Abstract
Double barrier sodium/water steam raising units were incorporated into the early DFR which has been operating since 1958, but to be economically viable the PFR units had to adopt a single wall concept. It should be remembered that the design style of PFR was decided upon in the early 1960's, when a very cautious approach had to be made. It was vital to ensure that a steam raising unit had the maximum availability and so a forced circulation system was chosen, making the steam generators consistent with all other power station boilers installed in the U.K. at that time. It is only recently that once-through steam cycles have been accepted in this country by the CEGB and these are on the A.G.R. stations currently being built. The 250 MWe Prototype Fast Reactor incorporates the world's largest sodium heated boilers and having gone critical some 6 months ago is currently undergoing various commissioning trials prior to its run-up to full power. The paper gives a brief description of these, with comments on particular features of Design, Development, nd countered to date are discussed, together with the way in which these have been overcome. Extensive research and development work has been carried
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Citation Formats
Hayden, O.
Design and construction of past and present steam generators for the UK fast reactors.
IAEA: N. p.,
1975.
Web.
Hayden, O.
Design and construction of past and present steam generators for the UK fast reactors.
IAEA.
Hayden, O.
1975.
"Design and construction of past and present steam generators for the UK fast reactors."
IAEA.
@misc{etde_20107663,
title = {Design and construction of past and present steam generators for the UK fast reactors}
author = {Hayden, O}
abstractNote = {Double barrier sodium/water steam raising units were incorporated into the early DFR which has been operating since 1958, but to be economically viable the PFR units had to adopt a single wall concept. It should be remembered that the design style of PFR was decided upon in the early 1960's, when a very cautious approach had to be made. It was vital to ensure that a steam raising unit had the maximum availability and so a forced circulation system was chosen, making the steam generators consistent with all other power station boilers installed in the U.K. at that time. It is only recently that once-through steam cycles have been accepted in this country by the CEGB and these are on the A.G.R. stations currently being built. The 250 MWe Prototype Fast Reactor incorporates the world's largest sodium heated boilers and having gone critical some 6 months ago is currently undergoing various commissioning trials prior to its run-up to full power. The paper gives a brief description of these, with comments on particular features of Design, Development, nd countered to date are discussed, together with the way in which these have been overcome. Extensive research and development work has been carried out in support of Prototype Reactor and some of this continues well into the manufacture and commissioning programme. Critical areas such as tube-to-tubesheet welding, tube-grid fretting, burst disc and sodium/ water reaction work involves costly and time-consuming development. Sodium heated steam generators pose a greater number of problems to the designer than either fossil-fired or other types of nuclear steam raising plant. As in any boiler, economics demand that the heat exchanger surface is as compact as possible whilst retaining good 'low distribution inside and outside the tubes. Besides achieving a good thermal and mechanical design, the designer is faced with the possibility of a leak occurring and has to cater for the sodium/water reaction which may follow. Valuable experience has been gained in dealing with the sodium heated steam generators problems arising over the last few years, these have not been welcomed, but lessons have been learnt which will benefit CFR I, the next fully commercial demonstration 1300 MWe reactor now being designed and planned for the late 1970's or early 1980's. (author)}
place = {IAEA}
year = {1975}
month = {Jul}
}
title = {Design and construction of past and present steam generators for the UK fast reactors}
author = {Hayden, O}
abstractNote = {Double barrier sodium/water steam raising units were incorporated into the early DFR which has been operating since 1958, but to be economically viable the PFR units had to adopt a single wall concept. It should be remembered that the design style of PFR was decided upon in the early 1960's, when a very cautious approach had to be made. It was vital to ensure that a steam raising unit had the maximum availability and so a forced circulation system was chosen, making the steam generators consistent with all other power station boilers installed in the U.K. at that time. It is only recently that once-through steam cycles have been accepted in this country by the CEGB and these are on the A.G.R. stations currently being built. The 250 MWe Prototype Fast Reactor incorporates the world's largest sodium heated boilers and having gone critical some 6 months ago is currently undergoing various commissioning trials prior to its run-up to full power. The paper gives a brief description of these, with comments on particular features of Design, Development, nd countered to date are discussed, together with the way in which these have been overcome. Extensive research and development work has been carried out in support of Prototype Reactor and some of this continues well into the manufacture and commissioning programme. Critical areas such as tube-to-tubesheet welding, tube-grid fretting, burst disc and sodium/ water reaction work involves costly and time-consuming development. Sodium heated steam generators pose a greater number of problems to the designer than either fossil-fired or other types of nuclear steam raising plant. As in any boiler, economics demand that the heat exchanger surface is as compact as possible whilst retaining good 'low distribution inside and outside the tubes. Besides achieving a good thermal and mechanical design, the designer is faced with the possibility of a leak occurring and has to cater for the sodium/water reaction which may follow. Valuable experience has been gained in dealing with the sodium heated steam generators problems arising over the last few years, these have not been welcomed, but lessons have been learnt which will benefit CFR I, the next fully commercial demonstration 1300 MWe reactor now being designed and planned for the late 1970's or early 1980's. (author)}
place = {IAEA}
year = {1975}
month = {Jul}
}