Proiectul BRANCOVEANU

Proiectul Sfintii Martiri Brancoveni – deocamdata doar in limba engleza

This project is coming to solve one of the most important today problems of mankind – the energy. Long time ago I asked myself – which one is the easiest form of energy which humans can handle? The answer is clearly only one = THE LIGHT! Thus Open Sphere Project is the first true optical design of all time of a fusion reactor. Our goal is to obtain a little Sun kept in place by the power of light and not inside a cage!

A new age just started  – THE FUSION AGE!

Give me the right spark and I will give you a star!

Chapter 1.  Summary

  • inside an prolate ovoid reflector a sphere of high-temperature plasma is hold on geometrical centre by the reflected light and is bombard with high velocity ions in order to produce exothermic fusion reactions – the release energy under the form of light is reflected outside of ovoid over a carbon foil in order to generate electrical power.
  • the light emitted by the inner side of carbon belt is collected and focused over plasma sphere via inner reflectance surface of ovoid.
  • the reflected light and lasers light will pressurize the plasma sphere containing nuclear fuel
  • two type of ion guns will be used – one for small velocity ions which nourish the plasma globe with target fuel and another for high velocity ions (up to 8,000 km/s) to obtain fusion reactions
  • irradiative working light power over open plasma sphere is between 1012 – 1022 W/cm2
  • working temperature is between 280.000 – 300.000.000o Celsius

Chapter 2.  Assumptions

  • silver /aluminium coating reflection of inner surface of ovoid exceeds 99,9 % of the incoming light
  • the shape of the ovoid is stable due to the following factors: temperature is constant + the ovoid is not moving (tilting) + auctors can easily adjust the reflecting shape of ovoid
  • the reflected light not exceed the reflecting spectrum of silver or aluminium
  • the outer belt of focusing system has a precision of 0,04 arcseconds.
  • The ion guns are able to bombard precisely the open sphere of plasma, no ions are missing the sphere
  • The entire energy of ions is recovered either via nuclear fusion reactions (capture) or by elastic scattering

Chapter 3.  Geometry

The basic idea of this project is to obtain a plasma sphere or a plasmoid which to be hold in vacuum by the power of the light. Basically an f/0.25 prolate ovoid can do this task but we have at least 2 main problems:

  • the light emitted due to scattering of ions in the body of plasmoid and in it corona is not coming directly from the geometrically centre of ovoid . thus light cannot be reflected back with high precision over the plasmoid sphere
  • the generated and twice reflected light is very hard to be used via any kind of conversion

Thus a new design is required. The basic idea is to split the collecting of light generated by the plasma sphere by the focusing over the plasma sphere of the light coming from an external source which of course can be heated directly by the light coming from plasma sphere. With other words our little sun will be kept inside a “light” cage on the geometrical center of ovoid chamber by the power of light generated by itself. Thus no magnetic traps are required – so heavy, so bulky, so expensive – so impractical.

For this new design an ellipse with small eccentricity is the solution.  Let’s draw an ellipse with foci equally disposed each other and points A and D. Segments AB BC and CD are equal and have the length a. If we place this ellipse inside one dimension Universe a photon generated from point B will be reflected by the inner side of ovoid (point M1) directly to point C. The line BM1 intersect the line CH and point R.

But what if we remove the area of ellipse between points B and C? We will obtain something like that:

And if we join the remaining areas we will obtained a 2 bodies truncate ellipse like in the below image. If we spin this figure around major axis H-K we will obtained a prolate truncate ellipsoid body which myself I am calling it “rubinon” or “rubinon chamber”:

In the above picture now points B and C are the same. The height is a * 1.3333(3). We are still in that one dimension Universe. If we continue the line M1-R this line will arrive now in point A. With other words the photon which already left point B (C) will pass again through point R and now will arrive in point A. Another photon escaped from point B will touch the ovoid inner reflecting surface will hit point M2 and will arrive in point D. Now we are getting out from one dimension Universe. By rotating this shape around major axis B-H we will obtain this new type of ovoid which is called to fulfill 2 major tasks:

– the incoming light from outside sources to be precisely focused over the plasmoid located in point B (blue circle)

– any light generated inside and around point B=C to be collected (with less precision) and pushed out from ovoid. As long as the light collected will heat a large carbon foil we are in NOT in need for any precision of outside focusing of collected light.

The final shape of ovoid will be something like in the below picture (not exactly but similar):

The rubinon approximate a prolate ellipsoid shape (as per above picture) and it surface area is about x 1.205 the area of a sphere which can be placed inside (for easier calculation):

Please note that the entire amount of the light emitted is coming from a microns size spot area thus the light collected is not so difficult to be pushed out via the same focusing system. This type of truncate ellipsoid of course is not the only one solution for an optical fusion reactor – at least another 22 geometric shapes can be used for this purpose.

Please find below the diagram of the first optical fusion reactor EVER made.

