scholarly journals Large high-temperature gas-cooled reactor medium-enriched uranium spent fuel element definitions and block flows. Volume II

1978 ◽  
Author(s):  
G. Zane ◽  
D. Georghiou ◽  
C. Everline
Keyword(s):  
High Temperature ◽  
Fuel Element ◽  
Spent Fuel ◽  
Enriched Uranium ◽  
High Temperature Gas

Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM

2018 ◽  
Author(s):  
Jinhua Wang ◽  
Bing Wang ◽  
Bin Wu ◽  
Yue Li ◽  
Haitao Wang
Keyword(s):  
High Temperature ◽  
Fuel Element ◽  
Nuclear Power ◽  
Storage System ◽  
Spent Fuel ◽  
Graphite Matrix ◽  
Fuel Storage ◽  
Fuel Elements ◽  
And Storage ◽  
High Temperature Gas

With the continuous development of the nuclear power technology in the world, all countries in the world are becoming more and more interested in the inherent safety of nuclear power technology, while the research and development of the spherical bed type high temperature gas cooled reactor nuclear power technology in China has formally catered to this demand. As a major national science and technology project, since the construction of the high temperature gas cooled reactor demonstration project (HTR-PM) since 2012, the civil construction of the nuclear island has been basically completed, the installation of equipment has been carried out orderly, and many process systems have entered debugging and operation stage gradually. As an important auxiliary process system, fuel handling and storage system for online refueling of the pebble bed high temperature gas cooled reactor, plays an important role in relation to the stable operation of the reactor. The main functions of the fuel handling and storage system are loading the fresh fuel elements and unloading the spent fuel elements which has reached its target burnup continuously for reactor operation, the spent fuel elements would be discharged into the spent fuel canister firstly, when the spent fuel storage canister is full of spent fuel, the canister would be sealed through welding method, and then the spent fuel canister would be transferred and stored in the spent fuel storage silo with the ground crane system. The fuel element of the pebble bed high temperature gas cooled reactor is spherical fuel element with graphite matrix, the fuel elements will have friction and collision with the inner wall of the pipeline in transporting process, which will produce graphite dust, the graphite dust should be removed continuously though filtration method, so as not to affect the fuel elements transportation in pipeline. This article focus on the production mechanism and filtering method of the graphite dust in graphite matrix fuel element transporting process in pipeline, to study the graphite dust removal technology, and then we could provide theoretical guidance for the design and operation of the key system and equipment for HTR-PM.

Research and Development of Fuel Element for Chinese 10 MW High Temperature Gas-cooled Reactor

2000 ◽  
Vol 37 (9) ◽  
pp. 802-806 ◽  
Author(s):  
Chunhe TANG ◽  
Yaping TANG ◽  
Junguo ZHU ◽  
Xueliang QIU ◽  
Jihong LI ◽  
...  
Keyword(s):  
High Temperature ◽  
Research And Development ◽  
Fuel Element ◽  
High Temperature Gas

scholarly journals Development of Fabrication and Inspection Technologies for Oxidation-Resistant Fuel Element for High-Temperature Gas-Cooled Reactors

2019 ◽  
Vol 18 (4) ◽  
pp. 237-245
Author(s):  
Jun AIHARA ◽  
Atsushi YASUDA ◽  
Shohei UETA ◽  
Hiroaki OGAWA ◽  
Masaki HONDA ◽  
...  
Keyword(s):  
High Temperature ◽  
Fuel Element ◽  
Oxidation Resistant ◽  
High Temperature Gas

Thorium Cycle in High Temperature Gas-Cooled Gas Turbine Reactors (HTG-GT) Using Highly Enriched Uranium Obtained From the Dismantling of Nuclear Weapons

1994 ◽  
Author(s):  
Nicola Cerullo ◽  
Giovanni Guglielmini ◽  
A. Di Pietro
Keyword(s):  
High Temperature ◽  
Gas Turbine ◽  
Nuclear Weapons ◽  
Fuel Cycle ◽  
Fissile Material ◽  
High Investment ◽  
Enriched Uranium ◽  
The Cold War ◽  
Thorium Cycle ◽  
High Temperature Gas

