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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.
Figure 5.6. Scale Schematic of Fusion Ship II, a 750-MWe IEC Fusion Spacecraft UNCLASSIFIED/ /FOA OFFI&iIAk Wli& ONkY valuable fuels, especially t he 3 He. The ion thrusters run on Argon propellant at a specific impulse of 35,000 sec and an efficiency of 90 percent. The thrust is produced 4370 Newtons, probably an initia l acceleration of .0087 m/s 2. A typical trip time for an out-and-back mission to Jupiter is 210 days out and 153 days to return. This is comparable to or faster than that predicted in prior fusion studies. B • vi w The initial spaceship mass at mission is 500 metric tons start; 222 metric tons are the Argon propellant needed for a Jupiter round trip with /:::,,.V of 220 km/s. The IEC reactor, direct energy converters and ion thrusters contribute 178 metric tons. The remaining 100 metric tons includes 20 metric tons for the crew areas, 15 metric tons for the electronics/computers, 20 metric tons for food and life support, 15 tons for crew shielding and 1.2 metric tons for the antenna. Inclusion of a contingency of 30 percent of the dry mass adds 60 metric tons and provides a 30-day "safety factor" to the round trip flight time. Human factors have not been fully evaluated in this design, but are thought to be acceptable with the short mission time achieved. Fusion Ship II would be one of the largest propelled vehicles ever built, although its mass would be ¼ that of the Space Shuttle at liftoff. Table 5.2 compares IEC Fusion Ship I and II designs with a concept based on an "advanced" spherical Tokamak reactor "scaled up" from t he spherical Tokamak experiment at Princeton's Plasma Physics Laboratory as reported in an NASA-GLENN Laboratory study in 2001. The Tokama k has a shorter trip time by employing a power level that is six times the IEC units. Further, it is designed for D-T use (D- 3He is difficult to burn in such Tokomaks), but tritium handling, radiation damage, and radioactivity Issues are not addressed. Thus, if the IEC and Tokamak were compared on the same operational basis (i.e., same fuels and power levels), the IEC would clearly show a distinct advantage. Note that this is even true with the Tokamak using a very "advanced" conceptual design well beyond reach of ITER (originally International Thermonuclear Experimental Reactor) technology. UNCLASSIFIED/ /FOR OFFIEiIAk lel&& 0Nk¥ 55
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Official release, from the pursue collection. The PDF is mirrored here; the original link is above. 72 pages are in the text index: search them above, or from the library's search.