Results 61 to 70 of about 10,212 (309)
Computer Code System V. S. O. P. (99/11) Update 2011 of V.S.O.P(99)-Version 2009 CODE MANUAL [PDF]
V.S.O.P. is a computer code system for the comprehensive numerical simulation of the physics of thermal reactors. The application of the code implies processing of cross sections, the set-up of the reactor and of the fuel element, neutron spectrum ...
Haas, K. A., Pohl, C., Rütten, H. J.
core
Розглянуто типові конструктивні схеми гідравлічних приводів обертання. Розглянуті конструкції модулів теплового гідроприводу. Визначені основні конструктивні параметри, що впливають на вихідні характеристики та роботу приводу. Розглянуто ряд рідин, які можуть бути використані в якості робочого тіла для теплового гідроприводу.
Gubarev, A. +2 more
openaire +2 more sources
Influence of Test Temperature and Test Frequency on Fatigue Life of Aluminum Alloy EN AW‐2618A
The influence of test temperature and test frequency on the fatigue life of EN AW‐2618A is investigated. High‐cycle fatigue tests are performed at different test temperatures and frequencies on the 1000 h/230°C overaged state. Both test parameters reduce fatigue life due to time‐dependent damage mechanisms.
Ying Han +5 more
wiley +1 more source
Study on the Calculation Method of Molten Pool Decay Heat Distribution under IVR Condition
As an important strategy to mitigate severe accidents, the in-vessel retention (IVR) technique has been applied to the new generation of pressurized water reactor (PWR).
Yisheng Hao +11 more
doaj +1 more source
A Comparison in Thermal-hydraulics Analysis of Pwr1000 Using Fixed and Temperature Function of Thermal Conductivity [PDF]
A COMPARISON IN THERMAL-HYDRAULICS ANALYSIS OF PWR-1000 USING FIXEDAND TEMPERATURE FUNCTION OF THERMAL CONDUCTIVITY. A study to analyze theinfluence of the fuel-cladding's thermal conductivity on the sub-channel of pressurized waterreactor 1000 (PWR-1000)
Isnaini, M. D. (Muhammad) +1 more
core +2 more sources
This plot compares experimental tensile stress–strain curves (with 4 different strain rates) and corresponding modelled curves (obtained using the optimised sets of Voce and Miller–Norton parameter values shown). The inferred M‐N values, characterizing the creep, are very similar to those obtained via conventional creep testing.
S. Ooi, R. P. Thompson, T. W. Clyne
wiley +1 more source
Large-eddy simulations of turbulent flow for grid-to-rod fretting in nuclear reactors
The grid-to-rod fretting (GTRF) problem in pressurized water reactors is a flow-induced vibration problem that results in wear and failure of the fuel rods in nuclear assemblies.
Bakosi, J. +4 more
core +1 more source
Graphene nanoplatelet (0.1 wt.%) reinforcement significantly enhances the performance of β Ti‐28Nb‐35.4Zr alloy. Grain refinement, reduced water contact angle, and improved surface characteristics promote osteoblast adhesion and complete surface coverage after 7 days.
Khurram Munir +5 more
wiley +1 more source
Phenomenology of liquid metal thermal-hydraulics [PDF]
The cooling system of the Energy Amplifier (EA) is based on a Lead flow driven by natural circulation [1]. In the Energy Amplifier Demonstration Facility (EADF) a Lead-Bismuth eutectic is used and natural circulation, although enhanced through a gas ...
Bellucci, Valter +7 more
core
In this study, the interplay of dipolar dynamics and ionic charge transport in MOF compounds is investigated. Synthesizing the novel structure CFA‐25 with integrated freely rotating dipolar groups, local and macroscopic effects, including interactions with Cs cations are explored.
Ralph Freund +6 more
wiley +1 more source

