STEAM CYCLES FOR POWER REACTORS. PART 2

Journal Article · Sat Oct 01 04:00:00 EDT 1960 · Nuclear Power

OSTI ID:4127915

Thomas, W J; Lorge, R A

The problem of excess terminal-steam wetness due to efficiency is discussed. Regenerative feed heating improves efficiency, but not in nuclear stations working at low pressures. The steam pressure can be adjusted by rearranging the heating surfaces in the steam raising unit. Superheating of low- and high pressure steam increases efficiency while avoiding excess steam wetness. Various means are available for reducind steam wetness, e.g., internal drain boards and grooved turbine blades, and the type of expansion that can be obtained in this way is illustrated as a Mollier diagram for the Dresden BWR turbine fitted with grooved blades. Reheat of high-pressure steam It is used in the Dungeness and Tokai-Mura reactors. The integral nuclear steam generator, patented 5 years ago, is discussed. The PWR and BWR are discussed with respect to advantages and disadvantages of secondary circuits and heat exchangers. Externally fired super-and re-heaters (hybrid stations) are discussed, but they are not worth while in comparison with reactors having higher reactor-coolant temperatures . Some of the operating conditions are given for the advanced high- temperature gas-cooled reactors giving 930 to 2400 deg F coolant-outlet temperatures. Reactors using nuclear superheating of the working steam in the core are now in the design or building stage (Borax V, Bonus, Pathfinder, Vickers Marine, and Ural), and some of their operating conditions are given. A combined flow and heat-steam diagram is shown for the Vickers Marine reactor which has a thermocompressor in place of coolant circulators. If these reactor projects are successful, large nuclear stations in the 1970's can be expected to approach the steam cycles of conventional stations.

• Research Organization: Kennedy and Donkin, London
• NSA Number: NSA-15-002356
• OSTI ID: 4127915
• Journal Information: Nuclear Power, Journal Name: Nuclear Power Journal Issue: 54 Vol. 5; ISSN 0546-8981; ISSN NUPOAS
• Country of Publication: United Kingdom
• Language: English

Related Subjects

BORAX-5
CIRCUITS
COOLING
DRESDEN
DUNGENESS
EFFICIENCY
GAS COOLANT
HEAT EXCHANGERS
HIGH TEMPERATURE
MOUNTAINS
PATHFINDER
PRESSURE
REACTOR TECHNOLOGY
REACTORS
STEAM
SUPERHEATING
TEMPERATURE
TOKAI-MURA
USSR