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                             36 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Adsorption and separation behaviors of Y(III) and Sr(II) in acid solution by a porous silica based adsorbent Wu, Hao

53 10 p. 3352-3358
artikel
2 A mechanistic analysis of H2O and CO2 diluent effect on hydrogen flammability limit considering flame extinction mechanism Jeon, Joongoo

53 10 p. 3286-3297
artikel
3 An investigation on the improvement of neutron radiography system of the Tehran research reactor by using MCNPX simulations Amini, Moharram

53 10 p. 3413-3420
artikel
4 Application of STPA-SafeSec for a cyber-attack impact analysis of NPPs with a condensate water system test-bed Shin, Jinsoo

53 10 p. 3319-3326
artikel
5 A real-time sorting algorithm for in-beam PET of heavy-ion cancer therapy device Ke, Lingyun

53 10 p. 3406-3412
artikel
6 Artificial neural network for predicting nuclear power plant dynamic behaviors El-Sefy, M.

53 10 p. 3275-3285
artikel
7 Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment Luzzi, L.

53 10 p. 3367-3378
artikel
8 Beam line design and beam transport calculation for the μSR facility at RAON Pak, Kihong

53 10 p. 3344-3351
artikel
9 CFD investigation of a JAEA 7-pin fuel assembly experiment with local blockage for SFR Jeong, Jae-Ho

53 10 p. 3207-3216
artikel
10 Characterising the dynamic seals used in absorber rod drive mechanisms in Indian FBR Kaushal, Nihal

53 10 p. 3438-3448
artikel
11 Comparison of theoretical and machine learning models to estimate gamma ray source positions using plastic scintillating optical fiber detector Kim, Jinhong

53 10 p. 3431-3437
artikel
12 Copper neutron transport libraries validation by means of a 252Cf standard neutron source Schulc, Martin

53 10 p. 3151-3157
artikel
13 Corrigendum to “High performance γ-ray imager using dual anti-mask method for the investigation of high-energy nuclear materials” [NET, volume 53, issue 7, July 2021, pages 2371–2376] Lee, Taewoong

53 10 p. 3464
artikel
14 Delayed fast neutron as an indicator of burn-up for nuclear fuel elements Akyurek, T.

53 10 p. 3127-3132
artikel
15 Design and analysis of RIF scheme to improve the CFD efficiency of rod-type PWR core Chen, Guangliang

53 10 p. 3171-3181
artikel
16 Effect of multiple-failure events on accident management strategy for CANDU-6 reactors YU, Seon Oh

53 10 p. 3236-3246
artikel
17 Efficiency calibration and coincidence summing correction for a NaI(Tl) spherical detector Noureddine, Salam F.

53 10 p. 3421-3430
artikel
18 Electromagnetic interference caused by an electric-line current in a cable tray in nuclear power plants Lee, Hoon-Keun

53 10 p. 3314-3318
artikel
19 Experimental investigations and development of mathematical model to estimate drop diameter and jet length Roy, Amitava

53 10 p. 3229-3235
artikel
20 Extension of the NEAMS workbench to parallel sensitivity and uncertainty analysis of thermal hydraulic parameters using Dakota and Nek5000 Delchini, Marc-Olivier G.

53 10 p. 3449-3459
artikel
21 Flow blockage analysis for fuel assembly in a lead-based fast reactor Wang, Chenglong

53 10 p. 3217-3228
artikel
22 Fuzzy-technique-based expert elicitation on the occurrence probability of severe accident phenomena in nuclear power plants Suh, Young A

53 10 p. 3298-3313
artikel
23 GEANT4 characterization of the neutronic behavior of the active zone of the MEGAPIE spallation target Lamrabet, Abdesslam

53 10 p. 3164-3170
artikel
24 Human-machine system optimization in nuclear facility systems Corrado, Jonathan K.

53 10 p. 3460-3463
artikel
25 Implementation of a new empirical model of steam condensation for the passive containment cooling system into MARS-KS code: Application to containment transient analysis Lee, Yeon-Gun

53 10 p. 3196-3206
artikel
26 Influence of neutron irradiation and ageing on behavior of SAV-1 reactor alloy Tsay, K.V.

53 10 p. 3398-3405
artikel
27 Modelling of multidimensional effects in thermal-hydraulic system codes under asymmetric flow conditions – Simulation of ROCOM tests 1.1 and 2.1 with ATHLET 3D-Module Pescador, E. Diaz

53 10 p. 3182-3195
artikel
28 Monte Carlo simulations of chromium target under proton irradiation of 17.9, 22.3 MeV Kara, A.

53 10 p. 3158-3163
artikel
29 Numerical simulation on jet breakup in the fuel-coolant interaction using smoothed particle hydrodynamics Choi, Hae Yoon

53 10 p. 3264-3274
artikel
30 Prediction of ballooning and burst for nuclear fuel cladding with anisotropic creep modeling during Loss of Coolant Accident (LOCA) Kim, Jinsu

53 10 p. 3379-3397
artikel
31 Radiation testing of low cost, commercial off the shelf microcontroller board Fried, Tomas

53 10 p. 3335-3343
artikel
32 Smart grid and nuclear power plant security by integrating cryptographic hardware chip Kumar, Niraj

53 10 p. 3327-3334
artikel
33 Study of combinations of site operating states for multi-unit PSA Yoo, Heejong

53 10 p. 3247-3255
artikel
34 The detection and diagnosis model for small scale MSLB accident Wang, Meng

53 10 p. 3256-3263
artikel
35 Thermal conductivity prediction model for compacted bentonites considering temperature variations Yoon, Seok

53 10 p. 3359-3366
artikel
36 Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor García, Manuel

53 10 p. 3133-3150
artikel
                             36 gevonden resultaten
 
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