Hybrid reactor based on laser thermonuclear fusion

Basov, N G; Belousov, N.I.; Grishunin, P. A.; Kalmykov, Yu.K.; Lebo, I. G.; Розанов, В. Б.; Sklizkov, G. V.; Subbotin, V. I.; Finkel'shteĭn, K I; Харитонов, В. В.; Sherstnev, K. B.

doi:10.1070/qe1987v017n10abeh010765

Cited by 6 publications

(2 citation statements)

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“…Note that even a large-scale asymmetric compression of a target can reduce considerably the neutron output at the LTS. For example, according to [23], the dependence of neutron output on the degree of compression inhomogeneity ζ can be written as follows:…”

Section: Features Of the Image Obtained Through Backlight Imaging Of ...mentioning

confidence: 99%

Diagnostic of ICF target inhomogeneous compression by characteristic X-ray radiography

A.A.

D.S.

Yu.

et al. 2022

Optics and Spectroscopy

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A scheme is considered and the parameters of a multipulse X-ray source for obtaining images of the compressed state of a primary laser thermonuclear target are determined. As an example of a source, we consider the characteristic radiation of an iron secondary target with focusing on it of several picosecond laser pulses of subrelativistic intensity. The proposed technique makes it possible to determine the relative large-scale inhomogeneity of the energy release of laser beams that irradiated the thermonuclear target, based on the results of X-ray diffraction of a compressed thermonuclear target, and to estimate the decrease in the neutron yield caused by the asymmetry of the compressed target. Keywords: picosecond laser plasma, characteristic X-ray radiation, target in laser thermonuclear fusion, iron secondary target, backlighter image.

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Section: Features Of the Image Obtained Through Backlight Imaging Of ...mentioning

confidence: 99%

Diagnostic of ICF target inhomogeneous compression by characteristic X-ray radiography

A.A.

D.S.

Yu.

et al. 2022

Optics and Spectroscopy

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“…Andrei Sakharov originally discussed the concept of fusion driven fission systems in the 1950's [15]. Later, Hans Bethe and Nikolai Basov expanded on his ideas in the 1970's and 1980's, as did many other groups around the world [14,16,17,18]. Although the focus of many of these studies was on the use of fusion neutrons to generate fuel for fast nuclear reactors, Basov as well as Maniscalco also discussed the possibility of using laser-driven fusion targets to drive a fission blanket for generating commercial power.…”

Section: Introductionmentioning

confidence: 99%

Parameter study of the LIFE engine nuclear design

Kramer¹,

Meier²,

Latkowski³

et al. 2010

Energy Conversion and Management

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Please save a copy of this form to your computer, complete and upload as 'Checklist for New Submissions'. Your manuscript will be considered incomplete unless all the below requirements have been met. Please initial each step to confirm.(1) I _Kevin Kramer__{enter name} confirm that the work described has not been published previously (except in the form of an abstract or as part of a published lecture or academic thesis), that it is not under consideration for publication elsewhere, that its publication is approved by all authors and that, if accepted, it will not be published elsewhere in the same form, in English or in any other language, without the written consent of the Publisher.Authors found to be deliberately contravening the submission guidelines on originality and exclusivity shall not be considered for future publication in this journal.(2) The source document is editable, i.e. Word, WordPerfect or Latex _KJK__ {enter initials} AbstractLLNL is developing the nuclear fusion based Laser Inertial Fusion Energy (LIFE) power plant concept. The baseline design uses a depleted uranium (DU) fission fuel blanket with a flowing molten salt coolant (flibe) that also breeds the tritium needed to sustain the fusion energy source. Indirect drive targets, similar to those that will be demonstrated on the National Ignition Facility (NIF), are ignited at ∼13 Hz providing a 500 MW fusion source. The DU is in the form of a uranium oxycarbide kernel in modified TRISO-like fuel particles distributed in a carbon matrix forming 2-cm-diameter pebbles. The thermal power is held at 2000 MW by continuously varying the 6 Li enrichment in the coolants. There are many options to be considered in the engine design including target yield, U-to-C ratio in the fuel, fission blanket thickness, etc. Here we report results of design variations and compare them in terms of various figures of merit such as time to reach a desired burnup, full-power years of operation, time and maximum burnup at power ramp down and the overall balance of plant utilization.

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Power Plant for Heavy-Ion DT Fusion with Targets Containing Fissioning Materials

et al. 2005

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The special features of the concept of a hybrid power-generating plant, which combines the fusion and fission processes in a cylindrical target initiated by a high-power heavy-ion accelerator, are analyzed. The main advantages of the proposed setup are: burning of unenriched 238 U in the reactor cavity, continuous removal of fission products from the core, and impossibility of an uncontrollable nuclear reaction. The characteristics of matched heavy ion accelerator, target, reactor chamber, and blanket with circulating coolant in the blanket are presented, and the power parameters of the electric power plant are estimated.Evolution of the Concept of Hybrid Nuclear Power Systems. Different physical principles for producing energy can be used in nuclear power reactors: fission of actinides, fusion of light elements, or a combination of both of these reactions (hybrid system). In our view, a hybrid nuclear power system will have the highest energy production efficiency. In fission systems, most of the energy is contained in fission products, and the neutrons, although they do initiate this process, make a relatively small contribution to energy release. Conversely, in the DT fusion reaction the neutrons produced carry most of the energy. A combination of the fission and fusion processes in a single system would make it possible to increase substantially the specific power release (per unit mass of nuclear fuel). The fission energy increases the gain of the entire system (ratio of the obtained energy to the energy consumed), which for a prescribed power level decreases the requirements for increasing the power of the thermonuclear target itself. Burning uranium fuel in a hybrid reactor does not require critical parameters, which makes the system much safer. These considerations form the basis for various proposals for the development of hybrid nuclear power systems.In the first hybrid schemes, it was proposed that the thermonuclear reaction can be realized in some way (magnetic confinement, laser or ionic inertial confinement fusion, reaction on Z pinches), and the power of the reaction can be varied over the required limits so that the neutron flux would be controllable and would give the required fission of heavy nuclei in a subcritical assembly.For laser-driven thermonuclear fusion, hybrid schemes were first proposed in [1,2]. The designs of these reactors were studied in [3][4][5]. Specifically, it was shown in [4, 5] that an energy gain ~10 3 can be obtained as a result of fission in

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Hybrid reactor based on laser thermonuclear fusion

Cited by 6 publications

References 1 publication

Diagnostic of ICF target inhomogeneous compression by characteristic X-ray radiography

Diagnostic of ICF target inhomogeneous compression by characteristic X-ray radiography

Parameter study of the LIFE engine nuclear design

Power Plant for Heavy-Ion DT Fusion with Targets Containing Fissioning Materials

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