Talk:Small modular reactor

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This page was a fairly short-term project. While many sources are available on Small Modular Reactors, many of them are outdated or obviously biased. There are new sources emerging all the time, but most of them are from small conferences and think-tanks, and not accessible for others to reference. I would appreciate any help that anyone can give to help increase the number of viable sources and information for this page. Help? BJMcNall (talk) 21:07, 7 July 2010 (UTC)[reply]

Remove Operation section

The entire "Operation" section seems unnecessary. It is a long section and basically describes the operation of various types of nuclear reactors, with no real information specific to small modular reactors. This kind of section would be appropriate for the Nuclear Reactor Technology article or the Nuclear Reactor Physics article. I believe that as it is, it does not add anything to the article as a whole. —Megiddo1013 18:03, 27 November 2010 (UTC)[reply]

This section would be better served by just having a link to the more general article on Nuclear reactors and their types.

I.E. - Jderek6208 (talk) 10:26, 19 August 2017 (UTC)An SMR is a scaled down version of Larger scale First and second generation power plants described in; https://en.wikipedia.org/wiki/Nuclear_power_plant. The heart of any Nuclear power station is it's nuclear island or Nuclear steam supply system (NSSS) See also; https://en.wikipedia.org/wiki/Nuclear_reactor. Reactor system safety is a factor of redundant reactor control rods systems typified by a set of primary reactor shutdown rods in the center of the core and a secondary set of reactor control rods. This control rods use delayed neutron fractions of the entire neutron population to limit the overall power of the core through out reactor life. For a more detailed explanation see; https://en.wikipedia.org/wiki/Nuclear_reactor_physics. And, https://energy.gov/sites/prod/files/2013/06/f2/h1019v2.pdfCite error: There are <ref> tags on this page without content in them (see the help page).[reply]

Disadvantages and limitations of SMRs

This page as a whole reads like a funding request. Not being a nuclear scientist, there must be some information on limitations to this technology. No energy source is so clear of constraints. Geodaktari (talk) 17:05, 14 December 2013 (UTC)[reply]

Agreed, see "too promotional" section below... Johnfos (talk) 02:06, 3 January 2016 (UTC)[reply]

I agree that it's too one sided, so I've added a dedicated disadvantages/issues section, and added content - including with citation from widely-respected media source BBC News. Simonjon (talk) 11:31, 3 April 2016 (UTC)[reply]

As a former researcher I can certainly tell the bias of the previous detractors. I worked for fifteen years at the former Fast Flux Test Facility at Hanford, Washington USA. Which in reality was EBR number three. We derated FFTF from 400 MW thermal to 295 MW thermal to continue conducting limited research. Long story short in history section there is no mention of this facility or the Subsequently cancelled Porwer Reactor Inherently Safe Modular (PRISM) design by General Electric. Why, because politically Neither US DOE nor US NRC wanted to license and SMR. Heres the truth if you can Handle it.;

The FFTF while designed as a LMFBR was never allowed to be operated as a breeder reactor. It was successfully licensed and operated as a research reactor for over a decade. The operating crews received multiple awards and commendations for safe operation of the facility. When de-rated from 400 MWt to 295 MWt did not require it's Gas Expansion modules to be operated as an inherently safer reactor. As scram from 295 MWt resulted in an easy transformation from forced cooling to natural circulation cooling mode. In fact the disadvantage was that the liquid sodium required external electric resistance heating to keep from freezing solid. The general problem with all liquid metal or molten salt reactor facilities.

Additional advantages;

Electrical power requirements beyond two on station batteries is not required to keep a facility initially designed with natural circulation decay removal in mind in a safe shutdown mode. Two Naval submarine PWR's S5G and S8G an be operation at power with no coolant pumps in natural circulation modes of operation. — Preceding unsigned comment added by Jderek6208 (talk • contribs) 11:04, 19 August 2017 (UTC)[reply]

Needs a summary

Italic textVery hard to find out the history of actually constructed SMEs and which of the many current designs are ready for licencing or being constructed. - Rod57 (talk) 23:52, 8 April 2015 (UTC)[reply]

Too promotional: what about disadvantages, limitations, and the skeptics?

According to Mark Cooper, the failed “nuclear renaissance” of the 2000s did not live up to its promises and this experience should provide a rationale for healthy skepticism toward claims about new nuclear reactor technology:

"This skeptical approach should apply to the new darling technology of the nuclear industry, small modular reactors. The public is hearing exactly the same promises about standardization, modularization, learning curve cost reductions, improved safety, and fast construction schedules that were made—and broken—in regard to earlier reactor designs. These are assurances that drive the industry to skip proper research and development and careful pre-commercial demonstration. The early retirements in California, Florida, and elsewhere should lead to greater caution about nuclear power safety and economics, not less." -- Mark Cooper, "Nuclear aging: Not so graceful", 18 June 2013.

