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Title: US4582672: Method and apparatus for preventing inadvertent criticality in a nuclear fueled electric powering generating unit
[ Derwent Title ]


Country: US United States of America

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15 pages

 
Inventor: Tuley, Jr., Charles R.; Penn Township, Westmoreland County, PA
Bauman, Douglas A.; Murrysville, PA
Feilchenfeld, Michal M.; Pittsburgh, PA
Greenberg, Lesley; Monroeville, PA
Neuner, James A.; Gibsonia, PA

Assignee: Westinghouse Electric Corp., Pittsburgh, PA
other patents from WESTINGHOUSE ELECTRIC CORP. (625115) (approx. 12,106)
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Published / Filed: 1986-04-15 / 1982-08-11

Application Number: US1982000407231

IPC Code: Advanced: G21C 9/00; G21C 17/00; G21D 3/06;
Core: G21D 3/00; more...
IPC-7: G21C 17/00;

U.S. Class: Current: 376/254; 376/215; 376/255; 376/328; 976/DIG.139; 976/DIG.299;
Original: 376/254; 376/255; 376/215;

Field of Search: 376/254,255,259,214-218 250/390-392

Priority Number:
1982-08-11  US1982000407231

Abstract: An inadvertent approach to criticality in a nuclear fueled electric power generating unit is detected and an alarm is generated through on-line monitoring of the neutron flux. The difficulties of accurately measuring the low levels of neutron flux in a subcritical reactor are overcome by the use of a microcomputer which continuously generates average flux count rate signals for incremental time periods from thousands of samples taken during each such period and which serially stores the average flux count rate signals for a preselected time interval. At the end of each incremental time period, the microcomputer compares the latest average flux count rate signal with the oldest, and preferably each of the intervening stored values, and if it exceeds any of them by at least a preselected multiplication factor, an alarm is generated. The interval and multiplication factor are chosen such that an alarm is generated early enough in the event to provide adequate time for an automatic system or the operator to take action which prevents the reactor from going critical yet minimizes the likelihood of a spurious response. As applied to a pressurized water reactor system, boron dilution events are detected in time that the chemical and volume control system can be isolated and the valves for the refueling water storage tank can be opened to inject highly borated water into the reactor coolant system to keep the reactor subcritical.

Attorney, Agent or Firm: Abeles, Daniel C. ;

Primary / Asst. Examiners: Cangialosi, Salvatore;

Maintenance Status: E2 Expired  Check current status

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Designated Country: BE CH DE IT LI SE 

Family: Show 25 known family members

First Claim:
Show all 19 claims
What is claimed is:     1. A method of detecting an inadvertent approach to criticality in a nuclear fueled electric power generating unit comprising the steps of:
  • generating an instantaneous neutron flux count rate signal representative of the instantaneous neutron flux in the reactor at a level of reactivity of about 10-4 percent reactor power and below;
  • generating from the instantaneous neutron flux count rate signal first and second average flux count rate signals representative of the average neutron flux count rate signal over first and second incremental time periods spaced apart in time by a preset time interval including sampling the instantaneous neutron flux count rate signal repetitively during said incremental time periods and generating said first and second average flux count rate signals as the average of the samples taken during the respective intervals; and
  • comparing said first and second average flux count rate signals and generating an alarm when the second average flux count rate signal exceeds the first average flux count rate signal by at least a preselected multiplication factor.


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Forward References: Show 11 U.S. patent(s) that reference this one

       
U.S. References: Go to Result Set: All U.S. references   |  Forward references (11)   |   Backward references (10)   |   Citation Link

Buy
PDF
Patent  Pub.Date  Inventor Assignee   Title
Buy PDF- 6pp US3366544  1968-01 Bunch   METHOD OF AND APPARATUS FOR CONTROLLING START-UP OF A NUCLEAR REACTOR
Buy PDF- 5pp US3424653  1969-01 Cohn   METHOD FOR START-UP OF A NUCLEAR REACTOR UTILIZING A DIGITAL COMPUTER
Buy PDF- 7pp US3839159  1974-10 Dunnavant et al.  Westinghouse Electric Corporation SYSTEM FOR CONCENTRATING A MODERATING SOLUTION UTILIZED IN A PRESSURIZED WATER NUCLEAR POWER PLANT
Buy PDF- 13pp US3998693  1976-12 Musick  Combustion Engineering, Inc. Thermal margin control
Buy PDF- 7pp US4073683  1978-02 van der Schoot  Westinghouse Electric Corporation Boron control system for a nuclear power plant
Buy PDF- 9pp US4104117  1978-08 Parziale et al.  Westinghouse Electric Corp. Nuclear reactor power generation
Buy PDF- 7pp US4225390  1980-09 Brown et al.  Westinghouse Electric Corp. Boron control system for a nuclear power plant
Buy PDF- 4pp US4297581  1981-10 Brunson et al.  The Babcock & Wilcox Company Method for the fast and accurate identification of core power in nuclear reactors
Buy PDF- 7pp US4305786  1981-12 Schultz  Wachter Associates, Inc. Shutdown reactivity meter system for nuclear fuel storage cells
Buy PDF- 23pp US4427620  1984-01 Cook  Westinghouse Electric Corp. Nuclear reactor power supply
       
Foreign References:
Buy
PDF
Publication Date IPC Code Assignee   Title
Buy PDF - 10pp DE2137504 1973-02  G21C 17/00 Gesellschaft fuer Kernforschung mbH, 7500 Karlsruhe Verfahren und Vorrichtung zur statischen Messung der Unterkritikalitaet eines Kernreaktors 
  GB0827436 1960-02       
  GB0975742 1964-11       
  GB1047152 1966-11       
Buy PDF GB1498372 1978-01  G21C 17/00 ROCKWELL INTERNATIONAL CORP METHOD AND APPARATUS FOR AUTOMATIC ABNORMAL EVENTS MONITOR IN OPERATING PLANTS 
Buy PDF GB1534148 1978-11  G06G 7/00 COMMISSARIAT ENERGIE ATOMIQUE CONTROL OF PROTECTION SYSTEMS 
Buy PDF GB1577823 1980-10  F02B 3/00 ALNOR INSTRUMENT CO DIESEL ENGINE EXHAUST TEMPERATURE MONITOR 
Buy PDF- 11pp GB2050022 1980-12  G01S 15/00 MOSER M INTRUDER ALARM 
Buy PDF- 6pp GB2020042 1982-09  G01D 1/00 ANGLO AMERICAN CORP OF SOUTH AFRICA LTD MONITORING RATE OF CHANGE OF AN ELECTRICAL SIGNAL 
Buy PDF- 4pp GB2074721 1983-09  G08B 17/10 FURNACE CONSTRUCTION CO LTD SMOKE SENSOR APPARATUS 


Other Abstract Info: CHEMABS 100(18)147228X

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