US3184389A
Expired / Lapsed
US
⏱️ 0.0 years remaining
Fine control of a suspension nuclear reactor
Assignee: STICHTING REACTOR CENTRUM
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Filing: 1961-12-28
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Granted: 1965-05-18
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Expires: 1981-12-28
Abstract
No abstract record available.
Inventors
- 👤 Johannes A H Kersten
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-11-08 23:37
CPC Classifications
G; G21; G21D; G21D3/00; G21D3/08; G21D3/18; G21C; G21C1/00; G21C1/04; G21C1/06; G21C1/22; Y; Y02; Y02E; Y02E30/00; Y02E30/30; Y10; Y10S; Y10S376/00; Y10S376/90; Y10S376/904
Claims Analysis
Total Claims: 4
Claim 1
Independent Claim
173 words
A METHOD FOR THE FINE CONTROL OF THE POWER LEVEL OF A NUCLEAR REACTOR, IN WHICH REACTOR A PROCESS IS ESTABLISHED FOR A SELF-SUSTAINING NEUTRON CHAIN NUCLEAR FISSION REACTION, THE SAID REACTOR BEING A PART OF A SYSTEM, SAID SYSTEM COMPRISING A NUCLEAR FUEL SUSPENSION OF SOLID FISSILE MATERIAL PARTICLES IN WATER AND A REACTOR ASSEMBLY, SAID REACTOR ASSEMBLY COMPRISING A REACTOR-CIRCUIT AND CONTROL APPARATUS, SAID REACTOR-CIRCUIT COMPRISING THE SAID NUCLEAR REACTOR WHEREIN CRITICAL CONDITIONS PREVAIL AND AN EXTERNAL CIRCUIT INCLUDING A HEAT-EXCHANGER, WHEREIN NON-CRITICAL CONDITIONS PREVAIL, THE SAID NUCLEAR FUEL SUSPENSION CIRCULATING THROUGH SAID REACTOR-CIRCUIT, THE IMPROVEMENT COMPRISING GRADUALLY ADDING TO THE SAID CIRCULATING FUEL SUSPENSION A SMALL QUANTITY OF AN AQUEOUS SOLUTION OF A BASE SELECTED FROM THE GROUP CONSISTING OF SODIUM HYDROXIDE AND AMMONIA IN AN AMOUNT OF 0.3CC. OF A 0.1 NORMAL SOLUTION OF THE BASE PER LITER OF CIRCULATING NUCLEAR FUEL SUSPENSION, SAID ADDITION BEGINNING AS SOON AS ABNORMAL FLUCTUATIONS OF THE POWER LEVEL ARE MEASURED, AND ENDING AS SOON AS THE SAID ABNORMAL FLUCTUATION MEASUREMENTS HAVE DISAPPEARED.
Claim 2
Independent Claim
173 words
A METHOD FOR THE FINE CONTROL OF THE POWER LEVEL OF A NUCLEAR REACTOR, IN WHICH REACTOR A PROCESS IS ESTABLISHED FOR A SELF-SUSTAINING NEUTRON CHAIN NUCLEAR FISSION REACTION, THE SAID REACTOR BEING A PART OF A SYSTEM, SAID SYSTEM COMPRISING A NUCLEAR FUEL SUSPENSION OF SOLID FISSILE MATERIAL PARTICLES IN WATER AND A REACTOR ASSEMBLY, SAID REACTOR ASSEMBLY COMPRISING A REACTOR-CIRCUIT AND CONTROL APPARATUS, SAID REACTOR-CIRCUIT COMPRISING THE SAID NUCLEAR REACTOR WHEREIN CRITICAL CONDITIONS PREVAIL AND AN EXTERNAL CIRCUIT INCLUDING A HEAT-EXCHANGER, WHEREIN NON-CRITICAL CONDITIONS PREVAIL, THE SAID NUCLEAR FUEL SUSPENSION CIRCULATING THROUGH SAID REACTOR-CIRCUIT, THE IMPROVEMENT COMPRISING GRADUALLY ADDING TO THE SAID CIRCULATING FUEL SUSPENSION A SMALL QUANTITY OF AN AQUEOUS SOLUTION OF A BASE SELECTED FROM THE GROUP CONSISTING OF SODIUM HYDROXIDE AND AMMONIA IN AN AMOUNT OF 0.3CC. OF A 0.1 NORMAL SOLUTION OF THE BASE PER LITER OF CIRCULATING NUCLEAR FUEL SUSPENSION, SAID ADDITION BEGINNING AS SOON AS ABNORMAL FLUCTUATIONS OF THE POWER LEVEL ARE MEASURED, AND ENDING AS SOON AS THE SAID ABNORMAL FLUCTUATION MEASUREMENTS HAVE DISAPPEARED.
