I believe this is what it is all about:
https://patentscope.wipo.int/s…tring=&tab=PCTDescription
[011] Recently, Boss (Boss, et al, "Triple Tracks in CR-39 as the result of Pd-D Co-deposition: evidence of energetic neutrons", Naturwissenschaften, (2009) VoI 96:135-142) documented the production of deuterium-deuterium (2.45 MeV) and deuterium-tritium (14.1 MeV) fusion neutrons using palladium co-deposition on non-hydriding metals. These energetic neutrons were observed and spectrally resolved using solid state detectors identical to those routinely used in the ICF (DoE lnertial Confinement Fusion program) experiments (Seguin, FH, et al. "Spectrometry of charged particles from inertial-confinement-fusion plasmas" Rev Sci Instrum. 74:975-995. (2003).
[012] Boss, et al, filed U.S. Provisional Patent Application Serial No. 60/919,190, on March 14, 2007, entitled "Method and Apparatus for Generating Particles", which is incorporated by reference in its entirety and Serial No. 11/859,499, ['499] "System and Method for Generating Particles", filed on September, 21 , 2007, which is incorporated by reference in its entirety. Although that patent teaches a method to generate neutrons and describes in general terms their use, this embodiment teaches another means to fast fission a natural abundance uranium deuteride fuel element driven by DD primary and secondary fusion neutrons within said fuel element. Consequently, a heavily deuterided actinide can be its own source of fast neutrons, with an average neutron kinetic energy greater than 2 MeV and greater than the actinide fission neutron energy. Such energetic neutrons are capable of fissioning both fertile and fissile material. There is no chain reaction. There is no concept of actinide criticality. Purely fertile material, like 232Th or non-fertile isotopes, like 209Bi, may fission producing additional fast neutrons and energy up to 200 MeV/nucleon fissioned.
[013] This results in considerable environmental, health physics, and economic savings by using either spent nuclear fuel, mixed oxide nuclear fuel, natural uranium or natural thorium to "stoke the fires of a nuclear furnace" and is the basis for our Green Nuclear Energy technology, or GNE (pronounced, "Genie"). GNE reactors may consume fertile or fissionable isotopes such as 232Th, 235U, 238U, 239Pu, 241Am, and 252Cf, and may consume fission wastes and activation products in situ without requiring fuel
reprocessing. GNE reactors may consume spent fuel rods without either mechanical processing or chemical reprocessing. In this regard, GNE reactor technology may be an improvement over proposed Generation IV fission reactor technologies
(http://nuclear.enerqv.aov/aenlV/neGenlV1.htmh under development.
GNE may: improve safety (no chain reaction), burn actinides (reduced waste) and provide compatibility with current heat exchanger technology (existing infrastructure). By employing a novel, in situ, very fast neutron source, GNE constitutes a new Generation V hybrid reactor technology, combining aspects of Generation IV fast fission reactors, the DoE Advanced Accelerator reactor, and hybrid fusion/fission systems. It may eliminate the need for uranium enrichment and fuel reprocessing and, consequently, the opportunity for nuclear weapons proliferation through the diversion of fissile isotopes
