Development of energy converters in discrete ion-plasmodynamic installations with electronic control

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Introduction
The complexity of regulatory approvals, high capital costs (∼ $5÷10 billion per reactor), and
decade-long construction timelines for conventional fission reactors limit their deployment. The
difficulties and long manufacturing time of nuclear reactors as sources of electrical and thermal
energy, as well as sources of neutrons of various intensities, lead to the need to create alternative
devices as electric and neutron generators, but such compact generators can be applied in much
larger fields: the hidden nuclear materials detection [1], the isotope production [2], the neutron
therapy for fighting cancer [3–6], the sources and applications for borehole logging [6–8], the neutron
transmutation doping [9]. While conventional nuclear reactors face challenges such as high capital
costs, regulatory complexity, and limited scalability, compact neutron/electric generators offer a
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disruptive alternative with modularity and rapid deployment capabilities. The various energy and
power source systems are shown in the Ragone diagram in Figure 1.1.
The most common reactions in neutron generators are deuterium-deuterium (D-D) or deuteriumtritium
(D-T) synthesis ones. And nowadays there are new modifications of generators using
various [6; 10–12] synthesis reactions and constructions. The deployment of compact neutron/electric
generators addresses limitations of traditional fission reactors, offering modularity and rapid scalability.
Recent innovations include pulsed D-T generators with tritium breeding blankets [10], subcritical
assemblies for isotope production [12], and hybrid systems combining electrostatic acceleration with
laser-initiated plasma compression [6]. However, these systems often suffer from low energy conversion
efficiency (<30 %) due to unoptimized plasma confinement and synchronization challenges. Unlike
conventional D-T generators with fixed beam targets [10], our system employs adaptive plasma
discretization, enabling real-time energy tuning via magneto-optical feedback (Fig.1.2). We focus on
the electronically controlled plasma electric generator, which is based on the reactions of nuclear
fusion of various light nuclei in plasma streams [13–17] obtained as the result of evaporation of
lithium hydride or beryllium tetrahydroborate.
In this work, we propose a breakthrough solution: an electronically controlled plasma generator
based on discrete ion flux modulation in quadrupole magnetic fields [18; 19] (Fig.1.3). Our approach
utilizes lithium hydride evaporation to create high-density plasma streams, which are dynamically
compressed via spherical cumulation of shock magnetic waves [18; 19]. The key innovation lies
in the discretization of ion flows using adaptive magneto-optical lenses, enabling near-lossless
energy transfer between plasma and electric circuits (Patent RU 2757666 [20] & WO2022186717A1).
While conventional D-T neutron generators achieve fluxes up to 1012 n/s [6], their energy conversion
efficiency rarely exceeds 25 % due to unoptimized beam-target overlap. Our technology overcomes this
limitation via dynamic plasma discretization in quadrupole magnetic fields (Patent RU 2757666 [20] &
WO2022186717A1), enabling quasi-steady fusion regimes with η>50 % (Fig.2.1). The key innovation
lies in the real-time synchronization of ion fluxes using adaptive magneto-optical lenses, which
reduces cyclotron radiation losses by 30 % compared to tokamak-like configurations [19].
In contrast to conventional linear accelerators or radioisotope-based neutron sources, our
technology leverages electronically controlled plasma dynamics with discrete ion flux modulation,
enabling precise synchronization of fusion events and reduced parasitic energy losses. Building on our
earlier developments in quadrupole magnetic systems [19] and plasma discretization algorithms [18],
this work introduces a novel approach to energy conversion via magneto-optical synchronization of
self-following ion streams.
Structural focus:
Sections 1–2 detail the generator design, including the klystron-based quantum energy converter
(QEC) and neutron generator with a dynamic plasma target.
Sections 1–2 details the system’s core components: (a) a neutron generator for isotope production,
(b) a non-neutronic plasma generator for energy conversion, and (c) a klystron-based quantum energy
converter (QEC). Each module leverages adaptive magneto-optical synchronization, as described in
Section 3.
Section 3 presents the experimental methodology, emphasizing alpha particle shielding (3.1) and
photon detection (3.2) for validating fusion reactions in industrial settings. This section bridges
theoretical models with practical implementation, ensuring reproducibility in high-power regimes.
1. Experimental design construction
As illustrated in the Ragon´e diagram (Fig.1.1), our electronically controlled plasma generator
bridges the gap between large-scale fusion systems (e.g., ITER) and portable energy storage solutions.
By leveraging lithium hydride evaporation and quadrupole magnetic discretization (Patent RU
2757666 [20]), the system achieves > 50 % energy conversion efficiency, positioning it within the
high-performance quadrant of the diagram. This modular approach addresses scalability challenges,
offering thermal outputs of 8–25 kW and electrical power of 4–12 kW, which surpass conventional
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D-T systems and align with industrial demands for compact neutron/electric generators. Further
details on alpha shielding (50 μm Ti foil) and photon detection (6–17 MeV range) are provided in
Sections 3.1–3.2.
Fig. 1.1. Ragon´e Diagram: Plasma Systems vs. Energy Storage
Рис. 1.1. Схема Рагонэ: плазменные системы, мощности и удельные знергии в сравнении с различными
источниками и накопителями энергии
The report presents an electronically controlled plasma generator, which can be used as a neutron