Chapter 4.  Reactor design (diagram)

Please be aware that components are not presented at scale. Also the diagram is just a concept design!

Where:

  1. second part of focusing system belt
  2. second system for light rays alignment belt
  3. first part of focusing system belt
  4. first (main) system of light rays alignment belt
  5. carbon foil belt
  6. semi-transparent mirror or variable mirror
  7. the inner side of rubinon coated with a reflective micron layer of aluminium or silver
  8. ignition system (startup system) of reactor
  9. lasers used to accelerate and focus ions beams
  10.  ions guns
  11.  On the top and on the bottom of the chamber is placed another optical arrangement (not mentioned in picture) in order to replace the poor reflective power of the rubinon at it extremities.

The Wolter type 1 standard focusing system and Airy disk

Depending on the size of the reactor component 1 can be a belt of CaF2 glass up to 30 cm height and which can sustain CW of light up to 15.000 W/cm2. This focusing belt will be an f/0.375 high precision Fresnel glass. For a higher amounts of light component 2 is removed and components 1 and 3 will be replaced by a Wolter Type I optical arrangement (Wolter Type I foietage) – please check the above mentioned picture. Be aware that not the entire front end area of Wolter mirrors will be used (net output effective area is smaller then the entire output area – thus the disposal of this mirrors should take onto consideration also the ineffective area – please check the above picture). From above picture we can see that in practice on reactor side the mirrors are NOT mandatory to be aligned perfectly one under another but can be arranged in order to increase the effective area. From the top to the centre each mirror will be placed deeper and deeper inside the Wolter foietage (arrangement) as per below picture. This solution clearly make harder the industrial efforts but the main benefit is the increasing of effective area up to 85 % of the the total output area of said optical design.

Thus component 4 – the allignement system – may miss if the reactor is very large and mostly of the energy will be used for generation of electricity. An intelligent arrangement of mirrors should be used in this case in order to manage also the off-axis light rays reflected by rubinon walls.

Component 5 is a very large carbon foil belt of 20 microns thickness which will be heated on inner side by the light coming from reactor. The outer side of the foil is generating also light which partially is reflected by component 6. The net output of the reactor is giving it by the light which is passing through component 6. This light can be collected and used in various modalities (out of scope of this material). The foil itself is covered with a nano-metric layer of hafnium carbide in order to minimize the carbon sublimation For better focusing and thus smaller Airy spot this carbon foil can be nested inside an argon atmosphere. Thus the yellow light emitted by carbon foil will be shifted from 550 nm to ultraviolet 400 nm.The argon atmosphere will minimize carbon sublimation. The output energy of carbon foil may very from 200 up to 650 W/cm2.

The carbon itself can be replaced with lower performance by tungsten, boron si some carbide fibers.

Component 6 – is a variable mirror controlled either mechanically or electronically

Component 7 – the ovoid structure just made by carbon fiber or by boron 11 fiber and is composed by thousand of panels with variable size! Each panel will contained microns size holes for evacuating the nuclear ashes which mainly are gases – as usually helium! Also – if will be necessary auctors similar with that ones used for astronomically mirrors should be used for near to perfect alignment and positioning !

I know that it will be a huge task to build such very large ovoid – which – much more ! should be empty …. That means the pressure inside should be less than 1 torr. In some of designs this huge ovoid could have 216 m height and 162 m wide. At such dimensions even if the curvature of Earth or local gravitational anomalies will matter! Once positioned a 100 microns layer of zerrodur glass will be applied by sputtering and after that will be applied a 10 microns layer of aluminium or silver. The body of rubinon should be well protected from vibrations. Any earth wake clearly will immediately stop the reactor! That means the structure itself beyond panels should provide the required mechanical stiffness!

Component 8 – the ignition system is not hereby described (industrial secret).

Component 9 – the lasers used to push ions toward the plasmoid is not hereby described (industrial secret).

Component 10 – are ordinary ions guns and are not hereby described (out of scope of this material). Lasers are called to guide precisely the fuel to the target. No ions will hit the inner reflecting surface of the reactor.

How is working my reactor?

The startup system generates in a very brief sequence a sphere of plasma which is compressed. The nuclear fuel is ignited and the fusion reactions begun. The ignition system is called to furnish energy just enough time in order the carbon foil to reach the temperature of incandescence and the light collected from the foil to have enough power to sustain the fusion reactions inside. By aware that the initial material from startup sphere is not mandatory to be the same with the nuclear fuel used after ignition.

The fusion reactions generate high velocity ions which are losing their energy by scattering inside the plasmoid and it corona. The light emitted will be mainly over 300 nm .This light is collected by the ovoid inner surface and re-directed out of reactor via components 1-4 in order to heat component 5 = the carbon foil. Part of the carbon foil emission is after that re-collected, light rays are aligned and focused over the plasmoid via again the same components 1-4. Now the cycle is completed.

