Talk:Boiling water reactor safety systems

This article was nominated for deletion on 14 March 2011 (UTC). The result of the discussion was speedy keep.

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Deletion?

Why is this article flagged for deletion? —Preceding unsigned comment added by 195.228.35.219 (talk) 23:41, 14 March 2011 (UTC)[reply]

Why indeed? I found this article very useful as I was trying to learn a bit about BWR's in general, and Fukushima in particular. If this article would be deleted, I would hope that the majority of the information would be retained in the main BWR article. The diagram of the reactor core, showing the steam/water flow, was far more useful to me in finding an understanding of the thing than anything in the main BWR article, and I would suggest its inclusion there in any case. My only complaint (about both the main BWR article and this one) would be the use of jargon...there are places where the text is too dense for me to follow it, particularly with all the acronyms. I'd suggest trying to simplify it a bit, with the needs of the general reader (eg, encyclopedia user)in mind. All in all, a very helpful article. I hope you guys keep up the work! Cmichael (talk) 04:11, 15 March 2011 (UTC)[reply]

Introduction

Looks like an excellent article. Added the reference header than you missed. May I suggest that you add a introduction. Keep up the good work. Bjmullan (talk) 21:48, 28 February 2011 (UTC)[reply]

Looks like extremely amusing article now. —Preceding unsigned comment added by 178.37.148.163 (talk) 13:05, 13 March 2011 (UTC)[reply]

Yes; perhaps it could evolve into a description of how the safety systems at the Fukushima I Nuclear Power Plant were unable to prevent core damage following the 2011 Sendai earthquake and tsunami.— Wdfarmer (talk) 07:48, 14 March 2011 (UTC)[reply]

Whoever wrote it was sure optimistic and proven dead wrong .. —Preceding unsigned comment added by 173.230.187.166 (talk) 03:05, 16 March 2011 (UTC)[reply]

Should perhaps also mention situations that can cause hydrogen generation, and if/how the safety systems are designed to prevent and cope with this, (why they didn't work we can cover at Fukushima I Nuclear Power Plant ?) Rod57 (talk) 16:09, 14 March 2011 (UTC)[reply]

doi:10.1016/0029-5493(84)90263-2 could probably used as source for hydrogen... I only have access to the abstract, though (WP:REX?). 88.148.249.186 (talk) 18:13, 14 March 2011 (UTC)[reply]

Uh wow, I came here after the Japanese reactor thing, and while I'm pretty pro-nuclear, I had to lol at this classic statement:

"Because of this effect in BWRs, operating components and safety systems are designed to ensure that no credible scenario can cause a pressure and power increase that exceeds the systems' capability to quickly shutdown the reactor before damage to the fuel or to components containing the reactor coolant can occur."

Diesel generators getting wet wasn't credible? When your shit is right next to the ocean and has been hit with multiple tsunamis? I bet your fucking flood insurance company considers that situation pretty credible. How do you fuck up a single point of failure in backup power that badly?

And who the fuck puts spent fuel rods together so closely they're a subcritical fissionable mass? Might as well just dump some deuterium in that bitch and have another reactor.

I don't know whether to laugh or cry reading the rest of this shit. No wonder it's marked for deletion. Srsly.

Additional questions

Good article, lots of rare Information. I really needed to know this! But I have some further questions, mostly about the rest of the water loops of the varous systems. At the moment my questions are regarding to the old desings, not ESBWR or ADWR:

Where is the Main Steam Isulation Valve? Is it at the point where the steampipe passes through the RPV or the Containment? I think, the MSIV is closed at the beginning of a SCRAM to really seal the Containment?

If I understand correctly, the needed power for the RCIC comes directly from the reactor. Like in the graphic there must be a small steam turbine. To make this work, there has to be a heatexchanger after the turbine where the steam is condensed. Can you say something about that? Where goes this heat? If the system should work permantently this heat must be transportet out of the reactor building. How? This would be a lot of heat if the reactor should be cooled only by RCIC in a controled fast shutdown...

From where comes the fresh water for the RCIC? I assume to some fraction it is the condensed steam from the RCIC-Turbine. If RCIC is a closed cycle theare as to be a large heatexcanger/condensor. How exactly does this part of the system look like?

Te Torus/Suppression Pools are only a heat buffer. First, this buffer works quite well, but it gets hotter and after some time water in the Torus starts to boil. Te buffer is saturated. So if HPCS and LPCS should work for a longer period of time there must be a system to really remove heat from the reactor. How? Is there some kind of heatexchanger to coll the water after it is taken from the Torus an before it is injected into the RPV? (More or less same question as for the RCIC)

In the graphic are mostly shown ways to get water into the RPV but the main idea ist to get heat aut of it and so all water injected to the core also has to leave it after a while. How does that happen? Only by the RCIC and the ADS? So if the HPCS is activated, also the ADS activates, because it is not possible only to add water to the RPV?

Well, this are a lot of questions but you have already given so much detailed information about his complicated topic that I am confident you can answer them! Best regards an much thanks! Schmidti --129.206.196.61 (talk) 19:10, 14 March 2011 (UTC)[reply]