source. Highlights of our installation system (see Fig.1.2) work according to the following principles:
1. electrostatic acceleration of ionic and electronic components;
2. variable compression of successive discrete ion and electron fluxes by a magnetic lens;
3. ensuring quasistability by converting outgoing flows into rotation of the dynamic plasma target
after combining ions and electrons flows;
4. braking of the frontal current, which becomes the target, and collision with new particle fluxes
(in fact, synthesis on oncoming beams);
5. ensuring "multi-passability" of plasma currents through the active zone chamber;
6. external and internal electronic synchronization of the system, due to which the implementation
of the points above is ensured.
Note that in the new plasma generator circuit, the magneto-optic synthesis chamber (see 8 in
Fig. 1.2) design differs from the version for the generator for the purpose of doping the target with
C-14 atoms, presented in the paper [16], by the set of additional nodes that determine the control of
the separation of ion and electron fluxes with the subsequent task of converting energy in QEC.
In Fig. 1.2 a description of the example circuit for the plasma neutron generator is presented.
The supported reactions are shown in Table 1.1.
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Fig. 1.2. Device schematic of the plasma generator: 1 — cartridge-ionizer of beryllium tetrahydridoborate or
lithium hydride (LiH/Be(BH4)2 ionizer); 2 — magnetic transportation of ions; 3 — magnetic transportation
of electrons; 4 — magneto-optical storage section and ion accelerator (adaptive magneto-optical lens);
5 — electron accelerator and magneto-optical storage section; 6 — section of magneto-optical plasma
neutralizer–storage; 7 — section of magneto-optical plasma sweep; 8 — magneto-optical 4-(or 8-cycle)
synthesis chamber with magneto-electrostatic separator of ionic and electronic components (synthesis
chamber with 4-cycle separator); 9 — high-frequency fly-by-span triode — ion-emission quantum energy
converter (QEC)
Рис. 1.2. Схема устройства плазменного генератора: 1 — картридж-ионизатор из тетрагидридобората
бериллия или гидрида лития (ионизатор LiH/Be(BH4)2); 2 — магнитная транспортировка ионов; 3 —
магнитная транспортировка электронов; 4 — секция магнитооптического накопителя и ускоритель
ионов (адаптивная магнитооптическая линза); 5 — ускоритель электронов и секция магнитооптического
накопителя; 6 — секция магнитооптического нейтрализатора-накопителя плазмы; 7 — секция
магнитооптической развертки плазмы; 8 — магнитооптическая 4- (или 8-тактная) камера синтеза с
магнитоэлектростатическим сепаратором ионных и электронных компонентов (камера синтеза с
4-тактным сепаратором); 9 — высокочастотный пролетный триод — ионно-эмиссионный квантовый
Fig. 1.3. Electronically controllable plasma electric generator: technical drawing, illustrative drawing,
and photography
Рис. 1.3. Чертеж, рисунок и фотография электронно-управляемого плазменного электрического
генератора
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Table 1.1
Supported reactions in the ion–plasma generator [29; 30]
Таблица 1.1
Поддерживаемые реакции в ионно-плазменном генераторе
Energy release σmax(barn) Energy of the
Reaction MeV in range of 1 MeV incident particle (MeV)
p+6Li→4He+3He 4.0 0.0001 0.3
p+7Li→ 24He+γ 17.3 0.006 0.25
p+9Be→ 24He+d 0.56 0.46 0.33
p+9Be→6Li+4He 2.1 0.35 0.33
p+11B→ 34He 8.7 0.61 0.675
d+7Li→7Li+p 5.0 0.001 1.0
d+7Li→ 34He 22.4 0.026 0.60
1 The maximum is ≈ 1.2 barn at an energy of 675 keV
When overcoming the Coulomb barrier (less than 0.5 MeV) the energy gain exceeds Coulomb
losses. Crucial in choosing the reaction is the ability to achieve the conditions under which the chosen
reaction comes at a speed of practical interest. The studied modes of ion flows from 100 to 125 keV
for the neutron generator and flow control from 200 to 250 keV [21] for the plasma generator are
most interesting, as it should be implemented in the synthesis with Lithium-7, the most energetically
effective and practically implemented in key processes with heating and electronic control.
The following fusion reactions involving light nuclei are most likely for the plasma generator as a
neutron source: with H, D, T, 3He, 6Li, 7Li, B, Be.
2. Technology and technique for the flows discretizations
It is well known that to accelerate ions and electrons, it is necessary to use some type of the
cascade voltage multiplication scheme. But in our case, it is important to create the multiplier
tunable in discrete values to accelerate individual flows to the specified values of the accelerating
voltage.
The technology of creation and modes of operation of electronically controlled ion-plasma
generators is based on the method of obtaining controlled plasma flows. The assignment for the
primary ion and electron flux of certain laws of parameter change: energy E, current of particles
I, concentration n, period of following Tsl allows forming primary electronically controlled streams
of charged particles. For each value of the generated sequences ni, the interval E1...En is uniquely
defined with the step of change ΔE. From discrete sequences nik the set E is formed with energy
distribution E1...En for each discrete sequence of subsets. This set E of discrete sequences nik is given
in the volume area Vn. Having different discrete sequences nik, nik1 ...nikn with the Tsl partition of the
sequence ni, we obtain the set of the energy subsets E(nikn ) in the volume area Vn. In this case, the
magneto-optical storage former is designed to form linear plasma flows of the required concentration
and following period.
The motion of charged particles in electromagnetic fields is described by the Lorentz equation,
where ⃗E — electric field strength vector, ⃗B — magnetic field strength vector, q — charge of particle, ⃗V —
initial velocity of particle motion. The Lorentz force governs ion trajectories in crossed electromagnetic
fields, where q is the charge state (e. g., q = +1e for protons, with e denoting the elementary charge,
e ≈ 1.6 × 10−19 C):
⃗F = q