The net power of the reactor consists of the light emitted by the outer side of carbon foil which can be totally or partially used in order to generate electricity.

Another two versions of reactor can be find below without any further explanations (oblate trunchate spheroid like a torus and two joined prolate spheroid trunchate bodies).

Chapter 5.  Nuclear fusion reactions involved. Types of reactors.

Mainly there are 5 types of optical fusion reactors design:

  1. Near to full aneutronic design (CONSTANTIN design)
  2. Deuterium – Tritium design (STEFAN design)
  3. Other neutronic fusion/fission reactions design ( RADU design)
  4. Induced beta plus transmutation done via electron capture by a proton (ECP)  followed by neutron capture by ions (MATEIAS design)
  5. CONSTANTIN BRANCOVEANU design.

Design number 5 (CONSTANTIN BRINCOVEANU Voievod ) – is the smallest nuclear fusion design EVER – the 5th element – is not requiring at all any ovoid mirror and is suitable for ships and large trucks. A version of this design I built it for space tugs – Proiekt GAGARIN. CONSTANTIN BRANCOVEANU design is a complex and advanced machine and is called to replace the design CONSTANTIN and it associated hydrogen piles wherever is required. CONSTANTIN BRANCOVEANU design is not hereby explained.

  1. Near to full aneutronic reactions – CONSTANTIN design (Sfantul Martir Constantin)

This type of design not allowed us to deal with high speed neutrons which usually are generated via some of the easiest fusion reactions! Be aware that all below cross-sections was obtained in laboratory conditions and will largely vary inside my reactor! There are few reactions which Mother Nature gives us for such purposes! Only 5 fit well inside my reactor:

1.         D     +  3He     ->         4He  +     p

2.         9Be  +     p      ->         4He  +  6Li

3.         p      + 11B      ->          3 x 4He

4.         p      + 15N      ->         12C  + 4He

5.         p      + 6Li       ->         4He  + 3He

Other reactions which can be taken onto consideration:

6Li + T            ->         7Li  + D          1 MeV 10,6 Tj/kg       280 mb at 1,3 MeV 370 mb at 3,05 MeV

1.         Deuterium + Helium 3 fusion – helium 3 being the target.

Due to scarcity of helium this reaction should not be my first choice but …. lets to not forget that 1 kilogram of helium easily produce the same energy like millions of tones of coal ! As we can see below side reactions of helium 4 ash will have very small cross-sections ! Due to their high velocity helium nucleons quickly will escape from plasma sphere !

D + 3He -> 4He (3.712) + p (14.641) 18,4 MeV  (353 Tj/kg)    900 mb at 250 Kev, 830 mb at 640 Kev

For a helium 3 plasmoid (helium as target) we have the following secondary reactions:

4He + 3He       ->  7Be +  γ                 510 Kev resonance      1,58 MeV 21,8 Tj/kg 1 ub at 950 Kev

  p    + 3He      -> 4He + e+ + ve              18,8 MeV – ve (475 Tj/kg)

For a deuterium plasmoid (deuterium as target) we have the following secondary reactions:

4He + D (Q = 1,5 MeV and 0.1 microbarn at 700 kev and D + p (Q= 1.4 MeV and 10-25 barns at 1 MeV) with

other words both reactions being without any interest due to their very low cross-sections.

  • Beryllium – protons fusion. One of the most promissory and interesting fusion reactions. Why?

Because again of small velocity of ash ions and because of mutilple reactiosn from secondary chain.

9Be + p           -> 4He (1,27) + 6Li (0,85)      330 kev  360 mb 2.126 MeV 22,0 TJ/kg) 43,4 %  13,11 Tj/kg

9Be + p           -> 2x4He + D                         330 kev  470 mb    641 Kev        6,3 Tj/kg    56,6 %

If protons will be the target the below reactions we will have only lithium 6 – proton fusion as a massive secondary reaction but also with a relative minor cross section.

If beryllium is the target (beryllium plasmoid) both deuterium ash and alpha particles easily will fuse with beryllium plasma as per below equations:

9Be + D          -> 7Li  + 4He                                      7.153 MeV       63 Tj/KG       100 mb at 1 MeV

7Li + d            -> 8Li  +  p      500 mb at 1 MeV         -192 Kev         (       TJ/kg)      150 mb – 720 Kev

8Li + d             -> 7Li  +  T                                                                  40,7 Tj/kg 90 mb at 1,6 MeV

8Li + 4He        -> 11B + n                                           53,3 Tj/kg 310 mb at 600 kev  540 mb at 1 MeV

9Be + D           -> 8Be + T                               4,592 MeV  40,4 Tj/KG 190 mb/ 1 MeV  290 mb/ 4 MeV

9Be + 4He      -> 12C (4,4) + n (1.26) + y     5.7 MeV   42 Tj/kg     300 mb at 1.3 MeV  EHe > 1.2 Mev

