Results 51 to 60 of about 2,771 (221)

Simulation of Spray Injection in the Pressurizer Using RELAP5 [PDF]

, 2017
A modeling research using Relap5 to assess the pressurizer of a pressurized water reactor(PWR) power plant has been performed. The heater and water injection systems in the pressurizer system of the PWRare of greatimportance for system pressure control ...
Dibyo, S. (S), Susyadi, S. (S)
core   +1 more source

Steam Condensation Heat Transfer in the Presence of Noncondensable Gases (NCGs) in Nuclear Power Plants (NPPs): A Comprehensive Review of Fundamentals, Current Status, and Prospects for Future Research

International Journal of Energy Research, Volume 2024, Issue 1, 2024.
Efficient steam condensation is crucial for safe nuclear power plant (NPP) operations, preventing pressure buildup, overheating, and the release of radioactive materials. However, the presence of noncondensable gases (NCGs), such as air, nitrogen, hydrogen, or helium, can hinder the condensation process by creating a thermal resistance layer that ...
Samah A. Albdour, Yacine Addad, Nourah Alyammahi, Imran Afgan, Amin Shokrollahi   +4 more
wiley   +1 more source

Educational Activities to Help Transferring Knowledge in Nuclear: The Seminars of Spanish Young Generation in Nuclear (Jóvenes Nucleares) [PDF]

, 2011
From its creation, Spanish Young Generation in Nuclear (Jóvenes Nucleares, JJNN), a non-profit organization that depends on the Spanish Nuclear Society (SNE), has as an important scope to help transferring the knowledge between those generations in the ...
Alvarez, A., Jiménez Varas, Gonzalo, Ortega, S., Rubio, Rafael, Sánchez, M.   +4 more
core   +1 more source

Dynamic Response of AP1000 Nuclear Island Due to Safe Shutdown Earthquake Loading

MATEC Web of Conferences, 2017
AP1000 is a standard nuclear power plant developed by Westinghouse and its partners by using an advanced passive safety feature. Among the five principle building structures, namely the nuclear island, turbine building, annex building, diesel generator ...
Gan Buntara S., Nguyen Dinh Kien, Han Ay Lie   +2 more
doaj   +1 more source

Measurement of drop size distribution time rate for liquid-liquid dispersion using IPI method [PDF]

EPJ Web of Conferences, 2019
The liquid-liquid dispersion properties are studied mainly by image analysis (IA) and Interferometric Particle Imaging (IPI). Drop sizes will be investigated in dilute dispersion since in this case the break up phenomena is the dominating and is not ...
Jasikova Darina, Kotek Michal, Kysela Bohus, Sulc Radek, Kopecky Vaclav   +4 more
doaj   +1 more source

Neutronic Analysis of Accident‐Tolerant Cladding Materials in 3D Full Core BEAVRS PWR Benchmark Using OpenMC Code

International Journal of Energy Research, Volume 2024, Issue 1, 2024.
After the Fukushima Daiichi nuclear accident in 2011, the performance of nuclear fuel during accidents became a matter of great concern. To address this, a new type of fuel technology called accident‐tolerant fuel (ATF) has been developed with the goal of enhancing the ability of light water reactors (LWRs) to withstand severe accident conditions. Iron‐
Khalid A. Alamri, Meshari M. Alqahtani, Abdullah S. Alomari, Abdullah I. Almarshad, Andrey Kuzmin   +4 more
wiley   +1 more source

Enhancing Resilience through Nuclear Emergency Preparedness at El Dabaa Site

Science and Technology of Nuclear Installations, Volume 2024, Issue 1, 2024.
The research utilized advanced PCTRAN and RASCAL software to evaluate the potential radiological impacts of hypothetical accidents, specifically loss‐of‐coolant accident (LOCA) and long‐term station blackout (LTSBO), at the El Dabaa Nuclear Power Plant. Over a span of ten years, comprehensive meteorological data were meticulously analyzed to assess the
Waad Saleh, Juyoul Kim, Doddy Kastanya
wiley   +1 more source

Coupling of Modular High-Temperature Gas-Cooled Reactor with Supercritical Rankine Cycle

Science and Technology of Nuclear Installations, 2008
This paper presents investigations on the possible combination of modular high-temperature gas-cooled reactor (MHTGR) technology with the supercritical (SC) steam turbine technology and the prospective deployments of the MHTGR SC power plant.
Shutang Zhu, Ying Tang, Kun Xiao, Zuoyi Zhang   +3 more
doaj   +1 more source

Calculation and analysis of fast neutron fluence of pressure vessel in AP1000 reactor [PDF]

EPJ Web of Conferences
The structural integrity of the reactor pressure vessel plays an important role in the safe operation of AP1000 nuclear power plant. Radiation damage of fast neutrons is the main factor leading to pressure vessel material deterioration.
Wang Yue, Quan Guopiug, Yee Yeoh Eing, Zhu Cheng-lin, Yu Hui   +4 more
doaj   +1 more source

Evaluation of Passive Safety Injection System Performance Under Large Break LOCA for Qinshan PWR

Frontiers in Energy Research, 2021
In this work, a brand new passive safety injection system has been designed for the ocean-based Qinshan Phase I nuclear power plant to update and replace the traditional active ones. The passive safety injection system is made up of high pressure, medium
Xuesong Wang, Lin Sun, Meiru Liu, Genglei Xia   +3 more
doaj   +1 more source