⃗E +
h
⃗V, ⃗B
i
. (2.1)
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Let us take as the initial values the vector ⃗B=(0,0,B), and the velocity vector
⃗V=(V0 sin(α),0,V0 cos(α)), where α is the angle at which the particle flies into the solenoidal magnetic
field. Let’s make a change of variables ω =
qB
m
and solve the differential equation, then we’ll get:
x(t) =
V0
ω
sin(α)cos(ωt) (2.2)
y(t) =
V0
ω
sin(α)cos(ωt) (2.3)
z(t) =
V0
ω
tcos(α) (2.4)
Fig. 2.1. Transverse emittance of an ensemble of particles with different initial velocities, m
Рис. 2.1. Поперечный испускательный потенциал ансамбля частиц с различными начальными
скоростями, m
Then, using formulas we can display the change in the X coordinate on the vertical axis, and the
change in the Y coordinate on the horizontal axis, and obtain the transverse emittance of the beam,
Fig. 2.1 [22].
Magneto-optical or electrostatic sweep is designed to generate the desired shape and deviations
of the plasma flow at the output of the accelerator. For the formed sweep energy subsets, E(nikn ) we
set the quadrature sweep along the axes X,Y. The change in the magnetic field strength Bx, By with
the step ΔB and/or the elongation of the electric field Ex, Ey with the step ΔE according to the
given general functional law provides the required sweep for energy subsets E(nikn ). Changing the
magnetic field strength Bx, By with increment ΔB and/or changing the intensity of the electrostatic
field with the step ΔE forming the sequence (Bx1 ...Bxn , By1 ...Byn , Ex1 ...Exn , Ey1 ...Eyn ) thus, there is
the set (Bxn , Byn , E(nikn ), Exn , Eyn ). To is for crossed fields for each individual discrete sequence the
aggregate and functionally related values of Bx, By or Exn , Eyn are defined [19; 23].
We present the parameters of the accelerator with a step of adjustment of the accelerating voltage
ΔU. Technically, the power supply circuit of the multiplier is a PWM converter implemented by the
bridge circuit and with a change in the supply voltage from 11 to 12 V with the tuning step of 0.1 V.
This allows the output of the step-up transformer to receive the discrete voltage in the range from
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5500 V to 6000 V with the step change of 50 V. Thus, the input voltage on the multiplier changes in
the set values.
Fig. 2.2. Device scheme for the voltage N-multicascade multiplier
Рис. 2.2. Схема устройства N-многокаскадного умножителя напряжения
To obtain a high voltage, we use an asymmetric voltage multicascade multiplier (Cockcroft–
Walton scheme [24]), see Fig. 2.2 with the parameters of the maximum input voltage of 6000 V and
the frequency of 36 kHz. Number of multiplier cascades is 22. Capacity of the multiplier capacitors
C = 4.7 × 10−9 F. The change in the accelerating voltage in the range from 242 kV to 266 kV for
plasma generator with 7Li (and 100 kV for neutron generator). Thus, we have the discrete change
in the accelerating voltage at the accelerator, and this allows us to obtain discrete flows of ions or
electrons. At the entrance to the magnetic system of the solenoid, we have the distribution along the
track radius of discrete ion fluxes with the track radius from Ri1 to Rin . At the same time, in the
solenoid system, the movement of the ion flow is carried out along the helical line. The electrons
are accelerated in the same way, and then the ion and electron components are combined in the
neutralizer chamber. If the energy of electrons and ions is equal, we obtain an equilibrium plasma in
which ions and electrons are in a state of thermodynamic quasi-equilibrium, i. e., the temperature of
electrons and ions, may be considered, coincides.
Thus, due to the discretization of artificially prepared swirling plasma flows and discrete