9Be + 4He       -> 12C + n (4,25 MeV)           5,7 MeV 42 Tj/kg 0,65 mb at 620 kev 240 mb/1,85 MeV

Both beryllium helium 4 fusion reactions have a cross-section less then 1 mb at 620 kev and at 1.85 MeV a cross section of 240 mb. Where the neutron of 1.26 MeV is quicky thermalized and the neutron of 4.25 MeV is multiplicated by beryllium as per below equation:

9Be + n            -> 2 x 4He       + 2 n                with 500 mb for 3.5 – 14 MeV incident neutron energy

3.         Boron 11 proton fusion. The most well-known aneutronic fusion reaction but unfortunately with a poor cross section:

p + 11B           -> 3 x 4He                   8.7 MeV    (66 TJ/kg)    max 1.2 barn at 550 kev  1 mb at 150 kev

4.         Nitrogen 15 proton fusion. The scarcity of Nitrogen 15 is a problem but not a true one.

p + 15N           -> 12C + 4He              5.0 MeV  30 Tj/kg  100 mb at 340 kev   5 × 10−7 b at Ep = 100 keV

5.         Lithium 6 – proton fusion.

This reaction is a very-very interesting one because of low velocity of residual ash ions and because of a large number of reactions from secondary chain. Lithium 6 is a target thus we have a lithium 6 plasmoid.

All secondary reactions have large cross-section only helium3-helium3 fusion being the laziest one.

p + 6Li             -> 4He (1.7) + 3He (2.3)         4,023 MeV      55 Tj/kg  75 mb at 240 kev  110 mb at 500 kev                                                                                               220 mb at 1,08 MeV    270 mb at 1,8 MeV

6Li(p, γ)7Be                                                                 at 800 keV = 3.1 ± 0.4 μb

6Li  + 3He       ->  4He(2245) + 4He(2245) + p(12390)         16,878 MEV    180,6 Tj/kg

6Li  + 3He       ->  7Be(25)      + d(87)                                                112.4  keV.      320 mb at 1,6 MeV

6Li  + 3He       ->  8Be(1845)  + p(14756)                              16,786 MeV

  • Deuterium – Tritium design (STEFAN  design – Sfantul Martir Stefan)

This design required 1 bar hydrogen atmosphere inside ovoid (rubinon) chamber and also …. some changes in disposal of ion guns. The hydrogen is called to moderate high speed neutrons but also X-ray light.

            The below well known reactions can be run inside reactor:

D + T   ->        4He (3,518) + n (14,071)      5 barn max at 64 kev 17.589 MeV (337 Tj/kg – 67,4 Tj/kg for α )

D + D -> 3He (0.82) + n (2.45)     15 keV     (50 %)             (  79 TJ/kg)      max   96 mb at 1,25 Mev

D + D ->   T (1.011) + p (3.022)                    (50 %)             (  97 TJ/kg)      max 110 mb at 1,75 Mev

overall the release energy for D-D reaction is around 88 Tj/kg or 58 Tj/kg without neutron energy. For D-D reaction the fast neutron of 2.45 MeV required the chamber ovoid to very large – 64 m diameter and hydrogen filled at least 0.1 bar in order to thermalize the neutrons and to not damage the reflecting aluminium coating.

  • Other neutronic reactions design ( RADU design – Sfantul Martir Radu )

The following neutronic reactions are taking onto consideration:

3.1.      Lithium 7 – deuterium fusion:

7Li + d     -> 4He + 4He + n    ( 162 TJ/kg)     244 mb at 300 Kev  500 mb at 650 Kev 1 barn/1MeV

            7Li + d     -> 8Li          +  p                              -192 Kev  res. 181 mb at 770 kev  150 mb – 720 Kev

            8Li + d             -> 7Li  +  T                                                                  40,7 Tj/kg 90 mb at 1,6 MeV

8Li + 4He        -> 11B + n                                           53,3 Tj/kg 310 mb at 600 kev  540 mb at 1 MeV

  • Lithium 7 – helium 3 fusion

7Li + 3He        -> 9Be +  p                              11,2 MeV   108 Tj/kg 11 mb at 1 MeV 105/2,5

            7Li + 3He        -> 6Li  +  4He                         13,33 MeV      128 Tj/kg

            7Li + 3He        -> D     +  4He + 4He              11,8 MeV

3.3.      Lithium 6 – deuterium fusion:

            2D + 6Li          -> 4He (11,18) + 4He (11,18)             22,371 MeV    (270 Tj/kg)   97 mb at 1,02 MeV

                                                                                                105 mb at 950 Kev             215 mb at 1,75 MeV

            2D + 6Li          -> 7Li (0,828)  + p (4,4)                       5,23 MeV      (       Tj/kg) 190 mb at 4 MeV

