Dry stand-by liquid control system for a nuclear reactor

Patent metadata

Field	Value
Publication number	US-11200992-B2
Application number	US-201916729968-A
Country	US
Kind code	B2
Filing date	Dec 30, 2019
Priority date	Dec 30, 2019
Publication date	Dec 14, 2021
Grant date	Dec 14, 2021

Abstract

A boiling water reactor system includes a reactor vessel including a reactor core. A steam line is in communication with the reactor core and a turbine that is connected to an electrical generator. A dry standby liquid control system includes a standby vessel containing dry powder containing boron and including a high pressure water supply in communication with the standby vessel via a first closed valve, wherein the standby vessel is in communication with the reactor vessel via a second closed valve.

First claim

What is claimed is:

1. A dry standby liquid control system for a nuclear reactor, comprising:
a standby vessel including dry powder, the dry powder including boron;
a high pressure water supply in communication with the standby vessel via a first closed valve, the standby vessel being in communication with a reactor vessel via a second closed valve, the high pressure water supply being connected to an interior pipe system having a plurality of mixing holes within the standby vessel.

2. The dry standby liquid control system for a nuclear reactor according to claim 1 , wherein the high pressure water supply includes a heater.

3. The dry standby liquid control system for a nuclear reactor according to claim 1 , wherein the second closed valve is disposed in a bottom of the standby vessel in communication with a mixer eductor disposed on an outboard side of the second closed valve and in communication with the reactor vessel.

4. The dry standby liquid control system for a nuclear reactor according to claim 1 , wherein the dry powder containing boron includes dry sodium pentaborate.

5. The dry standby liquid control system for a nuclear reactor according to claim 1 , wherein the interior pipe system includes at least one pipe extending along an interior sidewall of the standby vessel.

6. The dry standby liquid control system for a nuclear reactor according to claim 5 , wherein the interior pipe system further includes a portion extending along an upper region of the vessel.

7. The dry standby liquid control system for a nuclear reactor according to claim 5 , wherein the plurality of water mixing holes are arranged in the at least one pipe to induce a swirl within the standby vessel.

8. The dry standby liquid control system for a nuclear reactor according to claim 7 , wherein the plurality of water mixing holes include a first plurality of water mixing holes directed generally tangential to the interior sidewall of the standby vessel and a second plurality of water mixing holes directed toward a center of the standby vessel.

9. A boiling water reactor system, comprising:
a reactor vessel including a reactor core;
a steam line in communication with the reactor core and a turbine that is connected to an electrical generator;
a standby vessel including dry powder, the dry powder including boron and including a high pressure water supply in communication with the standby vessel via a first closed valve, the standby vessel being in communication with the reactor vessel via a second closed valve, wherein the high pressure water supply being connected to an interior pipe system having a plurality of mixing holes disposed within the standby vessel.

10. The boiling water reactor system according to claim 9 , wherein the second closed valve is disposed in a bottom of the standby vessel in communication with a mixer eductor disposed on an outboard side of the second closed valve and in communication with the reactor vessel.

11. The boiling water reactor system according to claim 9 , wherein the dry powder containing boron includes dry sodium pentaborate.

12. The boiling water reactor system according to claim 9 , wherein the interior pipe system includes at least one pipe extending along an interior sidewall of the standby vessel.

13. The boiling water reactor system according to claim 12 , wherein the interior pipe system further includes a portion extending along an upper region of the vessel.

14. The boiling water reactor system according to claim 12 , wherein the plurality of water mixing holes are arranged in the at least one pipe to induce a swirl within the standby vessel.

15. The boiling water reactor system according to claim 14 , wherein the plurality of water mixing holes include a first plurality of water mixing holes directed generally tangential to the interior sidewall of the standby vessel and a second plurality of water mixing holes directed toward a center of the standby vessel.

Assignees

• Ge Hitachi Nuclear Energy Americas Llc

Inventors

• Anthony Gary M

Classifications

• G21D3/04

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

• G21C7/22

  by displacement of a fluid or fluent neutron-absorbing material {, e.g. by adding neutron-absorbing material to the coolant} · CPC title

• G21C9/033 Primary

  by an absorbent fluid · CPC title

• G21C13/02

  Details · CPC title

• G21C9/02

  Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; {Control elements having arrangements activated in an emergency}(control elements per se G21C7/00) · CPC title