Method for monitoring a nuclear core comprising a relaxation of a threshold, and associated programme, support and nuclear reactor

Patent metadata

Field	Value
Publication number	US-12347579-B2
Application number	US-201816634365-A
Country	US
Kind code	B2
Filing date	Jul 30, 2018
Priority date	Jul 28, 2017
Publication date	Jul 1, 2025
Grant date	Jul 1, 2025

Abstract

A method is for monitoring a nuclear reactor comprising a core in which fuel assemblies are loaded, each assembly comprising nuclear fuel rods each including nuclear fuel pellets and a cladding surrounding the pellets. The method includes determining ( 100 ) at least one operating time limit (T FPPI ) for the extended reduced power operation of the reduced power nuclear reactor, so as to avoid a rupture of at least one of the claddings, operating ( 102 ) the nuclear reactor at reduced power for an actual time strictly less than the time limit (T FPPI ), and relaxing ( 104 ) at least one threshold for protecting the nuclear power plant as a function of a difference between the time limit (T FPPI ) and the actual time.

First claim

The invention claimed is:

1. A method for monitoring a nuclear reactor comprising a core in which fuel assemblies are loaded, each fuel assembly comprising nuclear fuel rods each including nuclear fuel pellets and a cladding surrounding the nuclear fuel pellets, the method comprising the following steps:
determining at least one operating time limit for an operation at a reduced power of the nuclear reactor, so as to avoid a rupture of at least one of the claddings, the reduced power being inferior or equal to 92% of a nominal power of the nuclear reactor;
operating the nuclear reactor at the reduced power for an actual time strictly less than the operating time limit;
measuring and/or calculating a distribution of a linear power at any point of the core as a function of time;
relaxing a threshold linear power of the nuclear reactor as a function of a difference between the operating time limit and the actual time, the threshold linear power being a threshold of the linear power at any point of the core below which a rupture by Pellet/Cladding Interaction is avoided; and
further operating the nuclear reactor at the reduced power according to the threshold linear power from the relaxing step.

2. The monitoring method according to claim 1 , wherein the relaxing of the threshold linear power of the nuclear reactor as a function of the difference between the operating time limit and the actual time is performed based on a relaxation relationship between the threshold linear power and the difference between the operating time limit and the actual time, the method further comprising determining the relaxation relationship before the operating of the nuclear reactor at the reduced power.

3. The monitoring method according to claim 1 , further comprising the following steps before the determining of the operating time limit:
calculating the threshold linear power; and
calculating a linear power at 100%, the linear power at 100% being an estimate of the linear power at any point of the core and as a function of time if the nuclear reactor is operating at nominal power, said linear power at 100% being calculated from the measured and/or calculated distribution of the linear power at any point of the core as a function of time,
the determining of the operating time limit being made as a function of a difference between the threshold linear power and the linear power at 100%.

4. The monitoring method according to claim 3 , wherein the threshold linear power is calculated at any point of the core and as a function of time, a power distribution of the core being such that at any point of the core, a linear power is below the threshold linear power.

5. The monitoring method according to claim 3 , further comprising the following steps before calculating the threshold linear power:
calculating a rupture linear power at any point of the core and as a function of time; and
calculating a maximum linear power variation at any point of the core caused by accidental spikes,
the threshold linear power being equal to a difference between the rupture linear power and the maximum variation induced by accidental spikes.

6. The monitoring method according to claim 5 , wherein the rupture linear power is calculated by a thermomechanical code from a thermomechanical state of the core, the thermomechanical state of the core being known by the measurement and/or the calculation of the distribution of the power at any point of the core as a function of time.

7. The monitoring method according to claim 6 , wherein the calculation of the rupture linear power is done at least once every two hours, the threshold linear power then also being recalculated.

8. The monitoring method according to claim 1 , further comprising returning the nuclear reactor to nominal power; and
recalculating the operating time limit in real time and continuously, including increasing the operating time limit upon the returning of the nuclear reactor to nominal power.

9. The monitoring method according to claim 1 , wherein the measuring and/or calculating the distribution of the linear power at any point of the core as a function of time includes estimating a maximum linear power in real time and continuously.

10. The monitoring method according to claim 1 , wherein the threshold linear power from the relaxing step depends on an axial power imbalance, the axial power imbalance being a power difference between a bottom and a top of the core.

11. A computer program on a non-transitory computer readable medium comprising instructions for executing steps of the method according to claim 1 .

12. The non-transitory computer readable medium usable in a computer and on which the program according to claim 11 is recorded.

13. A method for monitoring a nuclear reactor comprising a core in which fuel assemblies are loaded, each fuel assembly comprising nuclear fuel rods each including nuclear fuel pellets and a cladding surrounding the nuclear fuel pellets, the method comprising the following steps:
determining at least one operating time limit for an operation at a reduced power of the nuclear reactor, so as to avoid a rupture of at least one of the claddings, the reduced power being inferior or equal to 92% of a nominal power of the nuclear reactor;
operating the nuclear reactor at the reduced power for an actual time strictly less than the operating time limit;
measuring and/or calculating a distribution of a linear power at any point of the core as a function of time and determining from the distribution of the linear power a thermomechanical state between the cladding and the nuclear fuel pellets;
recalculating the operating time limit in real time as a function of the thermomechanical state between the cladding and the nuclear fuel pellets;
relaxing a threshold linear power of the nuclear reactor as a function of a difference between the operating time limit and the actual time, the threshold linear power being a threshold of the linear power at any point of the core below which a rupture by Pellet/Cladding Interaction is avoided even in case of a power spike or a transition to operation at nominal power; and
further operating the nuclear reactor at the reduced power according to the threshold linear power from the relaxing step.

14. The monitoring method according to claim 13 , wherein the recalculating the operating time limit in real time as a function of the thermomechanical state between the cladding and the nuclear fuel pellets includes:
calculating a rupture linear power of the cladding of the nuclear fuel rods at any point of the core and as a function of the thermomechanical state between the cladding and the nuclear fuel pellets.

15. The monitoring method according to claim 14 , wherein the recalculating the operating time limit in real time as a function of the thermomechanical state between the cladding and the nuclear fuel pellets further includes:
calculating the threshold linear power as a function of the rupture linear power and a maximum linear power variation induced by accidental spikes at any point of the core.

16. The monitoring method according to claim 15 , wherein the recalculating the operating time limit in real time as a function of the thermomechanical state between the cladding and the nuclear fuel pellets further includes:
calculating a linear power at 100%, the linear power at 100% being an estimate of the linear power at any point of the core and as a function of time if the nuclear reactor is operating at the nominal power,
the recalculating of the operating time limit being performed as a function of a differ

Assignees

• Framatome Sa

Inventors

• Royere Christian
• Lasne Christophe

Classifications

• G21C7/36

  Control circuits · CPC title

• G21C7/00

  Control of nuclear reaction · CPC title

• G21C3/047

  Pellet-clad interaction · CPC title

• G21C3/06

  Casings; Jackets · CPC title

• G21C17/10

  Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain · CPC title