            2D + 6Li          -> 3He + 4He + n                                 5 MeV           (       Tj/kg)

            2D + 6Li          -> 7Be (0,42) + n (3)                             3,4 MeV (41 Tj/kg)    85 mb at 2,25 MeV

            7Be + D           -> 2 x 4He (2,8) + p (11,2)                  13 MeV  180 Tj/kg

            2D + 6Li          -> 5Li (0,222) + T (0,37)                       0,57 MeV      (       Tj/kg)

  • Boron 10 – deuterium fusion:

            10B + D           -> 3 x 4He                                           (148 Tj/kg)

            10B + D          -> 12C + γ (25,186)                            (202 Tj/kg)      200 mb at 1 MeV

            10B + D           -> 7Li + 4He

            10B + D           -> 11B + p                                           74 Tj/kg

            10B + 4He       -> 13C + p                                          4,06 MeV        (  28  Tj/kg) resonance 1,52 MeV

            10B + 4He       -> 13N + n                                          1,06 MeV        (  7,3  Tj/kg)

            10B + 4He       -> 12C + D                                          1,35 MeV        (  9,3  Tj/kg)

  • Boron 11 – deuterium fusion:

11B + D           -> 9Be +  4He                         8,022 MeV                  (  60 Tj/kg)

            11B + D           -> 12C +  n                  12,731 MeV    102 Tj/kg 0,5 mb/500kev 30 mb/1,15 MeV

            11B + D           -> 12B +  p                              1,138 MeV      8,5 Tj/kg 380 mb / 1,5 MeV

            12B + D           -> 13B + p                               12 MeV           98,8 Tj/kg

  • Uranium / plutonium fission design (not hereby explained – Proiekt URANIA) – where 1 atom of Uranium 235 releases about 202.5 MeV of energy from which 194 MeV can be used.
  • Induced beta plus transmutation done via electron capture by a proton (ECP) followed by

            neutron capture by ions ( MATEIAS design – Sfantul Martir Matei )

This design involved supplementary high power electron guns which spread with high precision relativistic electrons over the plasmoid surface. The required energy of electrons is around 780 Kev but in my design up to 20 MeV electrons are used. Relativistic electrons of 2-20 MeV hit ions and replace protons with neutrons inside nucleus. This type of reactor (Proiekt TAIMIR can be used for the industrial production of Flerovium 298 (298114Fl ) which is used further in other types of fission / fussion reactors (Proiekt INDIGIRKA).

Just 2 reactions fit well with MATEIAS design:

a) 3He + n       ->           T    +     p                  and                  b) 6Li  + n       ->           T    + 4He

a) Neutrons capture by helium 3 ions. This is my favorite reaction. Why? Because of low velocity of tritium and protons which easily will deposits their energy in plasmoid and in it corona. With no threshold this reaction is a true gem of fusion.

With only 3,4 mb at 191 kev tritium ions energy the neutron productions is quite small. The cross section of high speed neutrons captured by both species tritium and helium3 are several orders higher than both helium-tritium fusion reactions.

3He + n           -> T (191) + p (572)                            0.7638 MeV   18,4 Tj/kg   5,400 barn for thermal n–

Reactions from secondary chain:

n + T                -> T+n, p+n+2n, p+3n             2,4 barn at 3,5 MeV 1,6 barn at 0 MeV

3He + T           -> 4He (1344) + p (5376) + n (5376)  12.096 MeV (57 %) 194 Tj/kg 4 mb at 200 Kev 

3He + T           -> 4He (4773) + D (9546)                   14.319 MeV (43 %) 230 Tj/kg           

p + 3He           -> 4He + e+ + ve                                              18,8 MeV – ve (475 Tj/kg)

p + T                -> 3He +  n                                          -0.7638 MeV   200 mb at 1,2 MeV  550 mb at 2,8 MeV

The required neutrons are coming from the following reaction which has a variable cross-section (give it by the power of lasers and electron guns):

42He + e– → 41(2)HHe +  νe           41H    → 31T + n–   decay in 1,.39 × 10−22 s

that means we have to bombard in equal ratio the plasmoid with both helium 4 and helium 3 where also

32He + e– → 31(2)HHe+  νe                   and we obtained again tritium

The last reaction also can be used to run D-T fusion by bombarding in equal ratio the plasmoid with helium-3 nuclei (low velocity) and deuterium (high velocity). If the temperature of plasmoid is high enough (over 5,5 kev) we can run a self sustain reaction based also to helium-3 tritium fusion. Anymore due to the fact we have to bombard intensively with relativistic electrons the plasmoid this will have a very high temperature – over anymore 25 kev thus D-T reaction will have a high cross-section. Also another solution is to to bombard with deuterium and beryllium-10 nuclei which will quickly release 2 neutrons and 2 helium-4 ions

b) Neutron captures by lithium 6 ions:

Beams of relativistic electrons hit the dense lithium plasma. The cross-sections for such reaction is even if larger as below. The only one drawback being tritium lithium fusion via helium + neutron channel.  But because lithium 7 generation has a larger cross-sections practically the entire tritium will perish with this reaction. Please note that at any given moment will be enough lithium 6 inside core to run 6Li + n reaction.

