38results about "Neutron capture therapy" patented technology

Stable isotope labeling and neutron activation to measure biological functions are provided, as are the use and method of adding a chemical monitor to correct for neutron flux to sample vials prior to the addition of sample is presented, and the use of stable isotopes as a chemical bar code for vials and other items. Methods are provided also for measuring glomerular filtration rate and glomerular sieving function in a subject, and for measuring other physiological functions.

The present invention discloses a methodology for the characterization and determination of mixed-field dosimetry for 252Cf Applicator Tube (AT)-type medical sources, utilizing ionization chambers, GM counters, and Monte Carlo methods. Unlike the previous methodologies, the present invention discloses a specification of dose to muscle, rather than dose to water, for clinical dosimetry of 252Cf medical sources. A dosimetry protocol, similar to that utilized for ICRU-45, with parameters determined specifically for 252Cf brachytherapy is disclosed. Neutron isodose distributions and data necessary for clinical implementation of 252Cf AT sources are also disclosed herein. Additionally, novel methods for the encapsulation, storage, and delivery / implantation of 252Cf radionuclide sources are disclosed.

Described is a method of using gadolinium-containing compounds as agents for neutron capture therapy to treat neoplastic cell growth. The subject is exposed to a gadolinium-containing compound for a time sufficient to allow the compound to accumulate in neoplastic cells. The subject is then exposed to a thermal and / or epithermal neutron flux, thereby initiating a neutron capture reaction in the gadolinium atoms that results in specific death of neoplastic cells.

The invention relates to an amphiphilic graphene-gold thermal radiotherapy nano drug which comprises amphiphilic graphene, nano gold particles loaded on the surface of amphiphilic graphene, and tumor targeted molecules connected on amphiphilic graphene. The invention also provides a preparation method of the amphiphilic graphene-gold thermal radiotherapy nano drug, which comprises the following steps: modified diisocyanate on the surface of graphene oxide, and then adding a polymer containing carboxyl to enable carboxyl to react with diisocyanate, so as to obtain amphiphilic graphene; carrying out in-situ growth of gold nano particles on the surface of amphiphilic graphene; and finally, adding tumor targeted molecules containing amino groups and coupling agents into the product to enable the tumor targeted molecules containing amino groups to react with carboxyl of amphiphilic graphene, so as to obtain the amphiphilic graphene-gold thermal radiotherapy nano drug. The invention also provides the application of the amphiphilic graphene-gold thermal radiotherapy nano drug serving as an anti-tumor drug. The prepared nano drug can be compounded with protons / neutrons for treating through thermal therapy and has a relatively strong killing effect on tumor cells.

A neutron capture therapy system capable of eliminating amyloid β-protein includes a neutron capture therapy device and a compound capable of specifically binding to the amyloid β-protein having a nuclide with a large thermal neutron capture cross section. The neutron capture therapy device includes a neutron source, a beam shaping assembly and a collimator, the neutrons released by the neutron source pass through the beam shaping assembly and are slowed into a neutron beam within a certain energy range. The neutron beam irradiates the compound, and the energy generated by the reaction thereof can destroy the structure of the amyloid β-protein. The neutron capture therapy system can specifically eliminate the amyloid β-protein, and reduce the damage to the tissues surrounding the amyloid β-protein.

An irradiation method and system for irradiating a target volume, the method comprising: providing thermal neutron absorbing nuclides (such as in the form of a high neutron cross-section agent) at thetarget volume; and producing neutrons by irradiating nuclei in or adjacent to the target volume with a beam of particles consisting of any one or more of protons, deuterons, tritons and heavy ions, thereby prompting production of the neutrons through non-elastic collisions between the atoms in the path of the beam (including the target) and the particles. The neutron absorbing nuclides absorb neutrons produced in the non-elastic collisions, thereby producing capture products or fragments that irradiate the target volume.

Improved method and apparatus for neutron capture therapy are disclosed, which may beneficially be used to counteract restenosis. An improved stent and a method for manufacturing the stent are also presented. The stent comprises a stable nuclide having a large neutron capture cross-section. When a clinical need exists for radiation therapy, the stent is irradiated with thermal neutrons, thereby giving rise to radiation in the proximity of the stent to a therapeutic benefit. Since radiation is applied by an external source, it can be delivered at any time after placement of the stent and easily can be repeated. The stent only contains stable nuclides and therefore can be handled without the precautions needed when handling radioactive matter.

A process for treating highly localized carcinoma cells that provides precise positioning of a therapeutic source of highly ionizing but weakly penetrating radiation, which can be shaped so that it irradiates essentially only the volume of the tumor. The intensity and duration of the radiation produced by the source can be activated and deactivated by controlling the neutron flux generated by an array of electrically controlled neutron generators positioned outside the body being treated. The energy of the neutrons that interact with the source element can be adjusted to optimize the reaction rate of the ionized radiation production by utilizing neutron moderating material between the neutron generator array and the body. The source device may be left in place and reactivated as needed to ensure the tumor is eradicated without exposing the patient to any additional radiation between treatments. The source device may be removed once treatment is completed.