The closed thorium fuel cycle is based on the use of fissile U-233 produced by the thorium fertilization in the original fuel element without any refabrication action, which is very difficult, due to the high activity of Thorium activated products. The need of a consistent amount of fissile material for beginning the U-Th cycle activity, in order to sustain the Thorium conversion reactions, requires an high initial U-235 enrichment. This condition, due to high investment costs, stopped, in the last years, any initiative in this field. The end of the cold war and the disarmament agreements pose the problem of the use of military grade fissile materials resulting from the dismantling of nuclear weapons both Russian and American. In this paper the problem is analyzed and a High Temperature Gas-cooled Gas Turbine (HTG-GT) reactor, using a nuclear U-Th fuel cycle utilizing military grade highly enriched uranium, is proposed.

A Natural Circulation Waste Heat Recovery System for High Temperature Gas-Cooled Reactor Used and/or Spent Fuel Tanks: Part I — Design Considerations and Theoretical Simulation

2013 ◽  
Author(s):  
Franck M. Senda ◽  
Robert T. Dobson
Keyword(s):  
High Temperature ◽  
Heat Recovery ◽  
Waste Heat Recovery ◽  
Waste Heat ◽  
Natural Circulation ◽  
Heat Transfer Process ◽  
Spent Fuel ◽  
Fuel Tanks ◽  
High Temperature Gas ◽  
The Way

This paper presents potential application of waste heat recovery (WHR) systems in high-temperature reactors technology. WHR systems have attracted the attention of many researchers over the past two decades, as using waste heat improves the system overall efficiency, notwithstanding the additional cost to upgrade the plant efficiency. WHR systems require specially designed heat recovery equipment, and as such the high-temperature gas-cooled reactor used and/or spent fuel tanks (SFTs) were considered by the way of example. An appropriately scaled system was designed and modelled to demonstrate the functioning of such a system, by the way of a cooling process of the used and/or SFT. Two separate and independent cooling lines, using a natural circulation flow in a particular form of heat pipes called thermosyphon loops were used to ensure that the fuel tank (FT) is cooled when the power conversion unit has to be switched off for maintenance, or if it fails. Assuming a one-dimensional flow model, a quasi-static and incompressible flow of both liquid and vapour, a theoretical model that simulates the heat transfer process in the as-designed WHR system is developed in this paper.

The Gasification of Graphite Matrix in Pebble Bed Reactors

2009 ◽  
Author(s):  
Xinli Yu ◽  
Suyuan Yu
Keyword(s):  
High Temperature ◽  
Corrosion Rate ◽  
Fuel Element ◽  
Pebble Bed ◽  
The Core ◽  
Graphite Matrix ◽  
Matrix Graphite ◽  
Element Matrix ◽  
Fuel Elements ◽  
High Temperature Gas

This paper mainly deals with the simulations of graphite matrix of the spherical fuel elements by steam in normal operating conditions. The fuel element matrix graphite was firstly simplified to an annular part in the simulations. Then the corrosions to the matrix graphite in 10 MW High Temperature Gas-cooled Reactor (HTR-10) and the High Temperature Gas-cooled Reactor—–Pebble-bed Module (HTR-PM) were investigated respectively. The results showed that the gasification of fuel element matrix graphite was uniform and mainly occurred at the bottom of the core in both of the reactors in the mean residence time of the spherical fuel elements. This was mainly caused by the designed high temperature at the bottom. The total mass gasified in HTR-PM was much greater than the HTR-10, while it did not mean much severer corrosion occurred there. As it is known the core volume of HTR-PM is much larger than the HTR-10, which will result in much greater consumed graphite even for the same corrosion rate. The steam only lost about 1 to 3 percent after flowing through the cores in both reactors for different steam conditions. The corrosion of graphite became worse when the steam concentrations increased in helium coolant. The results also indicated that the corrosion rate of fuel element matrix graphite tended to increase slightly with the prolonging of the service time.

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