The required neutrons are coming from the following reaction which has a variable cross-section (give it by the power of lasers and electron guns):

73Li + e– → 72(3)HeLi+  νe                   72He   → 62He + n–  in 2.9(5)×10−21 s           where helium 6 easily:

62He + e– → 61(2)HHe+  νe                   61H    → 31T + 3n–  in 2.9×10−22 s  where n has with 1.6 MeV

 then :

6Li + n            -> T (2,75) + 4He (2,05)                     4.783 MeV    (   66 Tj/kg) 940 barn for thermal

6Li + n            -> D            + 4He + n (800 kev)       – 1.474 MeV        750 mb at 6 MeV

6Li + n             -> 7Li + y                                            7,25 MeV        ( 100 Tj/kg)  38,5 mb for thermal

Reactions from secondary chain:

6Li + T -> 7Li + D                   1 MeV             10,4 Tj/kg  280 mb at 1,3 MeV 370 mb at 3 MeV

6Li + T -> 8Li + p                    800 Kev           8,4 Tj/kg    52 mb at    1 MeV

6Li + T -> 4He + 4He + n        16,1 MeV        172 Tj/kg   320 mb at 1,9 MeV 530mb/ 7,5 MeV

8Li + 4He        -> 11B + n                                             53,3 Tj/kg 310 mb at 600 kev  540 mb at 1 MeV

6Li + T ->   9Be + y                 17.7   MeV

7Li + T -> 10Be + y                 17,25 MeV      166 Tj/kg   320 mb at 1,9 MeV 530mb/ 7,5 MeV

6Li + 4He        -> 10B + y                                           4,46 MeV – resonance/thrs at 1.75 MeV

6Li + 4He        ->   9B + n                                                                   thrs at 3,54 MeV

6Li + 4He        ->   9Be + p                                         – 2.126 MeV

6Li + 4He        ->   D + 4He + 4He                             – 1.475 MeV

            Please find below full ECP cycle for both 6Li and 7Li:

Lithium 6 under induced ECP (electron capture process)

63Li + e–  → 62(3)HeLi  +  νe

62He       →      63Li    in 806 ms –       a very long half-lifetime which theoretically may involve He6 in further reactions

62He + 2H    1/10000 probability. Will be neglected

62He + 1n–  → 31T + 31T       clearly with so long lifetime He6 will be involved in further reactions

62He + e– → 61(2)HHe                     61H    → 31T + 3n–                 in 2.9×10−22 s  where n has with 1.6 MeV

63Li + 2e– → 61(3)HLi→ 31T + 3n–      in 2.9×10−22 s  where n has with 1.6 MeV

The estimated cross-sections for single/double electron capture for both lithium isotopes is 10.000/1

In the end tritium will be the main product:   31T + 31T     → 42He + 2n–+ y (11.3 MeV)

Also is possible:                                                       31T + 42He   → 3 x 21D  + n–

and then:                                                                 21D + 31T     → 42He(2,425 MeV) + n–(14.01 MeV)

Lithium 7 under induced ECP (electron capture process)

73Li + e– → 72(3)HeLi+  νe           72He   → 62He + 1n–  in 2.9(5)×10−21 s  than

62He       → 63Li                        in 806 ms –        a very long lifetime which theoretically may not involve

Li6 in further reactions

42He + 2H         1/10000           probability

62He + n–  → 31T + 41H         41H    → 31T +  n–                  in 1.39 × 10−22 s  where n has with 4.7 MeV

62He + e– → 61(2)HHe+  νe           61H    → 31T + 3n–  in 2.9×10−22 s  where n has with 1.6 MeV

With less than 3 zeptoseconds on which Helium eject the neutron and also some residual quantities of He and diprotons, my believe is that this time is too short for further reactions of 72He with electrons or with ions. But let’s treat also these reactions as long as the true cross-sections remain unknown.Due to high density of electron cloud we cannot exclude the theoretical possibility that the entire mass of Lithium to decay quickly to Hydrogen extremely instable isotopes either by direct ECP or by double ECP as below described.

