Results 21 to 30 of about 1,865 (177)

Development and application of multi-scale thermal fluid coupling program for molten salt cooled fast reactor based on RELAP5 and sub-channel program

He jishu, 2022
BackgroundThe natural circulation chloride cooled fast reactor (N3CFR) has the characteristics of simple structure, high inherent safety and good economy. It is an advanced fourth-generation nuclear energy system with development potential.
SONG Shiyang, CHENG Maosong, LIN Ming, DAI Zhimin   +3 more
doaj   +1 more source

Improvement and validation of the delayed neutron precursor transport model in RELAP5 code for liquid fuel molten salt reactor

He jishu, 2021
BackgroundThe liquid-fueled molten salt reactor (MSR) is one of the Generation IV advanced reactor concepts, which has unique advantages in aspects of safety, economy and nonproliferation.
LI Rui, CHENG Maosong, DAI Zhimin
doaj   +1 more source

Study on the Density Wave Instability in Natural Circulation System under Rolling Conditions

International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023
In the ocean environment, the thermal fluid system installed on the ship moves with the waves. This unsteady transient motion imposes additional body forces on the liquid. Thereby, the thermohydraulic properties of the thermal fluid system are changed, especially for natural circulation systems with a low driving force.
Houjun Gong, Xiaoxi Zhang, Nan Gui, Yanping Huang, Xingtuan Yang, Shengyao Jiang, Rafael M. Santos   +6 more
wiley   +1 more source

ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate‐Type Heat Exchanger

Science and Technology of Nuclear Installations, Volume 2023, Issue 1, 2023., 2023
This paper summarises the results of an experimental campaign carried out at SIET on the ELSMOR facility built in 2022 to validate a decay heat removal system for the E‐SMR. Based on the passive mechanisms of natural circulation, the system aims to dissipate the reactor decay heat to a water pool, using two heat exchangers: a plate‐type one coupling ...
Roberta Ferri, Andrea Achilli, Cinzia Congiu, Stefano Marcianò, Stefano Gandolfi, Mattia Marengoni, Alberto Bersani, Alessandro Passerin D’Entreves, Doddy Kastanya   +8 more
wiley   +1 more source

Thermal-hydraulic analysis of loss-of-cooling accident in spent fuel pool of Bushehr NPP using the RELAP5 and MELCOR [PDF]

مجله علوم و فنون هسته‌ای, 2020
Following the Fukushima Daiichi accident, the simulation of accidents related to the Spent Fuel Pool (SFP) became more important due to the high content of long-lived radionuclides, and lack of the protection by the pressure vessel despite its low decay ...
S. Gol Narges, S.Kh. Mousavian
doaj   +1 more source

Simulations of Core Damage Progression for TMI‐2 Severe Accident Using CINEMA Computer Code

Science and Technology of Nuclear Installations, Volume 2023, Issue 1, 2023., 2023
As an integrated computer code development for severe accident sequence analysis in Korea, CINEMA has been developing from an initiation event to a containment failure. The CINEMA computer code is composed of CSPACE, SACAP, and SIRIUS, which are capable of simulating core melt progression with thermal hydraulic analysis of the RCS (reactor coolant ...
Rae-Joon Park, Donggun Son, Jun Ho Bae, Sung Won Bae, Bub-Dong Chung, Kwang Soon Ha, Han Zhang   +6 more
wiley   +1 more source

Experimental study and safety analysis on the heating surfaces in the 660 MW supercritical CFB boiler under sudden electricity failure

Energy Science &Engineering, Volume 10, Issue 7, Page 2088-2105, July 2022., 2022
In this project, the necessity of equipping with an emergency water supply system in a supercritical circulating fluidized bed (CFB) boiler has long been a controversial topic in the industry. And a boiler electricity failure experiment was accomplished, a mathematical model established and a calculation program developed.
Yinlong Li, Beibei Xie, Lingfeng Bi, Haoyu Yang, Chao Nie, Hao Qing, Dong Yang   +6 more
wiley   +1 more source

Development of a RELAP5/MOD3.3 Module for MHD Pressure Drop Analysis in Liquid Metals Loops: Verification and Validation

Energies, 2021
Magnetohydrodynamic (MHD) phenomena, due to the interaction between a magnetic field and a moving electro-conductive fluid, are crucial for the design of magnetic-confinement fusion reactors and, specifically, for the design of the breeding blanket ...
Lorenzo Melchiorri, Vincenzo Narcisi, Fabio Giannetti, Gianfranco Caruso, Alessandro Tassone   +4 more
doaj   +1 more source

SCDAP/RELAP5/MOD2 code manual [PDF]

, 1990
This report describes the materials properties correlations and computer subcodes (MATPRO) developed for use with various light water reactor (LWR) accident analysis computer programs. Formulation of the materials properties are generally semiempirical in nature.
Hohorst, J. K. (ed.) (EG, G Idaho, Inc., Idaho Falls, ID (USA))   +5 more
openaire   +2 more sources

The Concept of the Heat Removal System of a High‐Flux Research Reactor

Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022
Achieving high neutron fluxes in research pressurized water reactors is directly related to the intensity of the coolant flow through the core and the pressure in it, which provides an increased saturation temperature and a margin to critical heat flux.
Vitaly Uzikov, Ildar Suleimanov, Irina Uzikova, Alejandro Clausse   +3 more
wiley   +1 more source