Induced nuclear reactions: processes – systems – and elements – With control of reactor – By electronic signal processing circuitry
Patent
1989-06-26
1992-02-25
Walsh, Donald P.
Induced nuclear reactions: processes, systems, and elements
With control of reactor
By electronic signal processing circuitry
376217, 376236, G21C 1700
Patent
active
050911392
ABSTRACT:
A computed model of reactor power output distribution in space is read periodically to microprocessor based computer memory and retained in memory in a three dimensional matrix. This retention occurs between regular updates on the order of every two minutes. The reactor is conventionally monitored in groups of 16 fuel bundles each. Each 16 bundle group is monitored as to its thermal neutron flux by four vertical strings of local power range monitors, each string having one of four power monitors disposed at four different elevations extending the height of the active core. Each bundle group is controlled by four control rods and is assumed to be subject to uniform flow change with overall reactor flow change. The automated thermal limit monitor (ATLM) takes as inputs all power range monitor information from the BWR reactor core on a continuous basis to two channels one channel for determining operating limits the other channel for determining safety limits. These signals are processed inside the system according to different algorithm requirements for the protection of fuel thermal limits, i.e., minimum critical power ratio (MCPR) and maximum linear heat generation rate (MLHGR). The system also takes as input the on-line absolute core thermal parameters limits, together with a set of built-in parameters called A and B factors which are functions of core power, and control rod position, and the operating thermal limit data at the current power and flow conditions. Based on the above information, the system calculates signal setpoint values for MCPR and MLHGR, respectively. These setpoint values are compared with the instantaneously scanned ATLM signals continuously to determine whether a control rod withdrawal block command or core flow block command should be issued. If an instantaneously scanned and processed ATLM signal value approaches its setpoint, then rod block (or flow block) will be issued. This then assures that the core thermal limits are not violated on rod withdrawal or flow changes. This invention disclosure not only describes the system configuration and functional logic of rod block and flow block, it also describes the design bases of the A and B factors in the system algorithm which are fundamental to the whole ATLM system. The configuration concept, functional logic, and the form and design of the A and B factors constitute the bulk of the ATLM design invention disclosure.
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Country USA-In-Core Neutron Monitoring System for General Electric Boiling Water Reactors/4/69.
Chao Fred C.
Rowe William S.
General Electric Company
Schroeder Robert R.
Walsh Donald P.
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