In recent years, a large class of nuclear $C^ast$-algebras have been classified, modulo an assumption on the Universal Coefficient Theorem (UCT). We think this assumption is redundant and propose a strategy for proving it. Indeed, following the original proof of the classification theorem, we propose bridging the gap between reduction theorems and examples. While many such bridges are possible, various approximate ideal structures appear quite promising.

We present a simple introduction to the decision tree algorithm using some examples from nuclear physics. We show how to improve the accuracy of the classical liquid drop nuclear mass model by performing Feature Engineering with a decision tree. Finally, we apply the method to the Duflo-Zuker model showing that, despite their simplicity, decision trees are capable of improving the description of nuclear masses using a limited number of free parameters.

Domain of mathematical logic in computers is dominated by automated theorem provers (ATP) and interactive theorem provers (ITP). Both of these are hard to access by AI from the human-imitation approach: ATPs often use human-unfriendly logical foundations while ITPs are meant for formalizing existing proofs rather than problem solving. We aim to create a simple human-friendly logical system for mathematical problem solving. We picked the case study of Euclidean geometry as it can be easily visualized, has simple logic, and yet potentially offers many high-school problems of various difficulty levels. To make the environment user friendly, we abandoned strict logic required by ITPs, allowing to infer topological facts from pictures. We present our system for Euclidean geometry, together with a graphical application GeoLogic, similar to GeoGebra, which allows users to interactively study and prove properties about the geometrical setup.

By Lauren McCauley Common Dreams In landmark agreement, California’s last remaining nuclear plant will be replaced by greenhouse-gas-free energy sources A plan to shutter the last remaining nuclear power plant in California and replace it with renewable energy is being … Continue reading →

The invention relates to a process for the preparation of oligonucleotides by the following steps: reaction of a nucleoside with a phosphine derivative, reaction of the nucleotide derivative thus obtained with a nucleoside bonded to a polymeric carrier, oxidation of the carrier-bound nucleoside-nucleotide thus obtained with formation of phosphotriester groups, blocking of free primary 5'--OH groups, elimination of a protective group from the terminal 5'--OH group, where appropriate single or multiple repetition of the abovementioned steps to introduce further nucleoside phosphate or oligonucleoside phosphate units, and cleavage of the nucleoside-carrier bond and, where appropriate, elimination of all protective groups present in the oligonucleoside phosphates. The phosphine derivative used is a compound of the general formula III ##STR1## in which X and L can react with OH groups of the sugar units in the oligonucleotides, and R3 is a protective group which can be liberated by β-elimination.

Methods and a kit. A cement forming method includes nucleating an acidic metallophosphate reaction mixture with first particles, resulting in forming a settable metallophosphate cement from the acidic metallophosphate reaction mixture. The first particles include a first metal oxide. Each particle of the first particles independently have a particle size in a range from about 15 microns to about 450 microns. A method for applying cement includes seeding a solution with particles, resulting in forming a settable cement from the solution. The particles have a size in a range from about 15 microns to about 450 microns. The solution includes a first metal oxide reacting with phosphate. The settable cement is applied to a substrate. A cement application kit is also described.

The instant invention provides for novel cationic lipids that can be used in combination with other lipid components such as cholesterol and PEG-lipids to form lipid nanoparticles with oligonucleotides. It is an object of the instant invention to provide a cationic lipid scaffold that demonstrates enhanced efficacy along with lower liver toxicity as a result of lower lipid levels in the liver. The present invention employs low molecular weight cationic lipids with one short lipid chain to enhance the efficiency and tolerability of in vivo delivery of siRNA.

A method of disposing nuclear waste in underground rock formations is presented. The method includes the steps of selecting a land area having a rock formation positioned there-below of a depth able to prevent radioactive material placed therein from reaching the surface and drilling a vertical wellbore from the surface, to a depth ranging between 5,000 feet and 25,000 feet, into the underground rock formation or repository. A plurality of horizontal laterals or horizontal wellbores, ranging in length from 500 feet to 40,000 feet, are drilled from the vertical wellbore into the underground rock formation or repository. Nuclear waste to be stored within these laterals is encapsulated in a special waste canister and these nuclear waste canisters are positioned within the horizontal laterals wherein they are sealed to prevent loss and leakage. Means are also provided by which these canisters are adapted to allow retrievability of the canisters from the wellbore at a later date and to return the waste to the surface for use after retrieval.

Methods of capturing and immobilizing radioactive nuclei with metal fluorite-based inorganic materials are described. For example, a method of capturing and immobilizing radioactive nuclei includes flowing a gas stream through an exhaust apparatus. The exhaust apparatus includes a metal fluorite-based inorganic material. The gas stream includes a radioactive species. The radioactive species is removed from the gas stream by adsorbing the radioactive species to the metal fluorite-based inorganic material of the exhaust apparatus.

A method and device for limiting the degassing of tritiated waste issued from the nuclear industry are provided. The method reduces an amount of generated tritiated hydrogen (T2 or HT) and/or tritiated water (HTO or T2O) including at least one piece of tritiated waste from the nuclear industry. The method includes placing the package in contact with a mixture including manganese dioxide (MnO2) combined with a component that includes silver; and placing the package in contact with a molecular sieve.

The disclosure relates to methods of making polymer particles, said methods including the steps of: making an aqueous gel reaction mixture; forming an emulsion having dispersed aqueous phase micelles of gel reaction mixture in a continuous phase; adding an initiator oil comprising at least one polymerization initiator to the continuous phase; and performing a polymerization reaction in the micelles. Further, the initiator oil is present in a volume % relative to a volume of the aqueous gel reaction mixture of between about 1 vol % to about 20 vol %. The disclosure also relates to methods of making nucleic acid polymer particles having the same method steps and wherein the aqueous gel reaction mixture includes a nucleic acid fragment, such as a primer.

