279 results about "Neutron capture" patented technology

A dc accelerator system able to accelerate high currents of proton beams at high energies is provided. The accelerator system includes a dc high-voltage, high-current power supply, an evacuated ion accelerating tube, a proton ion source, a dipole analyzing magnet and a vacuum pump located in the high-voltage terminal. The high-current, high-energy dc proton beam can be directed to a number of targets depending on the applications such as boron neutron capture therapy BNCT applications, NRA applications, and silicon cleaving.

A method for producing ²²⁹Th includes the steps of providing ²²⁶Ra as a target material, and bombarding the target material with alpha particles, helium-3, or neutrons to form ²²⁹Th. When neutrons are used, the neutrons preferably include an epithermal neutron flux of at least 1×10¹³ n s⁻¹·cm⁻². ²²⁸Ra can also be bombarded with thermal and/or energetic neutrons to result in a neutron capture reaction to form ²²⁹Th. Using ²³⁰Th as a target material, ²²⁹Th can be formed using neutron, gamma ray, proton or deuteron bombardment.

A therapy apparatus for producing thermal neutrons at a tumor site in a patient has a plurality of fast neutron sources surrounding a moderator, a fast neutron reflecting media around the fast neutron sources, a gamma-ray and neutron shielding media surrounding the fast neutron reflecting media, and a patient chamber positioned inside the moderator. The fast neutron sources are positioned around the moderator to maximize and direct the neutron flux to said tumor site.

Moldable neutron sensitive compositions containing an inorganic scintillating component, and neutron capture component, and a moldable resin component, are described. They are prepared with optimized compositions for maximized thermal neutron sensitivity. Methods for preparing such compositions, and articles and radiation detectors made from them are described as well.

A neutron generator and method of using the same to produce commercial and medical isotopes. Isotopes are transmuted using fission spectrum neutrons produced in neutron multiplier alloys proximate a target isotope. The produced neutron fission spectrum is tailored or shaped by alloys disposed between the multiplier alloys and the target isotope. The tailoring alloys selectively convert the neutron fission spectrum to a nearly coherent distribution of selected high energy, fast, epithermal, or thermal neutrons. The tailoring alloys are engineered to slow the fission spectrum neutrons to the resonance energies of the selected target isotopes through scattering or hydriding of selected components of high temperature aluminum alloys that optimize neutron capture in engineered target alloys.

Multimodal nanoparticles are nanoparticles containing contrast agents for PAT and one or more of luminescence imaging, x-ray imaging, and/or MRI. The multimodal nanoparticles can have a dielectric core comprising an oxide with a metal coating on the core. The particles can be metal speckled. The multimodal nanoparticles can be used for therapeutic purposes such as ablation of tumors or by neutron capture in addition to use as contrast agents for imaging.

A neutron radiator for the B-neutron capture therapy in hospital is composed of a reactor and a neutron beam radiating unit. Said reactor consists of a water pool, a sealed stack container in water pool, stack core in said container, a Be ring as neutron reaction layer surrounding said stack core, and a water squeezer outside said Be ring. Said neutron beam radiating unit comprises neutron filter, neutron reflection layer, gamma attenuating cavity, gamma Bi diffuser and LiF neutron collimator. It can be used to treat the cerebral colloma with high stability and safety.

This invention relates to adaptive resistance inhibiting 100 to 10,000 Gy, single fraction proton and carbon ion microbeam and nanobeam radiosurgery, proton spray chemotherapy and proton spray gadolinium and boron neutron capture therapy with least normal tissue toxicity. Secondary neutrons, protons, ions and radiation from the accelerator and the patient specific collimator are removed with tissue equivalent collimator that also generates proton and carbon ion microbeam and nanobeam. Laser interaction with micrometer and nanometer thick metallic and diamond like carbon targets are also used for proton and carbon ion beam generation. Polyenergetic proton beam is spatially separated. Ion beam and Laser ion beam is accelerated in a hybrid RF accelerator. It is split into microbeam and nanobeam. Secondary neutrons, protons and gamma radiation are removed with tissue equivalent collimators that also generate microbeams and nanobeams. Adaptive resistance to cancer treatment is inhibited by dual target radiation, DNA strands break and enzymes inactivation.

The present invention discloses a system and method for estimating absolute elemental concentrations of a subterranean formation from neutron-induced gamma-ray spectroscopy. In one example, a system (10) for estimating an absolute yield of an element in a subterranean formation may include a downhole tool (12) and data processing circuitry (14). The downhole tool may include a neutron source (18) to emit neutrons into the formation, a neutron monitor (20) to detect a count rate of the emitted neutrons, and a gamma-ray detector (26,28) to obtain gamma-ray spectra deriving at least in part from inelastic gamma- rays produced by inelastic scattering events and neutron capture gamma-rays produced by neutron capture events. The data processing circuitry may be configured to determine a relative elemental yield from the gamma-ray spectra and to determine an absolute elemental yield based at least in part on a normalization of the relative elemental yield to the count rate of the emitted neutrons.

The invention provides a formation element capture gamma-ray spectra measurement method and device, and belongs to the technical field of oil-gas exploration logging. The method comprises the steps that a neutron source is slowed down according to the neutron capture cross section of samples to be measured; and standard capture gamma-ray spectra of the samples to be measured can be acquired through measurement when thermal neutron flux of reaction of the neutron source through slowing down and the atomic nucleus of the samples to be measured reaches the position of the preset value. The neutron source is slowed down according to the neutron capture cross section of different samples to be measured so that the element capture gamma-ray spectra of the samples to be measured can be acquired through measurement, and multiple types of formation element capture gamma-ray spectra with higher accuracy can be acquired.

