Subcritical Reactivity Monitor Utilizing Prompt Self-Powered Incore Detectors

a detector and subcritical reactivity technology, applied in nuclear elements, nuclear engineering problems, greenhouse gas reduction, etc., can solve the problems of not being sensitive enough to accurately detect low-level neutron flux emitted in the source range, and not being able to address the criticality approach in patents

Inactive Publication Date: 2017-05-18
WESTINGHOUSE ELECTRIC CORP
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Benefits of technology

[0018]This invention achieves the foregoing objectives by providing a nuclear reactor system comprising a pressure vessel housing a nuclear core and a volume of coolant within the nuclear core; a plurality of fuel assemblies are housed within the nuclear core with at least some of the fuel assemblies having one or more, primarily gamma sensitive, prompt responding self-powered neutron detectors located therein, responsive to the fission reaction activity within th...

Problems solved by technology

This support column arrangement assists in retarding guide tube deformation under accident conditions which could detrimentally affect control rod insertion capability.
Such fission and ionization chambers are capable of operation at all normal power levels, however, they are generally not sensitive enough to accurately detect low level neutron flux emitted in the source range.
However, that patent does not address the approach to criticality when a reactor approaches criticality due to withdrawal of control rods.
Currently, there is no direct method for measuring when criticality will occur from the source range ex-core detectors.
Therefore, estimating the conditions under which the plant will go critical from the ICRR curve is subject to much uncertainty, but also subject to considerable scrutiny by the Nuclear Regulatory Commi...

Method used

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  • Subcritical Reactivity Monitor Utilizing Prompt Self-Powered Incore Detectors
  • Subcritical Reactivity Monitor Utilizing Prompt Self-Powered Incore Detectors
  • Subcritical Reactivity Monitor Utilizing Prompt Self-Powered Incore Detectors

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Embodiment Construction

[0026]Commercial nuclear reactor operators are required to ensure that the reactor remains shut down by a minimum margin as defined by plant technical specifications (Tech Specs). The amount of reactor shutdown is determined via the calculated value of Keff; specifically by the amount that Keff is less than 1.0, defined as the Shutdown Margin. One current methodology for the calculation of Keff requires a number of conservative measures be included in the calculations to ensure the amount of boric acid added to the reactor coolant system bounds potential shutdown accident scenarios such as a control rod ejection, rapid reactor coolant system cool down, or unintentional dilution of the reactor coolant system boron concentration. The conservative amount of boric acid added to the reactor coolant system to ensure that Keff remains less than the limits imposed by plant Tech Spec requirements must be removed again from the reactor coolant system when it is time to restart the reactor aft...

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Abstract

A subcritical reactivity monitor that utilizes one or more primarily gamma sensitive (prompt responding) self-powered detector style radiation measurement devices located within the core of a nuclear reactor to determine the amount that the reactor multiplication factor (Keff) is below the reactivity required to achieve or maintain a self-sustaining nuclear chain reaction. This invention utilizes measured changes in the self-powered detectors' current(s) to allow a reactor operator to measure the value of Keff at essentially any desired interval while the reactor is shutdown with a Keff value less than the critical value of 1.0. This invention will enable integration of the output of the value of Keff directly into the Reactor Protection System, which will enable the elimination of the operational and core design analysis constraint costs associated with the current Boron Dilution Accident prevention methodology and enable automatic control of the Chemical Volume Control System.

Description

BACKGROUND1. Field[0001]This invention relates to conditions in a nuclear-fueled power-generating unit, and more particularly, to methods and apparatus for determining the effective neutron multiplication factor in a nuclear reactor.2. Related Art[0002]The primary side of nuclear power generating systems which are cooled with water under pressure comprises a closed circuit which is isolated and in heat exchange relationship with a secondary side for the production of useful energy. The primary side comprises the reactor vessel enclosing a core internal structure that supports a plurality of fuel assemblies containing fissile material, the primary circuit within heat exchange steam generators, the inner volume of a pressurizer, pumps and pipes for circulating pressurized water; the pipes connecting each of the steam generators and pumps to the reactor vessel independently. Each of the parts of the primary side comprising a steam generator, a pump and a system of pipes which are conne...

Claims

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Application Information

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IPC IPC(8): G21C7/22G21C7/24
CPCG21C7/22G21Y2002/501G21Y2002/50G21C7/24G21C9/02G21C17/104G21C17/108G21C19/28G21D3/001Y02E30/30
Inventor HEIBEL, MICHAEL D.
Owner WESTINGHOUSE ELECTRIC CORP
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