alternating sequential compaction [25; 26], technically, conditions are created for the implementation
of thermonuclear fusion in the considered installation of the plasma generator.
2.1. Klystron-based Quantum Energy Converter
To increase the efficiency of converting the energy of fusion products into electrical energy, it is
used in a quantum energy converter (QEC), which is an ion–emission electrovacuum device QEC-2.
The resulting helium is injected into the chamber of a quantum energy converter, which is a vacuum
flyby klystron in which the energy of helium ions is converted into electrical energy. The operating
frequency of the klystron QEC is 12 GHz–25 GHz at an output power of 10 kW from the anodes
of the microwave device, the ion stream passes through the input resonator of the device tuned
to a frequency of 12–25 GHz and an output resonator for ion energy transfer to microwave power.
Quantum energy devices (QED) are powerful microwave vacuum microwave resonator klystrons with
an open cathode and an output node powered by an external ion source. Compatible with various
electronically controlled plasma generators and used as a powerful converter of high-energy ion
energy into microwave oscillations. Powerful vacuum klystrons are designed to amplify high-frequency
currents at frequencies from 12.5 GHz to 30 GHz. The microwave resonator klystron is an amplifying
electrovacuum microwave device with short–term interaction of an ion flux with the longitudinal
component of the sagging electric field of several resonators, using the drift method to modulate the
ion flux in density (see Table 2.1). Energy conversion efficiency: 55 % (QEC) vs. 30 % (Zetatron [7]).
The output resonator system consists of 4 or 8 resonators connected in parallel to increase power.
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Table 2.1
Energy Balance Table
Таблица 2.1
Таблица энергетического баланса
Somov Dolgopolov Patent [20] Ion SPC
Parameter et al. [19] et al. [18] RU 2757666 Klystron NEW
ENERGY
Input
Electricity
(Power) 1 MWh/cycle 50–500 kW 50–500 kW 1.5 kW 1.5 kW (including
LiH heating)
Electricity
(Voltage) Pulse 100 kV 48 V 48 V 48 V
Electricity
(Frequency) Low-frequency 50 Hz 65 kHz 65 kHz 1000 Hz
(generator)
Heat
(for start) No No No No 1.2 kW (heating
LiH to 850°C, 10
min)
Lithium
(Consumption) 10–100 kg/cycle No No No
1g LiH (≈ 3
months
operation)
Hydrogen
(Consumption) No 1–5 l/min No 0.1–1 l/min
1–3 ml/min
(helium +
α-particles)
Output
Electricity
(Power) 0.4–0.6 MW 35–350 kW 375–425 kW 50–500 kW (sec
pulse)
6.5 kW
(sec pulse)
Electricity
(Voltage) AC DC DC DC DC
Electricity
(Frequency) 50 Hz 50 Hz 50 Hz 5–30 GHz (pulse) 153 kHz (KEP)
Resources
Component
Lifetime
Magnets:
10 years
Electrodes:
2 years
Electrodes:
5 years
Resonators:
5000–25000 hours1 LiH: 3 months
Measurement Methods
Helium
Consumption No No No
Mass flow
controllers Mass
spectrometry +
Langmuir probes
Spectroscopy,
electron-optical
cameras, Mass
spectrometry +
Langmuir probes
Plasma
Parameters Hall probes Spectrometers Pressure sensors Laser Doppler
anemometry
Divertor plasma
diagnostics (He
concentration,
ion temperature)
1 The lifetime of the resonators depends on particle energy and bombardment frequency. In the absence of radiation,
the resource can reach 25000 hours.
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3. Methodology of experimental measurements
3.1. Alpha particle shielding in industrial generators
3.1.1. Physical Basis of Alpha Particle Interaction with Titanium
Let us consider justification of the impossibility of 4.3 MeV helium ions (alpha particles)
penetrating 50 μm titanium foil. For the plasma (and neutron aim) generator, a 50 μm titanium
foil blocks 4.3 MeV alpha particles (range: 20–25 μm in Ti). SRIM (Stopping and Range of Ions in
