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A compact Monte Carlo method for the calculation of k(infinity) and its application in analysis of (n,xn) reactions

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 376 ()

To explore the Monte-Carlo definition of multiplication factor and the impact from specific reactions, a compact Monte Carlo method is established, wh......

Numerical investigation on turbulent penetration and thermal stratification for the in-surge case of the AP1000 pressurizer surge line

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 378 ()

The transient three-dimensional in-surge case of the AP1000 pressurizer surge line is investigated by conjugating multi-physics fields under the ANSYS......

Model investigations for seismic responses of a scaled polar crane at a nuclear power station

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 381 ()

In order to investigate the seismic responses of a polar crane at a nuclear power station, a 1:16 scaled model (C-L = 16) which uses the same material......

Ageing and air leakage assessment of a nuclear reactor containment mock-up: VERCORS 2nd benchmark

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 377 ()

Electricite de France (EDF) operates a large fleet of nuclear reactors and is responsible for demonstrating the safety of facilities, including concre......

Description and verification of KYLIN-V2.0 lattice physics code

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 379 ()

KYLIN-V2.0 is an advanced neutron transport lattice physics code developed by the Nuclear Power Institute of China (NPIC). This paper presents a brief......

Design and construction of Power Range Channel for the third generation Reactor Nuclear Instrumentation system

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 376 ()

The Power Range (PR) channel is the critical component of Reactor Nuclear Instrumentation (RNI) system which is used for continues monitoring of power......

An investigation of transition processes from transient gas-liquid plug to slug flow in horizontal pipe: Experiment and Cost-based recurrence analysis

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 379 ()

Transient gas-liquid two-phase flows are often encountered in nuclear industries. Investigating the dynamics of the transient gas-liquid flows is of s......

Vapor condensation with low air mass fraction inside water seal branch tube under free convection

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 379 ()

The pressure vessel has used a newly designed water seal structure, and the sealed water is from condensation at low hydrogen concentration. To get th......

Start-up characteristics for the test facility of a prototype sodium heated OTSG

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 378 ()

The test facility of the prototype sodium heated once-through steam generator (OTSG) is used to verify the accuracy and reliability of the design for ......

A numerical study of heat transfer enhancement by helically corrugated tubes in the intermediate heat exchanger of a very-high-temperature gas-cooled reactor

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 380 ()

We numerically investigate heat transfer enhancement by helically corrugated tubes (HCTs) in the intermediate heat exchanger (IHX) of a very-high-temp......

Drift-flux parameter modeling of vertical downward gas-liquid two-phase flows for interfacial drag force formulation

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 378 ()

The two-fluid model has been adopted as a platform of nuclear thermal-hydraulic system analysis code because it can treat the mechanical and thermal n......

CFD study on onset of liquid entrainment through ADS-4 branch line in AP1000

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 380 ()

The consequences of liquid entrainment through the fourth stage Automatic Depressurization System (ADS-4) of Advanced Passive nuclear power reactor (A......

Optimal and fast field reconstruction with reduced basis and limited observations: Application to reactor core online monitoring

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 377 ()

The fast reconstruction of neutronic field in a nuclear core using reduced modeling and limited observations has attracted considerable attention. In ......

Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 378 ()

Heat pipe cooled reactor (HPR) has a good adaptability to portable power system, which is popular in recent years. Due to the particularity of alkali-......

Multiphysics analysis of thorium-based fuel performance under reactor normal operating and accident conditions in a light water reactor

期刊: NUCLEAR ENGINEERING AND DESIGN, 2021; 375 ()

The ThO2 fuel has higher thermal conductivity and melting boiling point than the UO2 fuel, which is beneficial to the fast removal of heat and the imp......

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