Results 51 to 60 of about 1,365 (205)

Numerical Simulation of an Out-Vessel Loss of Coolant from the Breeder Primary Loop Due to Large Rupture of Tubes in a Primary Heat Exchanger in the DEMO WCLL Concept

Energies, 2021
This work presents a thermohydraulic analysis of a postulated accident involving the rupture of the breeder primary cooling loop inside a heat exchanger (once through steam generator).
Francesco Galleni, Marigrazia Moscardini, Andrea Pucciarelli, Maria Teresa Porfiri, Nicola Forgione   +4 more
doaj   +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

MELCOR Accident Consequence Code System (MACCS) [PDF]

, 1990
Data listing for three sample problems are provided to illustrate the use of MACCS (MELCOR [We84] Accident Consequence Code System developed by Sandia National Laboratories) referred to in the accompanying report as Problems A, B, and ...
Sandia National Laboratories
core  

A Comparison of Modifications to MELCOR versions 1.8.2 and 1.8.6 for ITER Safety Analysis [PDF]

, 2010
During the Engineering Design Activity of the International Thermonuclear Experimental Reactor (ITER), the MELCOR 1.8.2 code was selected as one of several codes to be used to perform ITER safety analyses [1].
null B. J. Merrill, null P. W. Humrickhouse, Merrill, B. J., Humrickhouse, P. W.   +3 more
core   +1 more source

Analysis of hydrogen control in a Small Modular Reactor during TLOFW severe accident

Brazilian Journal of Radiation Sciences
During the Fukushima Daiichi nuclear accident in 2011, hydrogen explosions occurred in all units from Unit 1 to Unit 3. Consequently, one of the lessons learned from the Fukushima Daiichi accident is the necessity of implementing hydrogen control and ...
Maritza Rodríguez Gual, Marcos Coelho Maturana, Nathalia Nunes Araújo, Marcelo Ramos Martins   +3 more
doaj   +1 more source

Time‐Series Forecasting of a Typical PWR Undergoing Large Break LOCA

Science and Technology of Nuclear Installations, Volume 2024, Issue 1, 2024.
In this work, a machine learning (ML) metamodel is developed for the time‐series forecasting of a typical nuclear power plant response undergoing a loss of coolant accident (LOCA). The plant model of choice is based on the APR1400 nuclear reactor. The key systems and components of APR1400 relevant to the investigated scenario are modelled using the ...
Michal Kaminski, Aya Diab, Doddy Kastanya   +2 more
wiley   +1 more source

Status of MELCOR Sodium Models Development

, 2017
A sodium coolant accident analysis code is necessary to provide regulators with a means of performing confirmatory analyses for future sodium reactor licensing submissions. MELCOR and CONTAIN, which have been employed by the U.S.
Larry L. Humphries, David L. Y. Louie
core   +1 more source

Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems

Science and Technology of Nuclear Installations, 2017
The integrity of the containment will be challenged during a severe accident due to pressurization caused by the accumulation of steam and other gases and possible ignition of hydrogen and carbon monoxide.
Siniša Šadek, Davor Grgić, Zdenko Šimić   +2 more
doaj   +1 more source

Accident Process and Core Thermal Response During a Station Blackout Initiated Study for Small Modular Reactor

Frontiers in Energy Research, 2018
Interest in evaluation of reactor response and off-site consequences following beyond design basis accidents has significantly increased after Fukushima.
Shasha Yin, Yajing Tian, Suizheng Qiu, Ye Tian, Huawei Fang, Wei Huang, Zhihui Chen   +6 more
doaj   +1 more source

Analyses on the recriticality and sub-critical boron concentrations during late phase of a severe accident of pressurized water reactors

Nuclear Engineering and Technology, 2023
The potential for recriticality and sub-critical boron concentrations is analyzed during the relocation of the fuel rods in the assembly, which we call late phase of a severe accident, via coupling between MELCOR and whole-core Monte Carlo analyses by ...
Yoonhee Lee, Yong Jin Cho, Kukhee Lim
doaj   +1 more source