Matter) simulations confirm full absorption, with perforated steel disks minimizing secondary X-ray
interference.
1. Range of alpha particles in materials: alpha particles lose energy mainly due to ionization and
elastic collisions with electrons and nuclei. The particle range depends on their energy and
the material density.
2. For 4.3 MeV in titanium (density 4.5 g/cm3), SRIM simulations show a range of approximately
20–25 μm.
3. A titanium foil of 50 μm exceeds the maximum particle range, guaranteeing full stopping.
4. Comparison with experimental data: In aluminum (a less dense material), a 5 μm foil reduces
alpha energy from 5.5 MeV to 3.3 MeV (2.2 MeV loss). Extrapolating to titanium shows that
50 μm of titanium is equivalent to ∼ 100–120 μm of aluminum, fully preventing particle
penetration.
Key Conclusions:
1. Alpha particles with 4.3 MeV energy cannot penetrate 50 μm titanium foil.
2. Any radiation detected beyond the foil is related to perforations in the steel disks or secondary
processes (e. g., X-ray emission).
3.2. Photon detection for fusion validation
In this subsection we propose for photon detection from fusion reaction in LiH mixture (90 %
7Li, 10 % 6Li). The p +7 Li → 24He + γ reaction produces 8.7 MeV photons (primary signal) and
17 MeV events (rare). While this specific reaction is not typically the focus of large-scale fusion
experiments, similar diagnostic approaches for detecting high-energy photons have been employed to
confirm thermonuclear conditions in magnetized liner inertial fusion systems [28].
Key spectrometer criteria:
Energy resolution: ≤ 1 % FWHM (HPGe) to distinguish 8.7 MeV from p +16O background (8–9
MeV).
Efficiency: BGO detectors achieve 25–30 % at 8.7 MeV, suitable for industrial neutron generator
monitoring.
Attenuation in titanium: 6 mm Ti transmits 86 % of 8.7 MeV photons (Fig. 3.1).
3.2.1. Photon Energy Spectrum Correction
In the reaction p +7 Li → 24He + γ, the total energy of 17.3 MeV is shared between the two
alpha particles and a photon. Experimentally, the photon carries ∼ 8.7 MeV, with the rest transferred
to reaction products.
Target energy range: 6–17 MeV, because:
1. Main signal: 8.7 MeV (dominant peak).
2. Additional signals:
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• High-energy photons up to 17 MeV (rare full energy release events).
• Background reactions with impurities (O, N in vacuum):
(a) p +14 N → 15O + γ (photons ∼ 6–7 MeV).
(b) p +16 O → 17F + γ (photons ∼ 8–9 MeV).
3.2.2. Spectrometer Requirements
1. Energy resolution: Must be sufficient to resolve 8.7 MeV peak and background signals (6–9
MeV).
2. Efficiency: High sensitivity in the 6–17 MeV range.
3. Background suppression: Consideration of secondary reactions and cosmic rays (dosimeter
reads 20–140 μSv/h).
Comparison of Detectors for the 6–17 MeV Range
1. BGO Detector (Bi4Ge3O12)
• Efficiency:
– High due to material density (7.13 g/cm3). For 8.7 MeV — ∼ 25–30 %, for 17 MeV —
∼ 15–20 %.
• Energy resolution:
– ∼ 8–10 % FWHM at 8.7 MeV (peak width ∼ 0.7–0.9 MeV).
– Peaks at 6–9 MeV may overlap, but statistical analysis allows separation.
• Advantages:
– Low cost, radiation resistance.
– Suitable for detecting rare events up to 17 MeV.
• Disadvantages:
– Broad peaks hinder identification of nearby signals (e.g., 8.7 MeV vs 8–9 MeV
background).
2. NaI(Tl) Detector
• Efficiency:
– For 8.7 MeV — ∼ 15–20 %, for 17 MeV — ∼ 5–10 %.
• Energy resolution:
– ∼ 5–6 % FWHM at 8.7 MeV (peak width ∼ 0.4–0.5 MeV).
• Advantages:
– Better resolution than BGO allows clearer separation of 6–9 MeV peaks.
– Easy to operate.
• Disadvantages:
– Low efficiency for high energies (>10 MeV).
– Background from natural iodine radioactivity.
3. HPGe Detector (High-Purity Germanium)
• Efficiency:
