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This Defense Intelligence Reference Document, dated 10 March 2010, was prepared by the Defense Intelligence Agency's Defense Warning Office under the Advanced Aerospace Weapon System Applications Program. It surveys the basics, experimental status, theory and possible uses of inertial electrostatic confinement (IEC) fusion, with emphasis on work at the University of Illinois Urbana-Champaign. It covers neutron sources, explosives detection and space propulsion. It ends by proposing a 12-gun hydrogen plasma experiment meant to show breakeven conditions for p-11B fuel.
From the source:Release of 2026-09-18 Incident: 3/10/10, Las Vegas, Nevada. Released with redactions. This document is a Defense Intelligence Reference Document (DIRD), a technical reference format used by the Defense Intelligence Agency (DIA) to capture baseline knowledge on a specific topic for later analytic use. DIRDs are best understood as reference and synthesis products rather than as original research. It is one of 38 DIRDs produced under the Advanced Aerospace Weapon System Applications Program (AAWSAP) between 2009 and 2011. Because AAWSAP’s scope permitted a broad range of supporting topics, not every DIRD in the series directly concerns aerospace systems or future threat assessment. The following summary reflects the DIRD’s scope and framing at the time of writing and should not be read as implying current validation of the concepts discussed. This DIRD surveys inertial electrostatic confinement (IEC) fusion, a relatively unconventional fusion concept that uses electric fields rather than the more established magnetic or laser-based approaches to confine ions, and it reviews both the underlying physics and the experimental work associated with the concept. The report emphasizes that IEC may have nearer-term value as a compact neutron, proton, or x-ray source and as a platform for studying experimental fusion approaches, while also presenting more ambitious possibilities such as aneutronic power generation and propulsion applications. At the same time, it makes clear that the concept remained far from practical fusion power, with experimental devices operating several orders of magnitude below breakeven and with major unresolved issues involving confinement, losses, grid damage, and scale-up. Overall, the document treats IEC as a technically interesting but still highly speculative path toward fusion energy, while suggesting that its more limited spin-off applications were more plausible in the near term than its long-range power generation or propulsion applications.
“Expedition X”1 page
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Table 5.2. Comparison of IEC Design and Magnetic Fusion Design
Pu ionShipI r'U ion hi pII pherical Tokamak
0 emll Mass Metric T 500 500 1690
0 emJI Length (m 174 00 240
umber of crew JO 10 6- 12
Thro I P wer (MW) 750 48 0
Rea tor gain 4 9 7
Rea tor power (MW) 21 217 7895
Thrust y t m Krypt n ion Arg n ion H1 - magnetic nozzle
pecific impul I 000 ,000 5,435
Jupiter ne way trip time (day' 400 210 118
The design of Space Ship II uses "coupled" IEC reactors that use magnetic guide
channels. This concept, termed the Magnetically-Channeled Spherical IEC Array (MCSA)
concept is briefly discussed next (Reference 5.3).
MAGNETICALLY- CHANNELED SPHERICAL IEC ARRAY {MCSA)
CONCEPT
The Magnetically-Channeled Spherical IEC Array (MCSA) concept for a hybrid magnetic
assisted spherical IEC configuration maintains the basic ion-injected IEC reactor
configuration but adds magnetic channels for coupling exhaust plasma and reaction
products. The MCSA is illustrated conceptually in Figure 5.7. The SIEC is confined in a
hexapole field configuration is qu ite different from the hexapole field used in R.W.
Bussard's Polywell. It is in turn located in a field channel (Bz field) created by a column
of Helmholtz coils. The field strengths of these coil sets is adjusted such that the fields
cancel in the center of the IEC, giving a larger field null region compared to that in a
cusp confined field . The MCSA configuration reta ins t he advantage of stability due to
good field curvature obtai ned in a cusp. In addition, it also effectively closes the "belt"
loss cone. As shown later, leakage in that direction is led around the hexapole coils and
back into the confinement region, termed here as "recirculation." Losses include
scattering into the spinda l loss cone along the z-axis and stochastic scattering due to
the violation of adiabatic invariance in the field null region. However, with the present
channel configuration, the axial losses from one IEC configuration enter a neighboring
unit. Thus, as they pass through the field null reg ion in that unit, stochastic scattering
leads to "retrapping" of much of this flow. Experimental verification of this "retrapping"
is then a second physics Proof-of-Principle (POP) objective. In this fash ion, an array of
multiple IECs increase the overall confinement time roughly in proportion to the number
of units. In operation, electrons would be magnetically confined as described, providing
electrostatic confinement of ions injected into the Spherical IEC region. An additional
benefit of this configuration is that in a reactor embodiment, both leaking fuel plasma
and energetic charged fusion products (e.g. the 14- MeV proton from D- 3He), can be
collimated and aimed into a direct energy converter such as a TWDEC (Reference 5.4) .
This results in a high overall energy conversion efficiency. Alternately, for space
propulsion, the proton beam, augmented by injection of heavy atoms to increase the
flow mass, can be directly exhausted for thrust.
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