Methods for protection of nuclear reactors from thermal hydraulic/neutronic core instability

Patent metadata

Field	Value
Publication number	US-11837372-B2
Application number	US-202017134983-A
Country	US
Kind code	B2
Filing date	Dec 28, 2020
Priority date	Mar 16, 2012
Publication date	Dec 5, 2023
Grant date	Dec 5, 2023

Abstract

The invention relates to methods for protecting a nuclear reactor core, such as a boiling water reactor core, from fuel and cladding damage due to thermal hydraulic instability in extended operating power flow conditions and, in particular, when an extended power uprate is implemented. The methods employ existing licensed stability methodologies and incorporated minor changes, e.g., to the Average Power Range Monitor (APRM)-based trip system to preclude operation inside the stability vulnerable region of the power/flow map. The APRM-based trip system is modified to set down the APRM flow-biased scram line when core flow is less than a predetermined core flow to prevent the core from entering an unstable region of operation.

First claim

What is claimed:

1. A method for protecting a nuclear reactor core from fuel damage due to thermal hydraulic instability in an extended operating domain for an extended power uprate, comprising:
generating a power-flow operating map, comprising:
establishing a natural circulation curve;
establishing a Maximum Extended Load Line Limit Analysis (MELLLA) control rod line; and
establishing a higher MELLLA+ control rod line positioned above the MELLLA control rod line;
forming a MELLLA+ domain above the MELLLA control rod line, up to the higher MELLLA+ control rod line;
identifying a predetermined core flow rate;
calculating by a thermal hydraulic code simulator a thermal hydraulic stability limit for core flow rates less than or equal to the predetermined core flow rate;
determining a power level that corresponds to the thermal hydraulic stability limit at different core flow rates that are less than or equal to the predetermined core flow rate;
providing an Average Power Range Monitor (APRM) flow-biased scram line;
lowering the APRM flow-biased scram line to below the thermal hydraulic stability limit based on the core flow rate being less than or equal to the predetermined core flow rate; and

when operating in the MELLLA+ domain, actuating an APRM-based trip system based on a core flow decrease resulting from a flow decrease transient and power increases above the power level to provide an automatic anticipatory scram or a selected rod insertion trip to cause a power reduction.

2. The method of claim 1 , wherein the predetermined core flow rate is 55% of rated core flow.

3. The method of claim 1 , wherein lowering the APRM flow-biased scram line to below the thermal hydraulic stability limit comprises positioning the APRM flow-biased scram line below and lateral to the thermal hydraulic stability limit.

4. The method of claim 1 , wherein the method further comprises employing Oscillation Power Range Monitor (OPRM) instruments for detecting power oscillations and thermal hydraulic instability, wherein upon exceeding an OPRM setpoint a scram signal is generated.

Assignees

• Westinghouse Electric Co Llc

Inventors

• Blaisdell John A
• Chu Edward M
• Rotander Camilla S
• Kumar Gurikar V

Classifications

• G21D3/001 Primary

  Computer implemented control · CPC title

• G21C17/112

  Measuring temperature · CPC title

• G21D3/04

  Safety arrangements (emergency protection of reactor G21C9/00) · CPC title

• G21D3/005

  Thermo-hydraulic simulations · CPC title

• Y02E30/30

  Nuclear fission reactors · CPC title