Steam generator for a nuclear reactor
US-10147507-B2 · Dec 4, 2018 · US
US9728281B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-9728281-B2 |
| Application number | US-201313766693-A |
| Country | US |
| Kind code | B2 |
| Filing date | Feb 13, 2013 |
| Priority date | Apr 17, 2012 |
| Publication date | Aug 8, 2017 |
| Grant date | Aug 8, 2017 |
A practical reading order for non-experts. Skip the full description unless you need deep technical detail.
What the patent document calls the invention.
A short plain-language summary of the technical disclosure.
Who owns or filed the patent and who is credited as inventor.
Filing, priority, publication, and grant dates set the timeline.
The legal scope of protection — read this for what is actually claimed.
Technology tags used to group this patent with similar filings.
Prior art links and similar publications in this corpus.
Official abstract text for this publication.
A nuclear reactor includes an internal steam generator and a nuclear core disposed in a containment structure. A condenser is disposed outside the containment structure, and includes a condenser inlet line tapping off a steam line connected to the steam generator outside the containment structure, and a condensate injection line conveying condensate from the condenser to the integral steam generator. Isolation valves are located outside the containment structure on a feedwater line, the steam line, and the condensate injection line. The valves have an operating configuration in which the isolation valves on the feedwater and steam lines are open and the isolation valve on the condensate injection line is closed, and a heat removal configuration in which the isolation valves on the feedwater and steam lines are closed and the isolation valve on the condensate injection line is open.
Opening claim text (preview).
What is claimed is: 1. A system comprising: a nuclear reactor disposed in a containment structure, the nuclear reactor including an internal steam generator and a nuclear core immersed in primary coolant water, the nuclear core comprising fissile material; a steam line connected to an outlet of the steam generator and passing through the containment structure to convey steam from the internal steam generator; a feedwater line connected to a first inlet of the steam generator and passing through the containment structure to convey feedwater into the internal steam generator; a condenser disposed outside the containment structure; a condenser inlet line tapping off the steam line at a point outside the containment structure and feeding into an inlet of the condenser; and a condensate injection line conveying condensate from an outlet of the condenser into a second inlet of the steam generator, wherein the first inlet of the steam generator is independent of the second inlet of the steam generator. 2. The system of claim 1 further comprising a valve on the condensate injection line and isolation valves outside the containment structure on the feedwater line and on the steam line, wherein the valves have: an operating configuration in which the isolation valves on the feedwater line and on the steam line are open and the isolation valve on the condensate injection line is closed, and a heat removal configuration in which the isolation valves on the feedwater line and on the steam line are closed and the isolation valve on the condensate injection line is open. 3. The system of claim 2 , further comprising a bleed valve connecting the condensate injection line with the feedwater line, the bleed valve being open in the operating configuration to keep the condenser in a hot standby state and closed in the heat removal configuration. 4. The system of claim 2 , wherein the condenser is an air-cooled condenser. 5. The system of claim 4 , wherein the air-cooled condenser includes a fan and a speed control drive that controls fan speed in the heat removal configuration based on primary coolant temperature. 6. The system of claim 5 , wherein the speed control drive controls fan speed to turn the fan off when the primary coolant temperature is below a minimum temperature. 7. The system of claim 6 , wherein the speed control drive controls fan speed to operate at maximum fan speed when the primary coolant temperature is above a maximum temperature. 8. The system of claim 7 , wherein the maximum temperature is greater than the minimum temperature. 9. The system of claim 1 , wherein the condenser is an air-cooled condenser that is cooled by at least one fan. 10. The system of claim 7 , wherein the condensate injection line injects the condensate back to the internal steam generator at an elevated point.
responsive to faults within the plant (in the reactor G21C9/00) · CPC title
Arrangements of auxiliary equipment · CPC title
comprising powered means, e.g. pumps · CPC title
from pressure vessel; from containment vessel · CPC title
Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core (G21C1/02 - G21C1/30 take precedence) · CPC title
Related publications grouped by family.
Answers are generated from the same data shown on this page.