72He + e– → 71(2)HHe+  νe                                   71H    → 31T + 4n–                 in 2.3(6)×10−23 s  than

73Li + n–  → 83Li → 84Be in 840 ms         84Be   → 2 x 42He  in 6.7×10−17 s    useful in next reactions

73Li + n–  → 42He + 31T + n– – 2.467 MeV                            due to Be fusion with He

63Li + n–  → 42He + 31T + y (4,8 MeV)  where He has 2.05 MeV and T has 2.75 MeV

42He + e– → 41(2)HHe +  νe           41H    → 31T +  n– (4.7 MeV)         in 1,.39 × 10−22 s

Clearly both He isotopes will quickly transform to instable isotopes of Hydrogen giving finally Tritium. Let’s treat now a possible but very rare induced double electron capture of Lithium 7. The cross-section of 3 electrons captured is very small and also the last proton will be quickly replaced by another one due to high presence of strong force inside this high density cloud of electrons and ions       

73Li + 2 e– → 71(3)HLi   +  νe                                              71H    → 31T + 4n–                 in 2.3(6)×10−23 s

Chapter 6   Plasmoid main parameters – temperature, pressure and fuel density.

Please find below some reactor examples for the Be+p fusion – a very big and a small size reactor:

1.         Very large size – ultra high tech technology – ultra high precision in collimation of light.

Lets take the following variant of reactor – probably the largest one which mankind can built – a rubinon chamber with 162 m diameter and 216 m height. The reflecting surface is about 100,000 m2 . A high quality mirror surface easily will reflect 99.9 % of the incoming light (if we run beryllium proton fusion) with resolving power of at least 1000 w per cm2 at working temperature of reflecting surface around 80 Celsius. Some X-ray will be responsible for this relative high working temperature. The reflecting power will be 1 x 1012 watts with other words 1,000,000 Megawatts installed power.

At such sizes I am not expected the Airy spot focus to be 0.366 microns diameter !!!!

At these sizes probably the first Airy maximum will be around 1.8 microns.

In despite of the fact that the shape of reflecting surface can be easily controlled also the working temperature I have some doubts that target of theoretically Airy first maximum spot of 0.366 microns can be achieved mainly due to defects of reflecting layer sputtering ! But for smaller sizes of rubinons an Airy spot of 0.8 microns can be achieved.

The sphere itself will be composed by 3 main layers (3 sphere of plasma placed each another one).

  1. The 1.8 µm diameter central sphere of maximum pressure will correspond to radiation above 360-400 nm. The first sphere surface is practically impenetrable for light at 1019 W/cm2.
  2. The 8 µm second sphere will start with the first Airy maximum, will overlap the second Airy maximum and will end with first Airy maximum of radiation around 1.100 nm.
  3. The third sphere will start above second layer with the second Airy maximum and will include the 3rd and the 4st Airy maximum and correspond with the overllaping of lasers. The third layer is the corona of our little sun. The surface temperature and the size of 3rd sphere is not hereby mentioned.

The pressure rapidly decrease from the surface of corona reaching 1 bar at 50 cm distance from the center of plasmoid.That means we have enough stopping power and in order to transform the kinetic energy of high velocity ions ash onto usefull spectrum light.

The reasonable size of the inner sphere of the first maximum will be (for Lambda 10) around 1.8 microns holding 40 % of plasmoid energy and the third sphere (lasers maximum) is expected to have around xxx microns. The irradiative power (light pressure) over the first layer can touch 4.4 x 1018 W/cm2 CW (lasers included) , the temperature on the surface of first Airy maximum is about 2,6 Kev where the light pressure will be near 15 Gbars, the plasma pressure around 8 Pbars and the density of plasma of beryllium + its derivates will be about 22 gr/cbm with other words up to 22 grams per cubic centimeter which is truly a high density. In such conditions if we take onto consideration all ions species involved and if we consider the fusion reactions isotropic we will have a tiny small spot inside first sphere with around 100 nanometres diameter where the temperature reach around 100 kev and pressure around 200 Pbars. The median density under the surface of first Airy maximum will be around 20 grams per cbm. The above mentioned calculations presumed that the entire power of reactor to be focused internally with no external output. By changing the power over the plasmoid can be changed also the output power. Of course there are NO economical reasons to build such very large and powerful reactor which required also a very large carbon foil of at least 200,000 m2. The size of this carbon foil will be 2,000 m diameter and 32 m high which clearly show us a very large electrical plant at all.

The most desirable type of reactor is that one which is using induced electron capture by protons and thus which is based to neutron capture by helium-3 and lithium-6 ions.

2.         Medium size – medium technology – poor precision in collimation of light.

Lets take the following variant of reactor built by a country from 3rd world – the rubinon chamber will have 54 m diameter and 72 m height. The reflecting surface is about 11,000 m2. A high quality mirror surface easily will reflect 99.1 % of the incoming light (if we run beryllium proton fusion) with resolving power of at least 225 w per cm2 at working temperature of reflecting surface around 80 Celsius. Some X-ray will be responsible for this relative high working temperature. The reflecting power will be 25,000 Megawatts.

Due to a low developed industry the diameter of first Airy maximum will be 2.8 mm diameter (0.25 cm2) and not 1,8 µm with an irradiative power over the first sphere surface barely reaching 4×1014 W/cm2, near 3 million Celsius temperature beneath it surface, a light pressure over 100,000 bars, a plasma pressure around 1 Mbar and a density of 0,1 g/cm3.

