Fusion-Power-Core Design of a Compact Reversed-Field Pinch Reactor (CRFPR)

Copenhaver, C.; Schnurr, N.M.; Krakowski, R.A.; Hagenson, R.L.; Mynard, R. C.; Cappiello, C.; Lujan, R.E.; Davidson, John; Chaffee, A. D.; Battat, M.E.

doi:10.13182/fst85-a39987

Cited by 3 publications

(3 citation statements)

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“…(2) Tokamaks and tandem mirrors are considered as the primary confinement concepts. Changes in R&D for reversed field pinches (RFPs) [5] need further evaluation. (3) Representative ranges for key parameters of commercial fusion reactors [6][7][8] are shown in Table 1.…”

Section: Goals Objectives and Assumptionsmentioning

confidence: 99%

“…A full blanket module test would need about 1 m 3 of test volume, require extensive modifications to any operating fission reactor core, and still only achieve the equivalent of (at most) a 1 MW-m" 2 heating rate in any existing reactor. In-core assemblies could be placed in existing fission reactors like FFTF at reactor relevant heating rates (2)(3)(4)(5) ), but would be limited to about 10 cm diameter. Such test assemblies could provide fairly realistic simulation of many fusion conditions, with complete coolant and purge flow systems and instrumentation.…”

Section: Tritium Permeation and Processing Experimentsmentioning

confidence: 99%

“…(1) measure the thermophysical properties of materials for which the database is poor, such as Be, and of advanced graphites and novel coatings produced by plasma spray; (2) evaluate brazing and bonding techniques; (3) study critical heat flux onset and augment heat transfer techniques; ( 4) study melt layer formation and stability in disruption simulations; (5) test the heat removal capacity of coolant systems designed for use in PIC applications; and ( 6) study coolant channel erosion caused by flow cavitation and coolant impurities. While these tests are necessary and provide valuable information, they all fall into the category of single effects testing.…”

Section: High Heat Flux Testingmentioning

confidence: 99%

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Technical issues and requirements of experiments and facilities for fusion nuclear technology

et al. 1987

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The technical issues, development problems and required experiments and facilities for fusion nuclear technology have been investigated. The results have been used to develop a technical framework for a test plan that identifies the role, timing, characteristics and costs of major experiments and facilities. A major feature of this framework is the utilization of non-fusion facilities over the next 15 years, followed by testing in fusion devices beyond about the year 2000. Basic, separate effect and multiple interaction experiments in non-fusion facilities will provide property data, explore phenomena and provide input to theory and analytic modelling. Experiments in fusion facilities can proceed in two phases: (1) concept verification and (2) component reliability growth. Integrated testing imposes certain requirements on fusion testing device parameters; these requirements have been quantified. The nuclear subsystems addressed in the study are: (a) blanket and first wall; (b) tritium processing system; (c) plasma interactive components; and (d) radiation shield. The two generic classes of liquid and solid breeder blankets have significant engineering feasibility issues, and new experimental data must be obtained before selection of an attractive design concept. Liquid metal blanket issues are dominated by problems related to momentum, heat and mass transfer, which can be addressed in non-neutron test facilities. Solid breeder blanket issues are, however, dominated by the effects of radiation, including heating, transmutation and damage, which can be reasonably addressed in fission reactors. The tritium processing uncertainties are primarily related to the control and recovery systems, and most can be addressed in existing and planned non-neutron facilities. A dominant feature of plasma interactive components is the strong interrelation to both plasma physics and nuclear technology. Required facilities include thermomechanical test stands and confinement devices with sufficiently long plasma burn. The radiation shield poses no feasibility issues, but improved accuracy of predictions will reduce design conservatism and lower costs.

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Section: Goals Objectives and Assumptionsmentioning

confidence: 99%

Section: Tritium Permeation and Processing Experimentsmentioning

confidence: 99%

Section: High Heat Flux Testingmentioning

confidence: 99%

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Technical issues and requirements of experiments and facilities for fusion nuclear technology

et al. 1987

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Compact reversed-field pinch reactors (CRFPR)

Krakowski

Hagenson

Schnurr

et al. 1986

Nuclear Engineering and Design. Fusion

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A major purpose of the Technical Information Center is to provide the broadest dissemination possible of information contained in DOE'S Research and Development Reports to business, industry, the academic community, and federal, state and local governments. Although a small portion of this report is not reproducible, it is being made available to expedite the availability of information on the research discussed herein.

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