mitigating nuclear power plant accidents caused by extreme external hazards Kang, Seongkeun

145 C p.
artikel
39 Preliminary design of the I2S-LWR containment system Wang, Mingjun

145 C p.
artikel
40 Quantitative software reliability assessment methodology based on Bayesian belief networks and statistical testing for safety-critical software Cai, Yuanfeng

145 C p.
artikel
41 Radiation environment in the I2S-LWR concept: Part I – Radial distribution and its impact on vessel fluence, neutron detectors placement, and radial reflector gamma heating Flaspoehler, Timothy

145 C p.
artikel
42 Resonance parameter adjustment in the resolved region based upon an Asymptotic Generalized Linear Least-Squares methodology in conjunction with the Monte Carlo method Pelloni, Sandro

145 C p.
artikel
43 Revisiting the bias factor methodologies for the validation of fast test reactors Palmiotti, Giuseppe

145 C p.
artikel
44 Serpent-2 and OSCAR-4 computational tools compared against McMaster nuclear reactor improved operational data history for U-235 fuel inventory tracking, local power tracking and validation of multiplication factor Alqahtani, M.

145 C p.
artikel
45 Simulation of the BEAVRS benchmark using VERA Collins, Benjamin

145 C p.
artikel
46 Simulation research on passive safety injection system of marine nuclear power plant based on compressed gas Zhida, Yang

145 C p.
artikel
47 Sintering of Metakaolin-based Na-Pollucite ceramics and their immobilization of Cs Chen, Song

145 C p.
artikel
48 SOARCA uncertainty analysis of a short-term station blackout accident at the Sequoyah nuclear power plant Bixler, N.E.

145 C p.
artikel
49 Study on reactivity control strategies for the thermoelectric integrated space nuclear reactor Li, Jian

145 C p.
artikel
50 Study on switching control of PWR core power with a fuzzy multimodel Jiang, Qingfeng

145 C p.
artikel
51 The development of TM2-RIA code for TRIGA type research reactors Allaf, Mohammad Amer

145 C p.
artikel
52 Time and frequency domain analyses of fluid force fluctuations in a normal triangular tube array in forced vibrations Chen, Yonggui

145 C p.
artikel
53 Use of ADVANTG to analyse skyshine γ-dose rates around a silo type LILW repository Kotnik, Domen

145 C p.
artikel
                             53 gevonden resultaten
 
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