Claim 3
Dependent Claim
183 words
A NUCLEAR REACTOR ASSEMBLY, COMPRISING A NUCLEAR REACTOR CONSTRUCTED AS A PRESSURE VESSEL, HAVING INLET AND OUTLET FOR PASSING THROUGH THE REACTOR A CONTINUOUS STREAM OF A SUSPENSION OF SOLID FISSILE MATERIAL IN A LIQUID, THE SAID PRESSURE VESSEL SURROUNDED BY A NEUTRON REFLECTOR AND BEING OF SUCH A SHAPE, THAT CRITICAL CONDITIONS THEREIN WILL PREVAIL IF THE SAID PRESSURE VESSEL IS COMPLETELY FILLED WITH THE SAID SUSPENSION OF SOLID FISSIBLE MATERIAL, AN EXTERNAL CIRCUIT INCLUDING A HEAT EXCHANGER, WHEREIN NON-CRITICAL CONDITIONS PREVAIL, THE SAID EXTERNAL CIRCUIT CONNECTED TO THE INLET AND OUTLET OF THE SAID PRESSURE VESSEL OF THE NUCLEAR REACTOR, A PUMP MOUNTED IN THE SAID EXTERNAL CIRCUIT FOR THE CIRCULATION OF THE SAID SUSPENSION THROUGH REACTOR AND EXTERNAL CIRCUIT, A CONTINUOUSLY OPERATING NEUTRON FLUX METER, SITUATED WITHIN THE MEASURABLE FLUX FIELD OF THE REACTOR, A DIFFERENTIAL AMPLITUDE CONTROLLER WITH A LOW PASS FREQUENCY BAND WIDTH LIMIT, WHICH IS COUPLED TO THE SAID METER AND WHICH IS OPERATIVELY CONNECTED TO AN AUTOMATIC CONTROL VALVE IN A CONDUIT WHICH CONNECTS A STORAGE TANK FOR ELECTROLYTE TO THE SPACE FOR THE CIRCULATING SUSPENSION.
Claim 4
Dependent Claim
183 words
A NUCLEAR REACTOR ASSEMBLY, COMPRISING A NUCLEAR REACTOR CONSTRUCTED AS A PRESSURE VESSEL, HAVING INLET AND OUTLET FOR PASSING THROUGH THE REACTOR A CONTINUOUS STREAM OF A SUSPENSION OF SOLID FISSILE MATERIAL IN A LIQUID, THE SAID PRESSURE VESSEL SURROUNDED BY A NEUTRON REFLECTOR AND BEING OF SUCH A SHAPE, THAT CRITICAL CONDITIONS THEREIN WILL PREVAIL IF THE SAID PRESSURE VESSEL IS COMPLETELY FILLED WITH THE SAID SUSPENSION OF SOLID FISSIBLE MATERIAL, AN EXTERNAL CIRCUIT INCLUDING A HEAT EXCHANGER, WHEREIN NON-CRITICAL CONDITIONS PREVAIL, THE SAID EXTERNAL CIRCUIT CONNECTED TO THE INLET AND OUTLET OF THE SAID PRESSURE VESSEL OF THE NUCLEAR REACTOR, A PUMP MOUNTED IN THE SAID EXTERNAL CIRCUIT FOR THE CIRCULATION OF THE SAID SUSPENSION THROUGH REACTOR AND EXTERNAL CIRCUIT, A CONTINUOUSLY OPERATING NEUTRON FLUX METER, SITUATED WITHIN THE MEASURABLE FLUX FIELD OF THE REACTOR, A DIFFERENTIAL AMPLITUDE CONTROLLER WITH A LOW PASS FREQUENCY BAND WIDTH LIMIT, WHICH IS COUPLED TO THE SAID METER AND WHICH IS OPERATIVELY CONNECTED TO AN AUTOMATIC CONTROL VALVE IN A CONDUIT WHICH CONNECTS A STORAGE TANK FOR ELECTROLYTE TO THE SPACE FOR THE CIRCULATING SUSPENSION.
References Cited (Backward Citations)
US3054738A
Cited
US3046212A
Cited
USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1968-05-17 | 1968-11-16 | 1969-05-18 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1972-05-17 | 1972-11-16 | 1973-05-18 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1976-05-17 | 1976-11-16 | 1977-05-18 | $7700.00 | Window Closed / Lapsed |