A SURVEY OF CONVENTIONAL STEAM BOILER EXPERIENCE APPLICABLE TO THE HTGR STEAM GENERATORS
BS>The steam generator of a high temperature gas-cooled reactor consists of tubular heating surface inside a shell which forms part of the primary He circuit of the reactor. When a tube fails in such a steam generator, moisture in the form of steam is released into the He steam and is carried through the reactor where it will cause corrosion and mass transfer of C in the core. A paramount consideration in the design of a steam generator for a high temperature gas-cooled reactor is the prevention of tube failures. Preference, therefore, should be given to a forced circulation design. The Loeffler Boiler would be the best from this standpoint alone since only steam enters the tubes, and its circulation rate can be maintained at an adequate value to insure cool tubes regardless of load fluctuations. The next type in the order of preference would be the forced recirculation boiler, since at least the boiier tubes always have an adequate cooling flow regardless of output. The third type in order of preference would be a Sulzer Type boiler since it has a separator to remove dissolved material from the water which is comparible in efficiency to a standard boiler drum and although the flow through evaporator and superheater fluctuates with load, the Sulzer Boiler can be operated as a forced recirculation boiler at low loads. The least desirable type would be a Benson or supercritical boiler which is completely dependent on input water purity for its survival. It is not claimed that Benson or supercritical boilers should not or will not be used in the future for gas-cooled reactors, but only that their use would be the least conservative choice from a tube failure standpoint at the present time. (auth)
- Research Organization:
- General Atomic Div. General Dynamics Corp., San Diego, Calif.
- DOE Contract Number:
- AT(04-3)-314
- NSA Number:
- NSA-16-012737
- OSTI ID:
- 4797455
- Report Number(s):
- GAMD-1208
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-62
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BOILING
CARBON
COMPRESSORS
COOLANT LOOPS
CORROSION
CORROSION PROTECTION
EROSION
FAILURES
GAS COOLANT
GAS FLOW
GRAPHITE MODERATOR
HEAT EXCHANGERS
HEAT TRANSFER
HELIUM
HIGH TEMPERATURE
HTGR
HUMIDITY
IMPURITIES
LEAKS
PLANNING
POWER
POWER PLANTS
PRESSURE
PRODUCTION
REACTOR CORE
REACTOR SAFETY
STEAM
SURFACES
THERMAL STRESSES
TUBES
VARIATIONS
WATER COOLANT