technology of the gas-cooled power reactor andrelated subjects
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technology of the gas-cooled power reactor andrelated subjects papers presented by the U. K. A. E. A. to the Second United Nations Conference.... by International Conference on the Peaceful Uses of Atomic Energy (2nd 1958 Geneva)

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Published by U. K. A. E. A. .
Written in English


Book details:

The Physical Object
Pagination196p.
Number of Pages196
ID Numbers
Open LibraryOL14113699M

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  For further reading try: "Description of the Advanced Gas Cooled Type of Reactor (AGR)" which currently can be downloaded free from more than one source on the internet. Dungeness 'B' cutaway. The gas-cooled fast reactor (GFR) system is a nuclear reactor design which is currently in d as a Generation IV reactor, it features a fast-neutron spectrum and closed fuel cycle for efficient conversion of fertile uranium and management of reference reactor design is a helium-cooled system operating with an outlet temperature of °C using . A review is given of developments in the area of Gas-Cooled Fast Reactors (GCFR) in the period from roughly until During that period, the GCFR concept was expected to increase the breeding gain, the thermal efficiency of a nuclear power plant, and alleviate some of the problems associated with liquid metal coolants. During this period, the GCFR concept was found to be Cited by: An Advanced Gas-cooled Reactor (AGR) is a type of nuclear reactor designed and operated in the United Kingdom. These are the second generation of British gas-cooled reactors, using graphite as the neutron moderator and carbon dioxide as coolant. They have been the backbone of the UK's nuclear generation fleet since the s. The AGR was developed from the .

Pioneering Science and Technology GFR Project Objective ¾To Design a Gas cooled Fast Reactor System with A high level of Safety − Successful decay heat removal under wide range of pressurized and depressurized conditions − Survive loss of active reactivity shutdown capability without core damage A Full Recycling of Actinides.   An Advanced Gas-cooled Reactor is a specific type of nuclear reactor. These are the second generation of British gas-cooled reactors, using graphite as the neutron moderator and carbon dioxide as. High Temperature Gas-cooled Reactor (HTGR), which is a graphite moderated, helium cooled reactor, is particularly attractive due to capability of producing high temperature helium gas and its inherent safety characteristics, as well as an option to efficiently burn weapons-grade plutonium for energy Size: 2MB. The GFR system is a high-temperature helium-cooled fast-spectrum reactor with a closed fuel cycle. It combines the advantages of fast-spectrum systems for long-term sustainability of uranium resources and waste minimisation (through fuel multiple reprocessing and fission of long-lived actinides), with those of high-temperature systems (high thermal cycle efficiency and industrial .

  Note: I’m a young whipper-snapper at 30 years old, so the following is more a representation of my historical learnings/readings than any firsthand account. There is some level of conjecture filling in the gaps here, but I hope it still gives some. Scientific researches of new technological platform realization carried out in Russia are based on ideas of nuclear fuel breeding in closed fuel cycle and physical principles of fast neutron reactors. Innovative projects of low-power reactor systems correspond to the new technological platform. High-temperature gas-cooled thorium reactors with good transportability properties, small Cited by: 6. Other articles where High-temperature gas-cooled reactor is discussed: nuclear reactor: High-temperature gas-cooled reactors: The high-temperature gas-cooled reactor (HTGR), as mentioned above in Fuel types, is fueled by a mixture of graphite and fuel-bearing microspheres. There are two competitive designs of this reactor type: (1) a German “pebble bed” system that . Description. This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments.