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I thought that EBR-I experienced the first [partial] meltdown, in 1955. That's what the Wiki entry says, and that's what I was told when I visited the EBR-I site.

The first recorded nuclear meltdown in the United States occurred at the EBR-1 reactor on 29 November 1955. I have modified the Power Generation text accordingly. BluegillTriplePrime (talk) 02:12, 1 May 2009 (UTC)[reply]

An excellent source is Smarter Use of Nuclear Waste, http://www.scientificamerican.com/article.cfm?id=smarter-use-of-nuclear-waste. —Preceding unsigned comment added by 12.156.194.3 (talk) 22:20, 28 August 2009 (UTC)[reply]
The submarine stuff should be scrubbed, has no references. I can't cite my source, has USN ties.

Shjacks45 (talk) 13:49, 31 October 2009 (UTC)[reply]

Probably good saved content: Lithium

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This content is probably worth to be added: but minimum needs a lot rewriting and shortening. Opinions? 217.233.176.164 (talk) 06:05, 24 December 2015 (UTC)[reply]

7-Lithium

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Also nether used already 7Li is an excellent coolant and excellent secure moderator allowing also full thorium fuel cycle with more than 2-3 times heat capacity than water and moderation better than rare beryllium[1] with very less neutron absorption(45 millibarns)[2](after capturing just decay to 4He over 8Be means not going itself radioactive). Lithium is melting 180°C boiling 1340°C means a huge usable temperature difference without pressure with about 3/4 (NaK77 1/4) specific heat capacity/kg than water and high possible temperatures without pressure (-loss and decreased overpressure risk) for efficient and compact turbines, secure high critical point (thermodynamic) 2950°C(causing also decreased specific heat capacity problem with water >374°C), strong negative VOID on bubbles security with less cooling loss, low density about 0.5g/ccm (hot), no expansion on solidification like rare bismuth (eutecticum), el. magn. pumpable over paramagnetism of Li, strong thermal expansion for thermal flow, chemical binding of tritium, iodine, bromine etc., most less reactive earth alkali metal, not spreading radioactivity like water (steam) and graphite smoke, price just about 5 mio. $ for 100 000l, 28 mio. t world reserve for Li with 92.5% 7Li inside etc. combinable with also suggested new extreme compact and secure (Full Zero Risk all possible cases at lowest price for GWe and kWh) pebbles pillar design from Kay Uwe Böhm with a long high tungsten reflector core tube (for example 3m diameter 18m high) for high thermal flow up and down around with some isolation concrete through cBN boron nitride(thermal conductivity extreme high 740W/(m*K) and there wanted neutron absorption) heat exchange tubes with normal lithium around flowing upwards and again around downwards then to turbines and back with fuel pebbles (out of SiC or moderating c11B15N melting 2973°C etc.) inside 7Li that can be taken in and out continiously also for regulation and trimming with near no neutron absorbers, controlled and stopped with different size absorber control and stopp pebbles and maybe turnable all around from top to bottom control and stopp rods with tungsten reflector and absorber side and addable independant and secure working stoppsand core catcher system. Possible catcher materials are broad band neutron absorbing hafnium carbide melting 3890°C at spread dome directly under core, thin cubic boron nitride plates melting 2973°C upon thick cheap magnesium oxide melting 2852°C. If the reactor core is opend all should come out quickly and quickly spreaded over a cover holded by (also active electric meltable) clamps then a mass of sand (SiO2 melting 1715°C boiling 2200°C) maybe with additional neutron absorber placed upon is keeping better cool than water with much boiling bubbles and takes decay heat itself never melting all if enough, not rising much pressure, spread risk and keeping near all down under with still closed quick spreadable high melting point pebbles. Around heat exchange (W/Mo) steel with ribs low melting concrete with additives like in glass production working for stabilization, isolation but in overheat situation as melting buffer and then again steel with ribs all shaped round and black for better radiation. The two different pebble sizes can be taken in and out by sieves at run time. El. magn. wandering field pumping of lithium can be done with not melting tungsten spooling and wiring through cBN etc. Preheating can be done also with cBN for electric isolation heating up a high melting material with enough electric resistance through tungsten etc. cBN has a strong one time expansion after backing usable also for fixing inside other materials tubes. Possibble is likely also direct fuel and extraction using continiously taking out fission products centrifuges etc. against leight weight lithium and replacement of nuclear fuel (ThC-PaC-233UC or ThO2-PaO2-233UO2) normally more heavy than all (lithium bound or density decreased alloyed) fission products maybe using a separation medium like red lead and maybe additional separation over fluoridization and/or fine seperating melting centrifuge watching outflow for colour, reflection, radioactivity kind and intensity etc. keeping the radioactive inventory always extreme low in all accidents cases (likely <0.2% compared with Fukushima 2% Chernobyl 20% set free), decreased decay heat problem, extraction also of reactor poisons like usable samarium etc. at run time like normally xenon or of breeded 233U surplus and continiously controlled nuclear fueling instead trimming with neutron wasting absorbers.

References

  1. ^ http://www.nndc.bnl.gov/sigma/getPlot.jsp?evalid=14968&mf=3&mt=102&nsub=10
  2. ^ http://www.nndc.bnl.gov/sigma/getPlot.jsp?evalid=14966&mf=3&mt=102&nsub=10
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Lithium-7 moderator & coolant

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Lithium-7 cooled an moderated for example Na-breeder design or Future CANDU HTR with ND3 (N-15) liquid about bar between tubes like D2O but quckly away into another tank if lithium-7 to hot used inside tubes out of RBN Reactor Boron Nitride isotopes B-11 like C-12 and N-15 with lowest neutron absorption of all usable isotopes used also for nuclear fuel just UO2 etc. baked iside BN to RBN same cBN that way starting with unenriched uranium but always breeding enough for about 30 years runtime then used for end storage inside stainless steel for example 30m deep in desert. cBN is well known super material if hot usable for heat exchange Li-7 to Li or CO2 but not usable in neutron area with isotopes B-10 or N-14 (n,p) C-14. Li-7 excellent moderstor and coolant with bubble slow down about 180-1340°C boiling point preheated. Li-7 and RBN not staying radioactive. Li-7 least reactive earth alkali metal in air LiN passivation layer RBN hard up to 2800°C, unburnable, insoluble enclosing like SiC but possible used thick adding moderation also in water moderated reactor and sand SiO2 is an emergenvy coolant taking decay heat etc. 195.63.193.148 (talk) 15:23, 26 February 2024 (UTC)[reply]

Power conversion

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There is practically nothing here about how energy conversion takes place in LMRs -- how the heat generated by the nuclear reactions is harnessed to drive turbines and electrical generators. There *is* a section near the end titled "Power generation" but, strangely, all this section does is list various existing or past facilities. Could I induce an expert to add a section (better still, to revise and expand the existing section) describing how the heat contained in the liquid metal coolant is used to generate useful power? Thanks!!! LyleHoward (talk) 16:59, 13 June 2024 (UTC)[reply]

The same way that all thermal power plants produce electricity; a steam turbine. This would be the secondary or more likely tertiary cooling loop. ---Avatar317(talk) 00:25, 18 June 2024 (UTC)[reply]
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