# US 4,382,059 A · Power change operating method of a boiling water reactor

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- Number: US 4,382,059 A
- Document ID: US4382059A
- Status: Granted
- Kind: A
- Application number: 06/154,998
- Filed: 1980-05-30
- Granted: 1983-05-03
- Earliest claimed: 1979-06-06
- Assignees: Hitachi, Ltd.
- Inventors: Kazuyori Doi; Takashi Kiguchi; Naoyuki Yamada
- Web page: https://patentgrep.com/patent/US4382059A

## CPC

- G21C 7/00: Control of nuclear reaction
- G21C 17/032: Reactor-coolant flow measuring or monitoring {(measuring volume or mass flow in general G01F)}
- G21C 17/02: Devices or arrangements for monitoring coolant or moderator
- Y02E 30/30: Nuclear fission reactors
- G21C: NUCLEAR REACTORS (fusion reactors, hybrid fission-fusion reactors G21B; nuclear explosives G21J)
- Y02E: REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION

## Abstract

A power change operating method of a boiling water reactor, in which an operation allowable range is defined by the relation between xenon and iodine concentrations, the present concentrations is compared with the allowable range, and the core flow is controlled so that the concentrations after the change can be included within the allowable range.

## Claims

### Claim 1

A method for changing thermal power of a nuclear reactor by controlling the speed of a recirculation pump of the reactor comprising the steps of:
(a) calculating the current thermal power in accordance with heat balance signals derived from the reactor and generating electrical signals of the thermal power;
(b) calculating xenon and iodine concentrations in accordance with the electrical signals of the thermal power and generating electrical signals of the xenon and iodine concentrations;
(c) calculating upper and lower limits of xenon concentration for different final power values in accordance with the relation between the thermal power and core flow in the current control rod pattern and generating electrical signals of the upper and lower limits;
(d) calculating transitional changes in the xenon and iodine concentrations after a power change for different initial values in accordance with the following equations, ##EQU2## wherein: Xe and I: Mean concentrations of Xe.sup.135 and I.sup.135 at
.SIGMA..sub.f : Means macroscopic fission cross section at core,
P: Mean thermal power at core,
.lambda..sub.X and .lambda..sub.I : Decay constants of Xe.sup.135 and I.sup.135, and
.gamma..sub.X and .gamma..sub.I : Numbers of Xe.sup.135 and I.sup.135 generated at each fission,
and generating electrical signals of the transitional changes;
(e) determining operating allowable ranges for the different initial values in accordance with the electrical signals generated in steps (c) and (d); and
(f) controlling the speed of the recirculating pump to maintain the current xenon and iodine concentrations within the operating allowable range.

### Claim 2 (depends on 1)

A method according to claim 1, wherein the reactor is a boiling water reactor and including the steps of supplying the electrical signals of the xenon and iodine concentrations to a display device, and displaying the concentrations.

### Claim 3 (depends on 2)

A method according to claim 2, further including the step of displaying the determined operating allowable ranges on the display device.

### Claim 4 (depends on 1, 2)

A method according to claim 1 or claim 2, wherein the operating allowable ranges for the different initial values are determined and stored prior to carrying out step (a).