Nuclear reactor safety system

• US 4,290,851 A
• Filed: 01/29/1979
• Issued: 09/22/1981
• Est. Priority Date: 01/29/1979
• Status: Expired due to Term

• Current Assignee: Babcock & Wilcox Company (Babcock International Group PLC)
• Original Assignee: Babcock & Wilcox Company (Babcock International Group PLC)
• Inventors: Roberts, Robert C., Ball, Russell M.
• Primary Examiner(s): Walsh, Donald P.
• Application Number:
  US06/007,077
• Time in Patent Office: 967 Days
• Field of Search: 176/24, 176/19 EC, 176/19 R, 176/19 S, 364/504
• US Class Current: 376/217
• CPC Class Codes: G21C 7/36 Control circuits
• CPC Class Codes: G21D 3/04 Safety arrangements emergency protection of reactor G21C9/00
• CPC Class Codes: Y02E 30/00 Energy generation of nuclear origin
• CPC Class Codes: Y02E 30/30 Nuclear fission reactors

Abstract

A safety system (10) for shutting down a nuclear reactor under overload conditions is provided using a series of parallel-connected computer memory type look-up tables (14a, 14b, 14c, 14d, 14e) each of which receives data on a particular reactor parameter (P, T, φ_T, φ_B, W) and each of which has stored therein a precalculated functional value [f(P); f(T); F(φ_T); f(φ_B); f(W)] for that parameter indicative of the percentage of maximum reactor load that the parameter contributes. The various functional values [f(P); f(T); f(φ_T); f(φ_B); f(W)] corresponding to the actual measured parameters are added together to provide a control signal (S) used to shut down the reactor under overload conditions.

Claims

1. A safety system for a nuclear reactor comprising:

a series of transducers for measuring various different parameters of the nuclear reactor'"'"'s operation;

a series of parallel-connected computer-type look-up tables each individually connected to each one of the transducers, each look-up table containing a precalculated function of that parameter measured by said transducer connected to that look-up table indicative of percentage of full reactor load contributed by that parameter for a series of measured parameter values and outputing said precalculated function in response to the parameter signal measured by said transducer connected thereto;

a summing station for receiving all of the outputs of the respective computing stations and summing them up to establish a control signal indicative of percentage of allowable full power reactor operation.

2. A safety system as set forth in claim 1 including a comparing station for comparing the control signal from said summing station with a power signal to establish an alarm signal whenever said power signal exceeds said control signal.

3. A safety system as set forth in claim 2 including a series of analog-to-digital converters mounted between each transducer and its respective computer-type look-up tables for converting the analog signal of each transducer to a digital signal for the computer-type look-up tables.

4. A safety system as set forth in claim 1 wherein the analog parameter signals from a pair of transducers are applied as inputs to one analog-to-digital converter to provide a digital output signal therefrom which is a ratio of the two parameters.

5. A safety system as set forth in claim 4 wherein the pair of parameters are φ

_T and φ

_B and their ratio is used to determine the offset of a nuclear reactor.

6. A safety system as set forth in claim 3 including a series of digital-to-analog converters individually mounted between said summing station and each of said computing stations to convert the digital output signal of said computing stations to an analog signal for the summing station.

7. A safety system as set forth in claim 6 wherein each of the computer-type look-up tables has a digital parameter value stored therein and a corresponding precalculated functional value for each stored parameter value representative of the percentage of full power contribution of the respective parameter.

8. A safety system as set forth in claim 7 wherein the parameters of the nuclear reactor sensed by respective transducers include reactor pressure, temperature, cooling fluid flow, neutron flux, escaping from the upper portion of the reactor and neutron flux escaping from the lower portion of the reactor.

9. A safety system as set forth in claim 6 wherein one of said digital-to-analog converters has a digital data word representing a parameter function as one input and an analog parameter function as the second input to provide an analog output which is the product of the two parameter functions.