Systems and methods including a material that emits high energy beta particles to destroy cancer cells contained in cancerous tumor or tissue. Electronic neutron generators produce neutrons with energies that have a high probability to interact with the material yttrium-89 to produce yttrium-90. Yttrium-90 emits beta radiation with a maximum energy of about 2.25 MeV and a half-life of about 64 hours, which decays to stable zirconium. Stable yttrium-89 can be directly placed in or around cancerous tissue and irradiated with neutrons in the 0.1-15 KeV energy range to produce significant amounts of yttrium-90. The beta radiation emitted by yttrium-90 will primarily destroy the more radiation sensitive cancer cells within the range of the beta particles. The resulting zirconium isotope is not radioactive such that no further radiation is released. A low probability gamma is also created that will assist in cancer cell destruction.

The invention provides MRI detectable species of formula (I): Dp-Sn-Nm, wherein D is a MRI detectable moiety; S is a spacer; N is a molecule of a nutrient or pseudo-nutrient; n is 0 or an integer, m is an integer and p is an integer. These compounds are useful for internalizing into tumor cells an amount of the MRI detectable moiety that is distinguishably higher than the amount internalized in normal healthy cells thus allowing the diagnosis of tumors. The internalization of the MRI detectable moiety involves the nutrients or pseudo-nutrients transporting system. Preferred compounds of formula (I) are those wherein D is the chelated complex of a paramagnetic metal ion.

This invention provides a process for producing a radioactive arsenic-containing compound, comprising the steps of: (i) subjecting an arsenic-containing compound to a neutron irradiation treatment, said arsenic-containing compound being selected from a group consisting of As2O3, As2S3, As2S2, and a combination thereof, such that the arsenic element contained in the arsenic-containing compound is converted to a radioactive arsenic isotope; and (ii) recovering the resultant product from step (i).This invention also provides a pharmaceutical composition comprising a therapeutically effective amount of the radioactive arsenic-containing compound and a pharmaceutically acceptable carrier. The pharmaceutical composition can be used in the treatment of tumors / cancers such as hematological malignancies and solid tumors.

This invention provides a process for producing a radioactive arsenic-containing compound, comprising the steps of: (i) subjecting an arsenic-containing compound to a neutron irradiation treatment, said arsenic-containing compound being selected from a group consisting of As2O3, As2S3, As2S2, and a combination thereof, such that the arsenic element contained in the arsenic-containing compound is converted to a radioactive arsenic isotope; and (ii) recovering the resultant product from step (i). This invention also provides a pharmaceutical composition comprising a therapeutically effective amount of the radioactive arsenic-containing compound and a pharmaceutically acceptable carrier. The pharmaceutical composition can be used in the treatment of tumors / cancers such as hematological malignancies and solid tumors.

Alkylphosphocholine analogs incorporating a chelating moiety that is chelated to gadolinium are disclosed herein. The alkylphophocholine analogs are compounds having the formula:or a salt thereof. R1 includes a chelating agent that is chelated to a gadolinium atom; a is 0 or 1; n is an integer from 12 to 30; m is 0 or 1; Y is —H, —OH, —COOH, —COOX, —OCOX, or —OX, wherein X is an alkyl or an arylalkyl; R2 is —N+H3, —N+H2Z, —N+HZ2, or —N+Z3, wherein each Z is independently an alkyl or an aroalkyl; and b is 1 or 2. The compounds can be used to detect solid tumors or to treat solid tumors. In detection / imaging applications, the gadolinium emits signals that are detectable using magnetic resonance imaging. In therapeutic treatment, the gadolinium emits tumor-targeting charged particles when exposed to epithermal neutrons.

According to an aspect, a magnesium fluoride sintered compact includes a disc-shaped magnesium fluoride sintered compact having a through hole passing through a center axis of the disc-shaped magnesium fluoride sintered compact. The magnesium fluoride sintered compact has a relative density of 95% or higher.

A composition for neutron capture therapy and a method of preparing the same are provided. The composition includes at least one nanodiamond particle and at least one neutron capture element, in which the at least one neutron capture element is embedded into the at least one nanodiamond particle by using an ion implantation system.

Alkylphosphocholine analogs incorporating a chelating moiety that is chelated to gadolinium are disclosed herein. The alkylphophocholine analogs are compounds having the formula:or a salt thereof. R1 includes a chelating agent that is chelated to a gadolinium atom; a is 0 or 1; n is an integer from 12 to 30; m is 0 or 1; Y is —H, —OH, —COOH, —COOX, —OCOX, or —OX, wherein X is an alkyl or an arylalkyl; R2 is —N+H3, —N+H2Z, —N+HZ2, or —N+Z3, wherein each Z is independently an alkyl or an aroalkyl; and b is 1 or 2. The compounds can be used to detect solid tumors or to treat solid tumors. In detection / imaging applications, the gadolinium emits signals that are detectable using magnetic resonance imaging. In therapeutic treatment, the gadolinium emits tumor-targeting charged particles when exposed to epithermal neutrons.