Fusion reactors blanket nucleonics

Greenspan, E.

doi:10.1016/0149-1970(86)90042-9

Cited by 7 publications

(2 citation statements)

References 61 publications

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“…Therefore, the transmutation of nuclear wastes has become an international hotspot issue [1,2]. Using a high-energy neutron spectrum, the nuclear wastes can be transmuted to light elements (isotopes) with much shorter half-lives [3]. Transmutation of long-lived Actinides is one of the most attractive capabilities of a fast neutron and is being investigated in many studies for different types of reactors.…”

Section: Introductionmentioning

confidence: 99%

Transmutation Investigation of a Typical VVER-1000 Reactor Burnup Products to less Toxicity Isotopes in a Fusion-Fission Hybrid Reactor

Sendesi

Ghasemizad

2021

Politeknik Dergisi

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Section: Introductionmentioning

confidence: 99%

Transmutation Investigation of a Typical VVER-1000 Reactor Burnup Products to less Toxicity Isotopes in a Fusion-Fission Hybrid Reactor

Sendesi

Ghasemizad

2021

Politeknik Dergisi

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“…The focus of many of these studies was on the use of fusion neutrons to generate fuel for fast nuclear reactors, although Basov and others discussed the possibility of using laser-driven fusion targets to drive a fission blanket for generating commercial power. In addition, Greenspan and his colleagues suggested the idea of combining the benefits of fusion and fission to generate nuclear energy without enrichment and without solid fission products separation [29,30,31,32]. Unfortunately, fusion-fission engines never advanced beyond the discussion stage mainly because powerful high-average-power lasers and other required technologies did not exist.…”

Section: Scope and Purpose Of Current Studymentioning

confidence: 99%

Laser Intertial Fusion Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System

Kramer¹

2010

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This study investigates the neutronics design aspects of a hybrid fusion-fission energy system called the Laser Fusion-Fission Hybrid (LFFH). A LFFH combines current Laser Inertial Confinement fusion technology with that of advanced fission reactor technology to produce a system that eliminates many of the negative aspects of pure fusion or pure fission systems. When examining the LFFH energy mission, a significant portion of the United States and world energy production could be supplied by LFFH plants.The LFFH engine described utilizes a central fusion chamber surrounded by multiple layers of multiplying and moderating media. These layers, or blankets, include coolant plenums, a beryllium (Be) multiplier layer, a fertile fission blanket and a graphite-pebble reflector. Each layer is separated by perforated oxide dispersion strengthened (ODS) ferritic steel walls. The central fusion chamber is surrounded by an ODS ferritic steel first wall. The first wall is coated with 250-500 µm of tungsten to mitigate x-ray damage. The first wall is cooled by Li 17 Pb 83 eutectic, chosen for its neutron multiplication and good heat transfer properties. The Li 17 Pb 83 flows in a jacket around the first wall to an extraction plenum. The main coolant injection plenum is immediately behind the Li 17 Pb 83 , separated from the Li 17 Pb 83 by a solid ODS wall. This main system coolant is the molten salt flibe (2LiF-BeF 2 ), chosen for beneficial neutronics and heat transfer properties. The use of flibe enables both fusion fuel production (tritium) and neutron moderation and multiplication for the fission blanket. A Be pebble (1 cm diameter) multiplier layer surrounds the coolant injection plenum and the coolant flows radially through perforated walls across the bed. Outside the Be layer, a fission fuel layer comprised of depleted uranium contained in Tristructural-isotropic (TRISO) fuel particles having a packing fraction of 20% in 2 cm 1 diameter fuel pebbles. The fission blanket is cooled by the same radial flibe flow that travels through perforated ODS walls to the reflector blanket. This reflector blanket is 75 cm thick comprised of 2 cm diameter graphite pebbles cooled by flibe. The flibe extraction plenum surrounds the reflector bed. Detailed neutronics designs studies are performed to arrive at the described design.The LFFH engine thermal power is controlled using a technique of adjusting the 6 Li/ 7 Li enrichment in the primary and secondary coolants. The enrichment adjusts system thermal power in the design by increasing tritium production while reducing fission. To perform the simulations and design of the LFFH engine, a new software program named LFFH Nuclear Control (LNC) was developed in C++ to extend the functionality of existing neutron transport and depletion software programs. Neutron transport calculations are performed with MCNP5. Depletion calculations are performed using Monteburns 2.0, which utilizes ORIGEN 2.0 and MCNP5 to perform a burnup calculation. LNC supports many design parameters and is capable of p...

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Minimum thickness blanket-shield for fusion reactors

Karni¹,

Greenspan

1989

Fusion Engineering and Design

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Fusion reactors blanket nucleonics

Cited by 7 publications

References 61 publications

Transmutation Investigation of a Typical VVER-1000 Reactor Burnup Products to less Toxicity Isotopes in a Fusion-Fission Hybrid Reactor

Transmutation Investigation of a Typical VVER-1000 Reactor Burnup Products to less Toxicity Isotopes in a Fusion-Fission Hybrid Reactor

Laser Intertial Fusion Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System

Minimum thickness blanket-shield for fusion reactors

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