Digitale Bibliotheek
Sluiten Bladeren door artikelen uit een tijdschrift
     Tijdschrift beschrijving
       Alle jaargangen van het bijbehorende tijdschrift
         Alle afleveringen van het bijbehorende jaargang
                                       Alle artikelen van de bijbehorende aflevering
 
                             35 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A comprehensive Thermo-hydraulic neutronic and safety analysis of a 100MWth pebble bed reactor core Boyes, W.A

398 C p.
artikel
2 Aerosol retention within submerged Containment-Type iPWRs: Experiments and modeling Lebel, Luke

398 C p.
artikel
3 Assessing high fidelity multi-component models to facilitate safeguards at Gas Centrifuge Enrichment Plants Paudel, Wisher

398 C p.
artikel
4 Assessment of the market opportunities for hydrogen derived from high temperature reactor driven processes Simpson, Allan

398 C p.
artikel
5 Automatic recognition system for document digitization in nuclear power plants Ou, Elisa

398 C p.
artikel
6 Comparative evaluation of the performance of improved genetic algorithms and differential evolution for in-core fuel management of a research reactor Tran, Hoai-Nam

398 C p.
artikel
7 Comparative study on the numerical reproduction of falling film hydrodynamics based on different surface tension models Zhao, Chuang-Yao

398 C p.
artikel
8 Comparison of lifetime assessments between ASME and RCC-MRx in liquid metal nuclear research reactors surfing from thermal striping Dougdag, Mourad

398 C p.
artikel
9 Development and assessment of a reactor system prognosis model with physics-guided machine learning Gurgen, Anil

398 C p.
artikel
10 Development of a Multi-Compartment Containment thermal hydraulic code: PARIRODHAN Mittal, Dharmanshu

398 C p.
artikel
11 Development process of FPGA based technology for control rod drive systems of experimental power reactor Santoso, Sigit

398 C p.
artikel
12 Editorial Board
398 C p.
artikel
13 Effect of contact plasticity on the seismic response of a 7-duct bundle immersed in fluid Peng, Q.

398 C p.
artikel
14 Estimation of pipe failure frequencies in the absence of operational experience data: A pilot study Heckmann, Klaus

398 C p.
artikel
15 Experimental study of voiding effects with thorium based MOX fuel cluster in Critical Facility Mallick, Amod Kishore

398 C p.
artikel
16 Extension of the CIRCE methodology to improve the Inverse Uncertainty Quantification of several combined thermal-hydraulic models Cocci, Riccardo

398 C p.
artikel
17 Feasibility study of using the NUR research reactor for a BNCT installation and Monte Carlo optimization of a BSA Boumghar, R.

398 C p.
artikel
18 Heat transfer correlation for film boiling during quenching of micro-structured surfaces Ebrahim, Shikha A.

398 C p.
artikel
19 How could fuel corrosion influence the delayed neutron signal time evolution in sodium cooled fast reactors? Ding, C.

398 C p.
artikel
20 Improvement of two-phase closure models in CTF using Bayesian inference Kumar, Vineet

398 C p.
artikel
21 Influence of thermal effects on the cavitation of orifices in nuclear power plants Xu, Bo

398 C p.
artikel
22 Integrated analysis to investigate the viability of using Thorium-based fuel instead of traditional fuel in CANDU reactor Abdelghafar Galahom, A.

398 C p.
artikel
23 Investigating sedimentation process in the plutonium reconversion using Eulerian Two-Fluid simulations and experimental verification Panda, Saroj K.

398 C p.
artikel
24 Mapping of the potential involvement of national companies to fulfilment of local content requirements in HTGR construction projects in Indonesia Deswandri,

398 C p.
artikel
25 Mechanical property and microstructure characterization of incoloy 800H alloy and its welds after corrosion testing in high temperature steam Xiao, L.

398 C p.
artikel
26 Neutron activation analysis of novel space shielding for terrestrial applications Long, Michael

398 C p.
artikel
27 Preliminary assessment of sustainability of HTR fuel programme for newcomer countries Johari, J.M.C.

398 C p.
artikel
28 Present status of JAEA’s R&D toward HTGR deployment Shibata, Taiju

398 C p.
artikel
29 RELAP5 validation for core makeup tank analysis based on separate effect tests Zhu, Mingzhang

398 C p.
artikel
30 Solid-to-fluid radiative heat transfer modeling for System Analysis Module Johnson, Ishak

398 C p.
artikel
31 Texture analysis of AGR program matrix materials Gerczak, Tyler J.

398 C p.
artikel
32 The progress on the 3D whole-core neutronics calculation of PANGU code Wen, Yutong

398 C p.
artikel
33 Uncertainty analysis of k eff due to the random packing of pebbles in the pebble bed HTR Hao, Chen

398 C p.
artikel
34 UO2-liquid metal suspension fuel concept for enhanced passive safety of LWRs: A heat pipe case study Greenquist, Ian

398 C p.
artikel
35 Validation of the novel core solver nTRACER/COBRA-TF for full core high fidelity cycle analysis of VVERs Papadionysiou, Marianna

398 C p.
artikel
                             35 gevonden resultaten
 
 Koninklijke Bibliotheek - Nationale Bibliotheek van Nederland