A Compact Neutron Generator for the Niort® Treatment of Severe Solid Cancers

In the last four years, TheranostiCentre S.r.l , Berkion Technology LLC and ENEA have patented and fabricated a first prototype of a Compact Neutron Generator (CNG) currently under testing in the ENEA laboratories. Besides the usual applications in the field of materials irradiation, this CNG - producing neutrons of 2.45 MeV energy through the deuterium-deuterium (DD) fusion reaction - was conceived for the neutron irradiation of the solid cancer’s tumour bed by means of the Intra-Operative Radiotherapy (IORT) technique, the so-called neutron-IORT (nIORT®). The DD-CNG is self-shielded and light-weight (~120 kg) making possible its remote handling by a robotic arm. Accurate Monte Carlo simulations, modelling the CNG and the “open wound” biological tissues near its irradiation window, demonstrated that the apparatus operated at 100 kV-10 mA supplies a neutron flux ~108 cm-2 s-1 and can deliver equivalent dose rates ~2 Gy (RBE)/min. Hence, it can administer very high dose levels in limited treatment times. This article briefly summarizes the main findings of this collaborative research study, the clinical rationales underpinning the nIORT® idea and the potential performances of the DD-CNG for the treatment of solid cancer pathologies. Indeed, the CNG can be installed in an operating room dedicated to nIORT® treatments, without posing any environmental and safety issues. Monte Carlo simulations have been carried out by envisioning the CNG equipped with an IORT applicator, that is an applicator pipe with a tuneable diameter to be inserted in the surgical cavity. By foreseeing the clinical endpoints of the standard IORT protocols, the irradiation performances for potential nIORT® treatments - obtained with an applicator pipe of 6 cm diameter - are here reported for different regimes: from 10 up to 75 Gy (RBE), that can be administered in a single session of about 4 to 30 minutes. Besides the dose peak in the centre of the tumour bed, the almost isotropic neutrons emission allows to irradiate its surroundings side-walls – usually filled by potential quiescent cancer cells – and therefore reducing the chances of local recurrences by improving the local control of the tumour. The rapid decrease in tissues depth of the dose profile (in few centimetres) will spare the neighbouring organs at risk from harmful radiations. Thus, the DD-CNG apparatus developed for nIORT® applications can potentially improve the resectability rate of a given neoadjuvant cancer treatment and, generally, could satisfy all five R’s criteria of radiotherapy. Furthermore, in comparing with the current IORT techniques with electrons or low-keV Xrays, the nIORT® exploiting a high-flux neutrons beam of 2.45 MeV energy could lead to some significant clinical advantages due to its high linear energy transfer (~ 40 keV/mm as average) and significantly higher relative biological effectiveness (@16) than all other forms of ionizing radiation

Ion source for neutral beam injection meant for plasma and magnetic field diagnostics

At the Lawrence Berkeley National Laboratory (LBNL) a diagnostic neutral beam injection system for measuring plasma parameters, flow velocity, and local magnetic field is being developed. The systems is designed to have a 90 % proton fraction and small divergence with beam current at 5-6 A and a pulse length of {approx}1 s occurring once every 1-2 min. The ion source needs to generate uniform plasma over a large (8 cm x 5 cm) extraction area. For this application, we have compared RF driven multicusp ion sources operating with either an external or an internal antenna in similar ion source geometry. The ion beam will be made of an array of six sheet-shaped beamlets. The design is optimized using computer simulation programs

Highly Compact Accelerator-Driven Subcritical Assembly for Medical and Industrial Applications

Highly Compact Accelerator-Driven Subcritical Assembly for Medical and Industrial Application

Characteristics of a RF-Driven Ion Source for a Neutron Generator Used For Associated Particle Imaging

We present recent work on a prototype compact neutron generator for associated particle imaging (API). API uses alpha particles that are produced simultaneously with neutrons in the deuterium-tritium (2D(3T,n)4 alpha) fusion reaction to determine the direction of the neutrons upon exiting the reaction. This method determines the spatial position of each neutron interaction and requires the neutrons to be generated from a small spot in order to achieve high spatial resolution. The ion source for API is designed to produce a focused ion beam with a beam spot diameter of 1-mm or less on the target. We use an axial type neutron generator with a predicted neutron yield of 108 n/s for a 50 muA D/T ion beam current accelerated to 80 kV. The generator utilizes a RF planar spiral antenna at 13.56 MHz to create a highly efficient inductively-coupled plasma at the ion source. Experimental results show that beams with an atomic ion fraction of over 80percent can be obtained while utilizing only 100 watts of RF power in the ion source. A single acceleration gap with a secondary electron suppression electrode is used in the tube. Experimental results, such as the current density, atomic ion fraction, electron temperature, and electron density, from ion source testing will be discussed