I've added a "missing information" tag which should help. -- Johnfos (talk) 02:06, 3 January 2016 (UTC)[reply]

I agree that it was too one sided, so I've added a dedicated disadvantages/issues section, and added content - including with citation from widely-respected media source BBC News. Simonjon (talk) 11:31, 3 April 2016 (UTC)[reply]

Merged in content from article Micro nuclear reactor

Article merged: See old talk-page here

Licensing

Submarine reactors presumably count as "small". Would a reactor, licensed for submarine use, also be licensed for use on land or are there separate regulatory regimes for marine and land use? Roberttherambler (talk) 18:50, 12 August 2016 (UTC)[reply]

My understanding is that a submarine reactors use highly enriched uranium and their design is a secret. So they can't be used in the civilian market. However, the Russian Russian floating nuclear power station uses low enriched uranium could probably be licensed for land. Paul Studier (talk) 16:38, 13 August 2016 (UTC)[reply]

Thanks. Roberttherambler (talk) 22:18, 12 September 2016 (UTC)[reply]

This comment is extremely valid. See https://en.wikipedia.org/wiki/Category:Nuclear_propulsion

Naval Submarine reactors are not licensed in the same way as civilian power reactors. Although they get a rigorous review process, formerly a prototyping and testing phase. If licensing under the US NRC worked properly SMR's would in fact be a reality today. However, the US NRC should be more aptly entitle the US Nuclear Decommissioning Service. Since no new plants have been granted a license since 1975. The United States has lost the will to continue Nuclear Research into the the Twenty First century. And, such it is the opinion of this author no SMR or other reactor facility either can or will ever again be sited on US soil.

The USS Sam Rayburn SSBN 635 was converted from an operational submarine to the MTSD 635 https://en.wikipedia.org/wiki/USS_Sam_Rayburn_(SSBN-635) Sam Rayburn was decommissioned on 31 July 1989 and reclassified a moored training ship with hull number MTS-635.[3][4] Stricken from the Naval Vessel Register on 31 July 1989,[5] she arrived at the Naval Nuclear Prototype Training Unit at Goose Creek, South Carolina, in August 1989 after achieving initial criticality in her new role on 29 July 1989.[citation needed] Her modifications included special mooring arrangements, including Water Brake, a mechanism to absorb power generated by her main propulsion shaft.[citation needed] She is scheduled to operate as a moored training ship until 2020 while undergoing shipyard availabilities for repairs and alterations at five-year intervals.[citation needed]

Therefore, safe operation of submarine reactor designs as SMR's is not only possible but a defacto argument for their existence as viable electrical power generators. — Preceding unsigned comment added by Jderek6208 (talk • contribs) 11:34, 19 August 2017 (UTC)[reply]

History

At the end of the History section, it says "Smaller reactors would be easier to upgrade quickly, require a permanent workforce, and have better quality controls, just to name a few more advantages." Why would smaller reactors require a permanent workforce more than larger reactors do? Is this perhaps missing a "do not" before "require a permanent workforce" or perhaps "smaller" before "permanent"? —Salton Finneger (talk) 17:27, 21 June 2017 (UTC)[reply]

The history section is to small to fully address the point but here goes:

The premise of SMR's is to bridge the gaps in the two major problems with NRC licensing in the United States and presumably other nations. To operates nuclear reactor facility first and foremost the Nuclear Island/Heat Souce/Reactor Module has to be able to be built to rigid safety standards. The problem is now and the foreseeable future is that we have two many choices in designs. PWR's, BWR's, LMR's, HTGR's and molten salt reactors just to name the few on my mind. Imagine the similarity to automobiles. Diesel, Gasoline, Ethanol, Electric, Hybrid, plug-in hybrid. You get the point. No single group of people can agree on a standard automobile as safe. When there are so few physicists, and every journalist thinks they are the supreme expert on all things nuclear no one can agree on what really is the next best thing. Second there are issues with licensing any new sites. Siting by the sea, good maybe but not in the case of Fucushima, Japan. Geologically stable sites in the US. We came up with three for siting a Nuclear waste repository and even with a facility built and presumably licensing in Nevada, It will now never open. The NIMBYists kill any attempt to site any new facilities. So while SMR's are a fantastic idea. Nothing new will or can ever be built as a prototype to know if the idea is a good one or not. Hence, the best way to build test and license will continue to be Naval vessels. — Preceding unsigned comment added by Jderek6208 (talk • contribs) 11:52, 19 August 2017 (UTC)[reply]

I don't see anything in your note that addresses the question of whether "Smaller reactors . . . require a permanent workforce" is a correct statement of the advantages of a smaller reactor to a larger reactor, given that larger reactors certainly also have permanent workforces. —Salton Finneger (talk) 13:14, 21 September 2017 (UTC)[reply]