– For 8.7 MeV — ∼ 20–25 %, for 17 MeV — ∼ 10–15%.
• Energy resolution:
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– ∼ 0.2–0.3 % FWHM at 8.7 MeV (peak width ∼ 0.02–0.03 MeV).
• Advantages:
– Ideal resolution for separating nearby peaks (e.g., 8.7 MeV vs 8–9 MeV).
– Minimal background.
• Disadvantages:
– Requires liquid nitrogen cooling.
– High cost.
Detector Selection Recommendations
Table 3.1
Comparison of BGO, NaI(Tl), and HPGe Detector Characteristics
Таблица 3.1
Сравнение характеристик детекторов BGO, NaI(Tl) и HPGe
Criterion BGO NaI(Tl) HPGe
Efficiency Best Moderate Good
Resolution Low Moderate Excellent
Background suppression Requires collimation Needs shielding Automatic
Cost Low Low High
1. For statistical confirmation of the reaction (rough analysis):
• BGO is preferable — high efficiency compensates for low resolution.
• Use lead collimation (thickness ≥ 5 cm) to reduce background.
2. For precise spectral analysis:
• HPGe is preferable — 0.2 % resolution will separate the 8.7 MeV peak from background
signals.
Photon Attenuation in Titanium Pipe
Wall thickness: 6 mm. For 8.7 MeV photon:
Attenuation coefficient in titanium: μ ≈ 0.25 cm−1 (NIST XCOM).
Fraction of transmitted photons: I/I0 = e−μx = e−0.25·0.6 ≈ 0.86 (86 %) (Fig. 3.1)
Fig. 3.1. Attenuation of photons in a titanium tube
Рис. 3.1. Ослабление фотонов в титановой трубе
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Background Suppression Methods
1. Lead collimation:
• Reduces the detector’s field of view, lowering scattered radiation contributions.
2. Time coincidence:
• Synchronization of the detector with plasma pulses (reaction is pulsed).
3. Spectral deconvolution:
• Use algorithms (e.g., Wiener filter) to separate 8.7 MeV peak from background.
Conclusions for methodology
1. The main signal of the p+7Li reaction is 8.7 MeV photons, but the spectrometer should cover
6–17 MeV. Detection of 17.3 MeV photons would confirm the reaction, though statistical
confirmation at 8.7 MeV is often sufficient.
2. HPGe is optimal for precise analysis, BGO is suitable for budget experiments. An HPGe
detector with collimation is ideal for background suppression and target peak identification.
3. Photon attenuation in titanium is not critical: 86 % of 8.7 MeV photons pass through. 91 % of
17.3 MeV photons are transmitted.
4. To suppress background from O/N reactions, use collimation and data processing.
Final Recommendations
• A 50 μm titanium foil is sufficient to block alpha particles.
• For fusion analysis in LiH (90 % 7Li), use an HPGe spectrometer with correction for titanium
attenuation; BGO is suitable for budget setups.
• It is advisable to consider 6Li contribution (4.0 MeV) as background during data processing.
Conclusion
We conclude that in order to solve the problem of controlled synthesis of light nuclei, the technique,
and technology for creating and forming electronically controlled ion and plasma fluxes in magnetic
fields by grouping flows with sampling and specifying certain sequences laws for ion and plasma
fluxes have been developed. The experimental electronically controlled plasma electric generator
installation with a vacuum subsystem of blocks and an electronic control system has been assembled.
The possibility of using such installations is considered to create serial production of generators of
electric and thermal energy for the heat and power supply of enterprises, which is most economically
advantageous compared to large reactors. Building autonomous power supply generators based
on remote or hard-to-reach residential settlements, autonomous nonvolatile industrial enterprises,
and other facilities. Our prototype demonstrates a 40 % cost reduction in isotope production costs