Measurement of actinide neutron cross sections

The maintenance of strong scientific expertise is criticalto the U.S. nuclear attribution community. It is particularly importantto train students in actinide chemistry and physics. Neutroncross-section data are vital components to strategies for detectingexplosives and fissile materials, and these measurements requireexpertise in chemical separations, actinide target preparation, nuclearspectroscopy, and analytical chemistry. At the University of California,Berkeley and the Lawrence Berkeley National Laboratory we have trainedstudents in actinide chemistry for many years. LBNL is a leader innuclear data and has published the Table of Isotopes for over 60 years.Recently, LBNL led an international collaboration to measure thermalneutron capture radiative cross sections and prepared the EvaluatedGamma-ray Activation File (EGAF) in collaboration with the IAEA. Thisfile of 35,000 prompt and delayed gamma ray cross-sections for allelements from Z=1-92 is essential for the neutron interrogation ofnuclear materials. LBNL has also developed new, high flux neutrongenerators and recently opened a 1010 n/s D+D neutron generatorexperimental facility

ADVANCED NEUTRON GENERATOR FOR SNM IMAGING

Report about the Advanced Neutron Generator for SNM Imaging

Prompt gamma activation analysis (PGAA) and short-lived neutron activation analysis (NAA) applied to the characterization of legacy materials

Without quality historical records that provide the composition of legacy materials, the elemental and/or chemical characterization of such materials requires a manual analytical strategy that may expose the analyst to unknown toxicological hazards. In addition, much of the existing legacy inventory also incorporates radioactivity, and, although radiological composition may be determined by various nuclear-analytical methods, most importantly, gamma-spectroscopy, current methods of chemical characterization still require direct sample manipulation, thereby presenting special problems with broad implications for both the analyst and the environment. Alternately, prompt gamma activation analysis (PGAA) provides a'single-shot' in-situ, non-destructive method that provides a complete assay of all major entrained elemental constituents.1-3. Additionally, neutron activation analysis (NAA) using short-lived activation products complements PGAA and is especially useful when NAA activation surpasses the PGAA in elemental sensitivity

Design, construction, and characterization of a compact DD neutron generator designed for 40Ar/39Ar geochronology

A next-generation, high-flux DD neutron generator has been designed, commissioned, and characterized, and is now operational in a new facility at the University of California Berkeley. The generator, originally designed for 40Ar/39Ar dating of geological materials, has since served numerous additional applications, including medical isotope production studies, with others planned for the near future. In this work, we present an overview of the High Flux Neutron Generator (HFNG) which includes a variety of simulations, analytical models, and experimental validation of results. Extensive analysis was performed in order to characterize the neutron yield, flux, and energy distribution at specific locations where samples may be loaded for irradiation. A notable design feature of the HFNG is the possibility for sample irradiation internal to the cathode, just 8 mm away from the neutron production site, thus maximizing the neutron flux (n/cm2/s). The generator's maximum neutron flux at this irradiation position is 2.58e7 n/cm2/s +/- 5% (approximately 3e8 n/s total yield) as measured via activation of small natural indium foils. However, future development is aimed at achieving an order of magnitude increase in flux. Additionally, the deuterium ion beam optics were optimized by simulations for various extraction configurations in order to achieve a uniform neutron flux distribution and an acceptable heat load. Finally, experiments were performed in order to benchmark the modeling and characterization of the HFNG.Comment: 31 pages, 20 figure

Robust estimation of bacterial cell count from optical density

Optical density (OD) is widely used to estimate the density of cells in liquid culture, but cannot be compared between instruments without a standardized calibration protocol and is challenging to relate to actual cell count. We address this with an interlaboratory study comparing three simple, low-cost, and highly accessible OD calibration protocols across 244 laboratories, applied to eight strains of constitutive GFP-expressing E. coli. Based on our results, we recommend calibrating OD to estimated cell count using serial dilution of silica microspheres, which produces highly precise calibration (95.5% of residuals <1.2-fold), is easily assessed for quality control, also assesses instrument effective linear range, and can be combined with fluorescence calibration to obtain units of Molecules of Equivalent Fluorescein (MEFL) per cell, allowing direct comparison and data fusion with flow cytometry measurements: in our study, fluorescence per cell measurements showed only a 1.07-fold mean difference between plate reader and flow cytometry data