Talk:OPR-1000: Difference between revisions

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== Improved core catching for EPR etc. ==

Improved core catching for EPR etc.

RBN fuel pebbles inside chromium tube melting about 1900*C then with still closed RBN pebles out rolling down the ramp to 170m² spreading area both with ZrB2 instead ZrO2 or sacrifice concrete then mich sand coolant for RBN
upon that. RBN is cubic boron nitride isotopes B-11 & N-15.

All pressurized water reactors with D2O in the primary circuit and RBN probably start up without enrichment like CANDU and thus breed enough for around 30 years of RBN fuel rod life and safe strong D2O bubble waste.

Lead bismuth eutectic boiling point 1670 °C is definitely 3 times the reactor overtemperature at Thor approx. 2700 °C then MgO melts but not ZrC UO2 inclusion and tungsten at white heat stable heat without He/Li cooling radiating into melted concrete like the filament in a light bulb .

Pb then captures very few neutrons at a very slow boiling point. Bi captures fast neutrons E^1 when very slow E^0 is definitely reducible. Very slow neutrons also capture U-238 more gradually than U-235 total fission but long fast neutrons make U-238 metastable for capture.

Concrete's melting point can be significantly reduced, even with expensive additions or with iron 1550°C? etc. as a buffer on the outside in a Mo double steel wall on the inside SiC cladding and RBN with keiviite (Yb) control rods.
Material must also withstand high expansion of Pb Bi upon solidification.

Thor 1 GWth globular cluster about the same size as EPR Core with 4.5 GWth but then compact on the outside with tungsten reflector helium downward channel behind then 1.6m steel concrete W double steel wall with Li separated on the inside to turbine more stable than EPR 2.6m concrete and steel on the inside Much smaller round dome houses large WW II 1000kg TNT bomb and A380.
Steel-tight welded inside and outside in argon with diving equipment. Lithium to He cooling surface customizable

Cr-52 better than Fe-56 for EPR fuel cladding or Zirkalloy Zr for CANDU not rusting and less H2 for core meltdown etc

CO2 turbine circuit also subsequently with H2O from condenser cooling and turbine surface heat
Can be operated at the rear with FK compressor CO2 return cooling th. fully insulated
Efficiency at 100 instead of 37%.

Future CANDU HTR is best started with natural uranium without enrichment 30 years RBN UO2 fuel life, also highly safe with ND3 (N-15) unheated, between RBN tubes with Li-7, pressure drop also quasi passive when Li-7 over approx. 1000°C ND3 valve to normal with pressure bubble control and Li-7 bubble drop 180 - 1340°C without pressure plus if necessary 1 floor SiO2 sand emergency coolant for RBN down below cheaper MgO.
Small or simply large with more parallel tubes
With control rods also in 2s from RBMK approx. 16s from below Cooling pipe length high at the time of the accident still wrong with positive VOID boiling bubble coefficient after roller coaster test ride until Rōhten burst and ceiling was gone then graphite smoke fire main spread.

No tungsten necessary with Future CANDU HTR and less RBN required than with Thor globular cluster HTR. ND3 & Li-7 coolant instead of H2O is also used optimally
Final costs are the lowest and can be built up quickly.

D-D in electrolysis etc. Hydrogen separated from H-H in gas centrifuge H-D with Li-7 LD + LH in melting centrifuge- separated hot decomposed.
Separated with H-H without D N-15 in ammonia.
B-11 is waste separated from B-10 enrichment in BF3 gas centrifuge cheaper in BH3/B2H6 borane production.
A good 1 billion t of boron reserve with 80% B-11 and 80% of air is N2 of which 0.4% (CO2 0.04% 3000Gt in air) so a lot of ammonia NH3 in the world is also made mostly Li-7 little Li-6 in Li. UO2 as granules in BN (B-11 & N-15 baked to RBN (CBN) without Triso.
CBN tubes can be connected by clamping with one-time expansion after baking with heat and pressure.
RBN remains hard up to approx. 2800°C, incombustible, insoluble in water, chemically stable and with a lot of neutrons, graphite remains a plastically deformable spherical bed from 2500°C.

Li-7 absorbs very few neutrons if <1s then decays to He binds T to LiT etc. can be separated in a centrifuge least reactive alkaline earth metal hot only approx. 0.5g/ccm excellent coolant for HTR and super moderator.

Superphenix Na breeder can also be reactivated with Li-7 & RBN also breeds and safely through bladder waste? [[Special:Contributions/2.200.189.85|2.200.189.85]] ([[User talk:2.200.189.85|talk]]) 11:05, 24 April 2024 (UTC)

Latest revision as of 11:37, 24 April 2024