US3773618A
Expired / Lapsed
US
⏱️ 0.0 years remaining
Coolant systems for nuclear reactors
Assignee: United Kingdom Atomic Energy Authority
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Filing: 1969-02-06
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Granted: 1973-11-20
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Expires: 1989-02-06
Abstract
Abstract In some reactors the fuel can be run at temperatures above that required by the heat utilisation plant to which the coolant is supplied. In these reactors a saving in pumping power may be achieved by raising only part of the coolant to core inlet pressure and by-passing the rest around the heat emitting part of the core. The by-pass stream is mixed with the hot outlet coolant at the core outlet to give a bulk coolant at the required temperature.
Inventors
- 👤 C Gratton
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-10-27 18:25
CPC Classifications
G; G21; G21D; G21D5/00; G21D5/04; G21D5/06; Y; Y02; Y02E; Y02E30/00
Claims Analysis
Total Claims: 5
Claim 1
Independent Claim
233 words
A method of utilizing heat from a nuclear reactor plant wherein hot gas coolant from a nuclear reactor plant is utilized to supply heat to a heat utilization plant and wherein the temperature of the coolant supplied to said heat utilization plant is maintained at a certain constant desired temperature, said method comprising providing a supply of gas coolant, introducing a first gas coolant stream from said supply to said reactor core for flow through a first flow path in said core at a location operating at a temperature such that the gas coolant is heated to a temperature above said certain constant desired temperature, introducing a second gas coolant stream from said supply into said reactor for flow through a second flow path at a location operating at a temperature such that the gas coolant is heated to a temperature below said certain constant desired temperature, said first flow path comprising interstices between fissile fuel particles and having a greater impedance to coolant flow than that of said second flow path, combining the first and second gas coolant streams exiting from said reactor, passing said combined gas coolant streams to said heat utilization plant, and regulating the relative flow rates of said first and second gas coolant streams such that the combined gas coolant stream from said reactor fed to said heat utilization plant is maintained at said certain constant desired temperature.
Claim 2
Independent Claim
233 words
A method of utilizing heat from a nuclear reactor plant wherein hot gas coolant from a nuclear reactor plant is utilized to supply heat to a heat utilization plant and wherein the temperature of the coolant supplied to said heat utilization plant is maintained at a certain constant desired temperature, said method comprising providing a supply of gas coolant, introducing a first gas coolant stream from said supply to said reactor core for flow through a first flow path in said core at a location operating at a temperature such that the gas coolant is heated to a temperature above said certain constant desired temperature, introducing a second gas coolant stream from said supply into said reactor for flow through a second flow path at a location operating at a temperature such that the gas coolant is heated to a temperature below said certain constant desired temperature, said first flow path comprising interstices between fissile fuel particles and having a greater impedance to coolant flow than that of said second flow path, combining the first and second gas coolant streams exiting from said reactor, passing said combined gas coolant streams to said heat utilization plant, and regulating the relative flow rates of said first and second gas coolant streams such that the combined gas coolant stream from said reactor fed to said heat utilization plant is maintained at said certain constant desired temperature.
Claim 3
Dependent Claim
19 words
A method according to claim 1 wherein said core is operated at a temperature near its maximum design temperature.
Claim 4
Dependent Claim
39 words
A method according to claim 1 wherein said first coolant stream is raised to a high pressure for passage through said reactor core, and said second coolant stream is raised to a lower pressure for passage through said reactor.
Claim 5
Dependent Claim
19 words
A method according to claim 1 wherein said second coolant stream passes through a fertile region of the reactor.
References Cited (Backward Citations)
No citation records indexed.
USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1976-11-19 | 1977-05-21 | 1977-11-20 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1980-11-19 | 1981-05-21 | 1981-11-20 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1984-11-19 | 1985-05-21 | 1985-11-20 | $7700.00 | Window Closed / Lapsed |