Results 31 to 40 of about 99,355 (324)

A new method for characterizing the heat transfer capacity of the divertor and high heat flux components

Nuclear Fusion, 2023
The divertor is usually exposed to extreme incident heat flux conditions in nuclear fusion engineering and its ability to remove the heat is extremely crucial for the safe operation of magnetic confinement nuclear fusion device.
Qianqian Lin, Lei Cao, Qing Zhuang, Nanyu Mou, Le Han, Damao Yao   +5 more
doaj   +1 more source

Fade-out time shortening on radiotoxicity and decay heat using TRU generation reduction fuel

Mechanical Engineering Journal, 2023
We analyzed the possibility of TRU generation reduction fuel using HALEU as the initial enrichment to reduce the radiotoxicity and decay heat of TRU when using the LWR fuels that can suppress radiotoxicity and decay heat in HLW. Fade-out time was defined
Kouji HIRAIWA, Rei KIMURA, Satoshi WADA, Tsukasa SUGITA, Kenichi YOSHIOKA, Satoshi TAKEDA, Takanori KITADA   +6 more
doaj   +1 more source

CLIRA DECAY HEAT REMOVAL TEST. [PDF]

, 1972
This report describes the design and fabrication of an electrically heated test section that was used to simulate the heat transport associated with the handling, after irradiation and discharge from the reactor vessel, of a fueled Fast Flux Test Facility (FFTF) closed loop test assembly while in the air-cooled ex-vessel handling machine.
Winegardner, W. K., Romsos, W. N.
openaire   +2 more sources

Dynamic Hybrid Reliability Studies of a Decay Heat Removal System [PDF]

International Journal of Reliability, Quality and Safety Engineering, 2015
Some critical safety systems exhibit the characteristics of hybrid stochastic class whose performance depends on the dynamic interactions of deterministic variables of physical phenomena and probabilistic variables of system failures. However, conventional probabilistic safety assessment (PSA) method involves static event and linked fault tree analysis
Kumar, Ranjan, Bechta, Sevostian, Kudinov, Pavel, Curnier, Florence, Marques, Michel   +4 more
openaire   +2 more sources

MANAGING A PROLONGED STATION BLACKOUT CONDITION IN AHWR BY PASSIVE MEANS

Nuclear Engineering and Technology, 2013
Removal of decay heat from an operating reactor during a prolonged station blackout condition is a big concern for reactor designers, especially after the recent Fukushima accident.
MUKESH KUMAR, A K NAYAK, V JAIN, P K VIJAYAN, K K VAZE   +4 more
doaj   +1 more source

Water film covering characteristic on horizontal fuel rod under impinging cooling condition

Nuclear Engineering and Technology, 2022
Jet impinging device is designed for decay heat removal on horizontal fuel rods in a low temperature heating reactor. An experimental system with a fuel rod simulator is established and experiments are performed to evaluate water film covering capacity ...
Penghui Zhang, Bowei Wang, Ronghua Chen, G.H. Su, Wenxi Tian, Suizheng Qiu   +5 more
doaj   +1 more source

Characteristic analysis of natural circulation residual heat removal in small reactor

International Journal of Advanced Nuclear Reactor Design and Technology, 2022
In order to study the characteristics of small helium-xenon cooled nuclear reactor that only relies on natural circulation to remove residual heat after shutdown, this paper carries out geometric and physical modeling of helium-xenon cooled nuclear ...
Haoyang Liao, Xianbo Wang, Jia Ma, Fulong Zhao, Chengtao Li, Sichao Tan   +5 more
doaj   +1 more source

Asymmetric Decay Heat Removal in MYRRHA: Experiments in the E-SCAPE Facility

20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20), 2023
MYRRHA is an accelerator-driven system, coupling a proton accelerator to a subcritical reactor cooled by lead-bismuth eutectic (LBE), under development by SCK CEN in Belgium. The reactor design is based on a pool configuration, all components of the primary system housed within the main vessel.
Pacio, Julio, Serrano Diogo, Rui, Van Tichelen, Katrien   +2 more
openaire   +2 more sources

The Gas-Cooled Fast Reactor: Report on Safety System Design for Decay Heat Removal [PDF]

, 2003
The gas-cooled fast reactor (GFR) was chosen as one of the Generation IV nuclear reactor systems to be developed based on its excellent potential for sustainability through reduction of the volume and radiotoxicity of both its own fuel and other spent ...
Driscoll, M. J., Feldman, E. E., Weaver, K. D., Marshall, T., Wei, T. Y. C., Ludewig, H.   +5 more
core   +1 more source

Passive decay heat removal system design for the integral inherent safety light water reactor (I2S-LWR)

, 2020
The Integral, Inherently Safe Light Water Reactor (I2S-LWR) is an innovative Pressurized Water Reactor (PWR) concept being developed by a multi-institutional team led by Georgia Tech and in collaboration with Westinghouse, under the Department of Energy ...
Mingjun Wang, A. Manera, V. Petrov, M. Memmott, S. Qiu, G. Su   +5 more
semanticscholar   +1 more source