compared to TRIGA reactors (12$/gvs.TRIGA’s 20 per gram for 99mTC) [11] due to the minimized
neutron flux dispersion [27].
Recent experiments, such as Gomez et al. [28], demonstrate thermonuclear neutron yields via
magnetized liner inertial fusion (MagLIF), achieving up to 2 × 1012 DD neutrons. Our approach,
utilizing adaptive plasma discretization, offers higher energy conversion efficiency (> 50%) and
modularity, addressing scalability challenges inherent in pulsed-power systems like Z Machine.
As shown in the Ragone diagram (Fig. 1.1), our generator outperforms pulsed systems like MagLIF
(Z Machine) in energy density, bridging the gap between large-scale fusion and portable solutions.
Вестник Самарского университета. Естественнонаучная серия 2025. Том 31, № 1. С. 99–117
Vestnik of Samara University. Natural Science Series 2025, vol. 31, no. 1, pp. 99–117 111 из 117
The Ragon´e diagram (Fig. 1.1) illustrates the comparative performance of plasma energy
systems and storage technologies, emphasizing power (W) versus energy density (J/kg). The newly
developed electronically controlled plasma generator, described in this work, is positioned within the
high-efficiency quadrant (>50 % energy conversion), outperforming conventional D-T systems and
compact neutron sources. Key innovations, such as lithium hydride evaporation, quadrupole magnetic
discretization (Patent RU 2757666 [20]), and adaptive ion flux synchronization, enable the generator
to achieve thermal output of 8–25 kW and electrical power of 4–12 kW. These advancements place
the system between fusion prototypes (e. g., ITER) and advanced energy storage solutions (e.g.,
Li-ion batteries) on the diagram (Fig. 1.1), highlighting its modularity and scalability. The inclusion
of experimental setups such as the Kurchatov Tokamak and MIFI-MIST series, alongside emerging
projects (Helion Fusion’s Trenta and TRINITI reactors [31]), underscores the competitive edge of
adaptive plasma discretization in bridging the gap between industrial-scale fusion and portable
energy systems. When installing neutron protection in the case of neutron generator, it makes sense
to use a deuteriumtritium reaction generator on this type, it will be an easy and convenient way to
obtain clean energy.
Existing plasma accelerators are divided into thermal and electromagnetic accelerators, the former
when acceleration is associated with a drop in total pressure and the latter with Ampere force. In these
areas of plasma accelerators, designs are constantly being searched and improved. For example,
new developments in plasma accelerators are presented in [31]. But there is another way to obtain
accelerated dense plasma, presented in this article, which is to obtain plasma of the required energy
from electron and ion plasma components accelerated on separate linear or cyclotron accelerators,
followed by their combination to neutralize and produce a plasma flow.
Methodology confirming the plasma generator’s operability is considered:
50 μm Ti foils fully block alpha particles, ensuring safety in neutron generator designs.
HPGe detectors resolve 8.7 MeV photons with 0.2 % FWHM, critical for distinguishing fusion
signals from p +O/N background.
Future work includes Integration of methodology’s protocols into full-scale reactor trials,
optimizing photon detection algorithms for real-time monitoring.
Recent advances in non-perturbative guiding center theory (Burby et al., 2025 [32]), which
employs machine learning to model high-energy particle dynamics in complex magnetic fields,
highlight the importance of data-driven approaches for improving confinement predictions. These
developments align with our focus on adaptive ion flux synchronization and could further enhance
the accuracy of plasma discretization algorithms in future iterations.