The present invention relates to novel methods for monitoring or tracing a job operation performed in a borehole, such as well boreholes traversing a geological formation. In one embodiment, the novel methods of the invention comprise the steps of: (a) disposing into the borehole a neutron absorber during the performance of the job operation; (b) logging the borehole with an instrument capable of measuring a neutron capture in and around the borehole after performance of the job operation; and (c) monitoring or tracing the job operation performed in the borehole by comparing the measured neutron capture with a baseline neutron capture in and around the borehole. The methods of the present invention pose small or no risk from a health safety and environment perspective and are useful for monitoring or tracing hydraulic fracturing, cementing operation in well boreholes, production logging or subsurface location of downhole collars, float shoes and other jewellery.

The invention relates to a boron carrying agent for integrating tumor diagnosis and treatment. The boron carrying agent is tyrosine boron trifluoride (FBY) obtained by replacing a carboxyl group witha boron trifluoride group on the basis of tyrosine. FBY can be used for boron neutron capture therapy (BNCT) for treating malignant tumors; radioactive <18>F-labeled FBY can also be used for positronemission tomography (PET) imaging diagnosis. <18F>-FBY can simultaneously achieve imaging diagnosis and precise treatment of cancers.

A method for determining at least one formation property calculated from neutron measurements acquired with a downhole tool includes emitting neutrons from a source in the tool into the formation, detecting neutrons with at least one detector in the downhole tool, calculating a first slowing-down length (L₁) based on the detected neutrons, and deriving a second slowing-down length (L₂) based on the first slowing-down length (L₁). Further steps include deriving a correlation function for relating slowing-down lengths from a first tool to slowing-down lengths associated with a different source, wherein the correlation function depends on formation properties such as bulk density; and applying the correlation function to the slowing-down length of the first tool to derive the slowing-down length of the second tool. A method for determining a thermal neutron formation porosity based on a slowing-down length from epithermal neutron measurements from an electronic neutron source includes converting the slowing-down length into a computed neutron slowing-down length from thermal neutron measurements from a chemical neutron source, wherein the converting uses a correlation function that depends on formation bulk density; deriving a thermal neutron countrate ratio based on the computed neutron slowing-down length, wherein the deriving uses a function that depends on the formation bulk density and formation sigma; and computing the thermal neutron formation porosity from the thermal neutron countrate ratio.

The invention features a class of 2-nitroimidazole compounds with a secondary basic nitrogen atom and a linker bearing one or more therapeutic agents, cytotoxic agents, detectable labels, or chelating groups. In particular, the invention provides 2-nitroimidazole compounds containing a cluster of boron atoms for use in boron neutron capture therapy (BNCT). The 2-nitroimidazole compounds can be used to treat hypoxic conditions, including, e.g., cancer, inflammation, and ischemia. The weakly basic 2-nitroimidazole compounds target to hypoxic tissue and provide increased tissue concentration overall.

A neutron scintillator composed of a resin composition comprising (A) an inorganic phosphor containing at least one neutron capture isotope selected from lithium 6 and boron 10 and (B) a resin, wherein

• • the inorganic phosphor is a particle having a specific surface area of 50 to 3,000 cm²/cm³, and the internal transmittance based on 1 cm of the optical path length of the resin composition is 30%/cm or more at the emission wavelength of the inorganic phosphor.

The present invention discloses boronic acids and esters of phospholipid ether analogs and methods for their synthesis and use. The boronic acids and esters of phospholipid ether analogs described herein can be used in treating cancer and in particular can be used in conjunction with radiation therapy, such as external beam radiation therapy and neutron capture therapy to specifically target and kill cancer cells.

A water Cerenkov-based neutron and high energy gamma ray detector and radiation portal monitoring system using water doped with a Gadolinium (Gd)-based compound as the Cerenkov radiator. An optically opaque enclosure is provided surrounding a detection chamber filled with the Cerenkov radiator, and photomultipliers are optically connected to the detect Cerenkov radiation generated by the Cerenkov radiator from incident high energy gamma rays or gamma rays induced by neutron capture on the Gd of incident neutrons from a fission source. The PMT signals are then used to determine time correlations indicative of neutron multiplicity events characteristic of a fission source.

The invention discloses a small high-yield and deuterium-deuterium neutron generator. Modular distributed high-frequency ion sources are adopted and evenly distributed on the outer surface of a ceramic cylinder with the spherical end, and deuterium ion beams distributed evenly are output, wherein the flow intensity of the deuterium ion beams is larger than 1 A, and the single atom proportion is larger than 80%; the deuterium ion beams are accelerated in a cylindrical accelerating electric field with the spherical end and bombard a cylindrical metal or ceramic self-forming target to cause a deuterium/deuterium reaction and then generate neutrons of 2.45 MeV, and the self-forming target is located at the high-potential end and provided with the spherical end. The number of the modular distributed high-frequency ion sources and the area of the self-forming target are not limited, the yield of the neutrons of the deuterium/deuterium reaction is larger than 1011 n/s, and no radioactive pollutants are discharged. The neutron generator is suitable for commercialized application such as the fields of boron neutron capture treatment, neutron radiography, on-line material component neutron detection, neutron irradiation modification and californium neutron source substitute products.

The invention provides a neutron capture therapy device which is capable of improving reliability of a boron neutron capture therapy. The neutron capture therapy device (1) in the invention is radiates neutron beams onto a object to be radiated (M), and boron in the radiated object (M) is enabled to react with the neutrons. The neutron capture therapy device (1) has a neutron beam radiating part (4) used for radiating the neutron beams (N) onto the object to be radiated (M) and a boron concentration measuring part (32) used for measuring in real time the concentration of boron in the object to be radiated (M) when the neutron beam radiating part (4) radiates the neutron beams (N).