One question aris quickly:

            CAN WORK SUCH REACTOR?

The answer is: YES, of course. And easily! Why?

Because the high speed ions will have even if higher velocity on the surface of first maximum Airy sphere due to less losses via scattering.

In fact for a pure fusion reactor an irradiative pressure over first sphere of around 1×1016 W/cm2 is very possible to be the OPTIMUM between the cross-section requirment and losses due to scattering on evading ash. 10 Mbar pressure and 50 ev temperature is very possible to be the optimum for first sphere.

Also a well executed reactor of 18 x 24 metres and 10 microns diameter of first sphere easily can reach the parameter of 1×1014 W/cm2 – where the diameter of 10 microns means no very high collimation at all nor very high precision in rubinon manufacturing.

High irradiative power is required ONLY for reactors based to induced beta plus transmutation done via ECP – where also the main data for pressure + temperature + density differ due to pressure of electron plasma and also due to toroidal vortexs of magnetic field.

2.         Small size – ultra-high technology – very high precision in collimation of light.

Lets take the following variant of reactor built by a country like Germany for example – the rubinon chamber will have 16.5 m diameter and 22 m height. The reflecting surface is about 1,000 m2. A high quality mirror surface easily will reflect 99.9 % of the incoming light (if we run beryllium proton fusion) with resolving power of at least 1,000 w per cm2 at working temperature of reflecting surface around 80 Celsius. Some X-ray will be responsible for this relative high working temperature. The reflecting power will be 10,000 Megawatts and the output power may very between 20 up to 800 Megawatts.

The diameter of first Airy maximum will be 1.8 µm diameter with an irradiative power over the first sphere surface barely reaching 4×1016 W/cm2, around 9 million Celsius temperature beneath it surface, a light pressure of 14 Mbar, a plasma pressure of 2 Tbars and a density of 1 g/cm3. The carbon foil will be small – 100 m in diameter and 3.2 m height.

PROIEKT TUNGUSKA

Refers to a thermonuclear power plant of 88,000 MW with a final net gain of 15 % , 71 % plant itself consumption and 14 % lost energy. Project initiated on June 2012 ended August 2014.

Medium size – medium technology – medium precision of light collimation.

Lets take the following variant of reactor built by a country from 3rd world like Romania – the rubinon chamber will have 78 m diameter and 104 m height.In real life we can see from very far away a large doom of 60 m height and 80 m diameter. The reflecting surface is about 23,000 m2. A high quality mirror surface easily will reflect 99.5 % of the incoming light (if we run beryllium proton fusion) with resolving power of 383 w per cm2 at working temperature of reflecting surface around 55 Celsius. The reflecting power will be 88,000 Megawatts and the installed electrical power max. 13,000 Megawatts via 40 medium sizes steam turbines.

Due to the medium developed industry the diameter of first Airy maximum will be 1.6 mm diameter with an irradiative power over the first sphere surface of 62,000 MW reaching 3.1 x 1015 W/cm2, 4.8 million Celsius temperature beneath it surface, a light pressure over 1,000.000 bars, a plasma pressure around 80 Mbar and a density around 0,2 g/cm3.

Chapter 7   Benefits and draw-backs of such type of reactor

The benefits are multiple:

  • very – very few radioactivity
  • no radioactive released in case of natural disaster (plane crush for example)
  • quick change of released power which may vary very large from 100 up to 30,000 Megawatts-hour
  • easy maintenance
  • very cheap construction (for the a/m example the final price will not exceed 400 millions euro = average european estimation for man-power and materials)
  • very low price of produced electrical power – around 14 eurocents per Megawatt-hour over 12 years

The draw-backs:

  • not easy at all to built such large mirror and to achieve such precision in focusing of the light
  • the internal reflective surface of ovoid reactor should be re-coated at least once at 2 years.
  • the entire construction is prone to vibrations and easier destruction by accidents
  • not easy at all this large ovoid to be hold inside a larger vacuum or low pressure chamber
  • overall very few countries can built such reactor mainly that ones with large experience in building of astronomically large mirrors

Disclaimer:

Above it is just a design proposal and should be treat it like that. Please be aware that not all details are presented nor all explanations are giving it. Heavy mathematical simulation/computation of the above mentioned spheroids shape is a must. During the development of the project the AUTHOR cannot be kept as responsible for any damages of equipments, machineries or/and any other kind of properties nor for people injuries or human losses. Properly trained staff has to be involved, certain authorized procedures has to be used as per each country / European laws and regulations. All materials used have to be approved by special authorities in order to avoid any accidentally surge of ionized / radioactive materials which may occur. Isolated places are required, neutrons shields has to be used. All electrical installations have to be properly isolated in order to avoid surges in walls and ground. Staff protection suites are required. Data management must be kept under strict control.