Results 21 to 30 of about 5,445,549 (348)

SOURCE TERM ASSESSMENT FOR 100 MWE PRESSURIZED WATER REACTOR [PDF]

open access: yes, 2020
One of the barriers on the implementation of nuclear energy in Indonesia is public perception towards the safety of nuclear power plants (NPPs). Therefore, it is necessary to perform a study about the radiation impact of normal and abnormal operations of
Udiyani, Pande Made   +1 more
core   +5 more sources

Uncertainty assessment for the displacement damage of a pressurized water reactor vessel

open access: yes, 2021
The neutron irradiation-induced mechanical property change is a major challenge for nuclear materials. For a Pressurized Water Reactor (PWR), neutron irradiation embrittlement of the reactor pressure vessel is one of the most important issues that ...
Shengli Chen   +4 more
semanticscholar   +1 more source

Climate change and the performance of pressurized irrigation water distribution networks under mediterranean conditions: Impacts and adaptations [PDF]

open access: yes, 2010
Numerous previous studies have modelled the impact of climate change on crop water requirements and hence future water resource needs for irrigated agriculture.
Nicola Lamaddalena   +5 more
core   +1 more source

Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation

open access: yesNuclear Engineering and Technology, 2018
Improved load-following capability is one of the most important technical tasks of a pressurized water reactor. Controlling the nuclear reactor core during load-following operation leads to some difficulties.
M. Zaidabadi nejad, G.R. Ansarifar
doaj   +1 more source

Control of the pressurized water nuclear reactors power using optimized proportional–integral–derivative controller with particle swarm optimization algorithm

open access: yesNuclear Engineering and Technology, 2018
Various controllers such as proportional–integral–derivative (PID) controllers have been designed and optimized for load-following issues in nuclear reactors. To achieve high performance, gain tuning is of great importance in PID controllers.
Seyed Mohammad Hossein Mousakazemi   +2 more
doaj   +1 more source

A high-resolution characterization of the initiation of stress corrosion crack in Alloy 690 in simulated pressurized water reactor primary water

open access: yes, 2020
Stress corrosion crack initiation of alloy 690 in simulated pressurized water reactor primary water was studied through high-resolution characterization of grain boundaries at different stages of the initiation process.
W. Kuang, G. Was
semanticscholar   +1 more source

Anaerobic Treatment of Concentrated Black Water in UASB Reactor at a Short HRT [PDF]

open access: yes, 2010
This research describes the feasibility of applying a UASB reactor for the treatment of concentrated black (toilet) water at 25 °C. On average 78% of the influent load of COD at an HRT of 8.7 days was removed. Produced methane can be converted to 56 MJ/p/
Temmink, B.G.   +3 more
core   +1 more source

Kinetic study of defluoridation of drinking water by electrocoagulation/electroflotation in a stirred tank reactor and in an external-loop airlift reactor [PDF]

open access: yes, 2010
A kinetic study of defluoridation of drinking water was carried out using the electrocoagulation/electroflotation process in two batch reactors of identical volume (20 L): a stirred tank reactor (STR) and an external-loop airlift reactor (ELALR).
A.H. Essadki   +13 more
core   +1 more source

Development of a computer code for thermal–hydraulic design and analysis of helically coiled tube once-through steam generator

open access: yesNuclear Engineering and Technology, 2017
The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a key piece of equipment for compact small reactors. The present study developed and verified a thermal–hydraulic design and performance analysis computer code for a countercurrent H-OTSG
Yaoli Zhang   +3 more
doaj   +1 more source

Study of Pressurized Water Reactor Design Models [PDF]

open access: yes, 2013
This study of pressurized water reactor design models involves the application of linear regression analysis on two typical Water-Cooled Nuclear Reactor design models, viz Pressurized Water Reactor Design I (PWRD I) and Pressurized Water Reactor Design ...
Oludare, A.I., Akusu, P.O., Agu, M.N.
core   +1 more source

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