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                             38 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A multi-stage hybrid fault diagnosis approach for operating conditions of nuclear power plant Wang, Zhichao

153 C p.
artikel
2 Analysis of coupled flow and heat transfer in primary and secondary sides of helical coil Once-through steam generator Liu, Fayu

153 C p.
artikel
3 A non-intercepting monitoring method for beam position on the target in an accelerator driven system Yin, Kai

153 C p.
artikel
4 A numerical analysis for a damage propagation in a plate-type fuel assembly of a research reactor Park, Jong-Pil

153 C p.
artikel
5 Application of Kriging and Variational Bayesian Monte Carlo method for improved prediction of doped UO2 fission gas release Che, Yifeng

153 C p.
artikel
6 Application of three-dimensional detailed geometry to simulation of melt progression in an intricate BWR lower head Okawa, Tsuyoshi

153 C p.
artikel
7 A study on the radial expansion reactivity of a metal-fueled sodium-cooled fast reactor via a physics experiment Yun, Sunghwan

153 C p.
artikel
8 Calculation approach to building DCGLs of waste treatment facilility for Kori unit 1 decommissioning and comparative analysis of the results Seo, Hyung-Woo

153 C p.
artikel
9 CFD simulation on the transient process of coolant mixing phenomenon in reactor pressure vessel Li, Jun

153 C p.
artikel
10 COCOSYS analysis on aerosol wash-down of THAI-AW3 experiment and generic containment Wang, Fangnian

153 C p.
artikel
11 Component unavailability model for PSA Level I applications considering aging and startup degradation: An Application to an Emergency Diesel Generator System Lima do Nascimento, J.M.

153 C p.
artikel
12 Convergence analysis of the non-linear CMFD schemes for acceleration of multi-group fixed source neutron transport calculations Jain, Lakshay

153 C p.
artikel
13 Corrigendum to “Seismic response correlation coefficient for the structures, systems and components of the Korean nuclear power plant for seismic probabilistic safety assessment” [Annals Nucl. Energy 150 (2021) 107759] Eem, Seunghyun

153 C p.
artikel
14 Coupled system thermal Hydraulics/CFD models: General guidelines and applications to heavy liquid metals Pucciarelli, A.

153 C p.
artikel
15 Development and verification of thermal neutron scattering law data calculation module in nuclear data processing code NECP-Atlas Tang, Yongqiang

153 C p.
artikel
16 Development of a coupling between a system thermal–hydraulic code and a reduced order CFD model Star, S. Kelbij

153 C p.
artikel
17 Development of a diagnostic algorithm for abnormal situations using long short-term memory and variational autoencoder Kim, Hyojin

153 C p.
artikel
18 Development of a RELAP5 model for the thermo-hydraulic characteristics simulation of the helically coiled tubes Xu, Ziyi

153 C p.
artikel
19 Dynamic modeling and two-degree-of-freedom controller design for pressurized water reactor core Wan, Jiashuang

153 C p.
artikel
20 Editorial Board
153 C p.
artikel
21 Effects of U3Si2 fuel and minor actinide doping on fundamental neutronics, nuclear safety, and security of small and medium PWRs in comparison to conventional UO2 fuel Mitsuboshi, Natsumi

153 C p.
artikel
22 Experimental study on flow structures of central blockage accidents in a rectangular channel using PIV and POD Yuan, Dongdong

153 C p.
artikel
23 Fractional two energy groups matrix representation for nuclear reactor dynamics with an external source Aboanber, Ahmed E.

153 C p.
artikel
24 High-efficiency simulation of VENUS-3 neutron-shielding problem with an automatic and enhanced hybrid Monte-Carlo-Deterministic method Zheng, Qi

153 C p.
artikel
25 Impact of the vacuum core on the upper limit of the separative power of gas centrifuges Tronin, I.V.

153 C p.
artikel
26 Improved subgroup method coupled with particle swarm optimization algorithm for intra-pellet non-uniform temperature distribution problem Li, Song

153 C p.
artikel
27 Investigation of Anderson acceleration in neutronics-thermal hydraulics coupled direct whole core calculation Facchini, Alberto

153 C p.
artikel
28 Investigations on neutron attenuation properties of poly-boron materials using Am-Be and 252Cf sources neutron spectra Balasundar, S.

153 C p.
artikel
29 Metamorphic testing of the NUIT code based on burnup time Li, Meng

153 C p.
artikel
30 Numerical and semi-analytical solution of a transient during the start-up of a slab reactor with circulating fuel at zero power Ozgener, Huseyin Atila

153 C p.
artikel
31 Numerical simulation of bubble transport during steam generator tube rupture accident of Lead-cooled Fast Reactor Yu, Qifan

153 C p.
artikel
32 Numerical stability analysis of lp-CMFD acceleration for the discrete ordinates neutron transport calculation discretized with discontinuous Galerkin Finite Element Method Chan, Yimeng

153 C p.
artikel
33 Optimization of reactor size in the small sodium-cooled CANDLE burning reactor Nguyen, Hoang Hai

153 C p.
artikel
34 Research on the fabrication method of macroscopic cross section base on the Monte Carlo simulation Ge, Yulin

153 C p.
artikel
35 Sensitivities of delayed neutron fractions in the framework of SCALE 6.2 Zwermann, Winfried

153 C p.
artikel
36 Study on an improved burnup algorithm in Kylin-2 code Hu, Yuying

153 C p.
artikel
37 Study on the thermal hydraulic characteristics of a simulated pressurizer during the blowdown process Ke, Bingzheng

153 C p.
artikel
38 Three-dimensional transient analysis for control rods drop into CSR1000 core Lianjie, Wang

153 C p.
artikel
                             38 gevonden resultaten
 
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