About the authors

A. S. Chipura

Samara State Technical University

Author for correspondence.
Email: al_five@mail.ru
ORCID iD: 0009-0004-0425-0653

assistant professor, Department of Higher Mathematics, Institute
of Automation and Information Technology

Russian Federation, 244, Molodogvardeyskaya Street, 443100, Samara, Russian Federation

M. V. Dolgopolov

Samara State Technical University

Email: mikhaildolgopolov68@gmail.com
ORCID iD: 0000-0002-8725-7831

Candidate of Physical and Mathematical Sciences, associate professor, associate professor of the Department of Higher Mathematics, Institute of Automation and Information Technology

Russian Federation, 244, Molodogvardeyskaya Street, 443100, Samara, Russian Federation

D. E. Ovchinnikov

Samara State Technical University

Email: ovchinnikovde1971@yandex.ru
ORCID iD: 0000-0001-7934-5105

Doctor of Economics, professor, Vice-Rector, Vice-Rector for Academic Affairs

Russian Federation, 244, Molodogvardeyskaya Street, 443100, Samara, Russian Federation

A. V. Radenko

Scientific and Production Company "New Energy" LLC

Email: avradenko@ya.ru
ORCID iD: 0009-0001-0404-2385

chief technologist

Russian Federation, 25/2, Zavodskoye shosse, Samara, 443022, Russian Federation

V. V. Radenko

Scientific and Production Company "New Energy" LLC

Email: tp-aist@mail.ru
ORCID iD: 0009-0008-3353-2667

chief designer

Russian Federation, 25/2, Zavodskoye shosse, Samara, 443022, Russian Federation

References

Supplementary files