Results 1 to 10 of about 358,647 (309)
A SIMPLIFIED TWO-NODE COARSE-MESH FINITE DIFFERENCE METHOD FOR PIN-WISE CALCULATION WITH SP3 [PDF]
For accurate and efficient pin-by-pin core calculation of SP3 equations, a simplified two-node Coarse Mesh Finite Difference (CMFD) method with the nonlinear iterative strategy is proposed.
Zhao Wenbo +8 more
doaj +1 more source
The Evolution of the Fed Batch Ethoxylation Reactors to Produce the Non-Ionic Surfactants
The most recent reactor technology to produce non-ionic surfactants via ethoxylation reaction is illustrated in the present work. The most advanced reactors are deeply illustrated for what concerns the working principle and the main performance.
Martino Di Serio +3 more
doaj +1 more source
Atomic Routes and Cultures for a New Narrative on Franco’s Regime
A decision by two Spanish companies to start producing nuclear-based electrical energy was the beginning of a journey that led two Spanish engineers to the United States and Canada in 1957.
Ana Romero de Pablos
doaj +1 more source
Steady-state and transient analysis of reactor core under Reactivity-Initiated Accident (RIA) conditions are important for reactor operation safety. The reactor dynamics are influenced by neutronic and thermal-hydraulic aspects of the core. In this study,
Surian Pinem +4 more
doaj +1 more source
In pressurized water reactors (PWRs), flow-induced vibration (FIV) induces the fretting wear of fuel rods and supporting grids, and the process is accompanied by corrosion, which is called fretting corrosion. In this paper, fretting corrosion experiments
Xin Liu +5 more
doaj +1 more source
In view of the multimetal barrier environment of nuclear power plant, by considering the factors such as transmission power, transmission position, and multipath interference, based on the simulation of metal pipes and equipment, this paper carries out ...
Zhi-Guang Deng +6 more
doaj +1 more source
Innovative Design of Compact Heavy-Load Independent Transfer Device for Nuclear Engineering System
The transportation of heavy equipment in nuclear engineering has always been the focus of engineers, especially those transfer devices with the characteristics of small geometric size and heavy load.
Hao Wan +5 more
doaj +1 more source
This study conducted an evaluation of the corrosion behavior of an aluminum alloy utilized in the Isfahan Miniature Neutron Source Reactor (MNSR). The component analyzed, dry channel (DC), had been exposed to radiation for 12 years in a water environment
Mojtaba Bagherzadeh +5 more
doaj +1 more source
Study on kinetic parameters characteristics of pebble bed reactor using HTR-proteus facility [PDF]
The inherent safety feature of a pebble-bed reactor can be observed from its kinetic parameters. Proper modeling for calculating the reactor kinetic is also a concern for safe operation during normal and transient conditions.
Zuhair +4 more
doaj +1 more source
Deterministic Safety Technology for RBMK Reactors [PDF]
The present paper deals with the description of the technical activities conducted within the TACIS Project R2.03/97, 2 EC Contract no. 30303, related to RBMK. The project activities are focused toward the setting-up of a chain of computational tools suitable for the analysis of transients expected in the RBMK nuclear power plant (NPP).
D'AURIA, FRANCESCO SAVERIO +3 more
openaire +5 more sources