A method for producing a phenylphosphonic acid metal salt composition, including reacting a phenylphosphonic acid compound (a) with a metal salt, metal oxide or metal hydroxide (b) that is present in an amount beyond the equivalent, the phenylphosphonic acid metal salt composition containing phenylphosphonic acid metal salt, and a surplus amount of the metal salt, the metal oxide or the surplus metal hydroxide (b). A crystal nucleating agent comprises the phenylphosphonic acid metal salt composition produced by the method.

The present invention concerns a TCTP antagonist, in particular a nucleic acid targeting an m RNA encoding Translationally-Controlled Tumor Protein (TCTP), wherein said nucleic acid is capable of reducing the amount of TCTP in cells, for use in the treatment or prevention of hormone-independent cancer or chemo-resistant cancer, such as an androgen-independent prostate cancer.

The invention describes new structures of the nucleotide conjugates (nuc-macromolecules) comprising at lease one nucleotide moiety coupled to at least one macromolecular compound via a short linker. These conjugates can be used as substrates for various kinds of polymerizing enzymes in the enzymatic synthesis of nucleic acids. In particular, these compounds can be used for labeling nucleic acids.

The present invention is related to an L nucleic acid that binds to an SDF-1.

An antisense molecule capable of binding to a selected target site to induce exon skipping in the dystrophin gene, as set forth in SEQ ID NO: 1 to 202.

This invention relates to a process for preparing an oligonucleotide 5'-triphosphate. The process comprises the steps of: (a) synthesizing an oligonucleotide having a 5' hydroxyl moiety; (b) reacting the 5' hydroxyl moiety with a reagent of formula I: to convert the 5' hydroxyl moiety to a 5'-H-phosphonate, wherein R1 and R2 are each independently selected from the group consisting of haloalkyl, aryl, substituted aryl, heteroaryl, substituted heteroaryl, cycloalkyl, substituted cycloalkyl, heterocycle, and substituted heterocycle, acyl, phosphoryl, substituted alkyl acyl, substituted heteroalkyl acyl, substituted aryl acyl or substituted heteroaryl acyl, substituted alkyl phosphoryl, substituted heteroalkyl acyl, substituted aryl phosphoryl, and substituted heteroaryl phosphoryl; (c) activating the H-phosphonate of step (b) by reacting the H-phosphonate with a silylating agent, a halogenated oxidizing agent, a nitrogen-containing heteroaryl, or a combination thereof, to form an activated H-phosphonate; and (d) treating the oligonucleotide having an activated H-phosphonate from step (c) with a poly(alkylammonium)pyrophosphate.

The invention refers to polynucleotides selected from the group consisting of a) polynucleotides encoding for the polypeptide RBM20 comprising a P638L mutation for a human polypeptide RBM20, or a P641L mutation for a rat polypeptide RBM20, b) polynucleotides with a reverse complementary sequence of the polynucleotide of a) above, and c) polynucleotides with an identity at least 50% to a polynucleotide of a) or b) above.

The present disclosure provides reagents that can be used to label synthetic oligonucleotides with rhodamine dyes or dye networks that contain rhodamine dyes.

The present disclosure generally relates to dry solid matrices for the extraction, stabilization, and storage of nucleic acids, particularly RNA, in a dry format under ambient conditions for a prolonged period of time. Methods for collecting and recovering the nucleic acids stored in the dry solid matrix are also described.

A solid matrix for the extraction, stabilization, and storage of nucleic acids is provided. At least one protein denaturant, and at least one acid or acid-titrated buffer reagent are impregnated in a dry state therein the matrix; and the matrix is configured to provide an acidic pH on hydration. The matrix is configured to extract nucleic acids from a sample and stabilize the extracted nucleic acids, particularly RNA, in a dry format under ambient conditions for a prolonged period of time. Methods for collecting and recovering the nucleic acids stored in the dry solid matrix are also described.

The present disclosure generally relates to solid matrices for the extraction, stabilization, and storage of nucleic acids, particularly RNA, in a dry format under ambient conditions for a prolonged period of time. Methods for extracting, collecting, and recovering nucleic acids from the solid compositions are also described.

The instant invention provides for novel cationic lipids that can be used in combination with other lipid components such as cholesterol and PEG-lipids to form lipid nanoparticles with oligonucleotides. It is an object of the instant invention to provide a cationic lipid scaffold that demonstrates enhanced efficacy along with lower liver toxicity as a result of lower lipid levels in the liver. The present invention employs low molecular weight cationic lipids comprising at least one short lipid chain to enhance the efficiency and tolerability of in vivo delivery of siRNA.

The present invention relates to the field of organic chemistry and in particular to organic free radicals used as polarizing agents in the technique of Dynamic Nuclear Polarization (DNP), which involves transferring the polarization of electron spins to the nuclei of a compound whose Nuclear Magnetic Resonance (NMR) is being observed. It concerns Dinitroxide-type Biradical polarizing agents characterized by a rigid linkage between the aminoxyl groups of said nitroxide units. This particular structure enables, at low temperatures and high fields, optimal transfer of polarization and optimal enhancement of NMR/MAS signals of the polarized nuclei of the compound studied.

The present invention generally relates to use of compounds and compositions as a chemosensitizers and/or radiosensitizers and/or inhibitors of PNKP phosphatase activity. The present invention provides pharmaceutical combinations and/or a pharmaceutically acceptable salt thereof, kits containing such compounds and/composition and methods of using such compounds and/or compositions.

The invention encompasses devices and methods for treating one or more damaged, diseased, or traumatized intervertebral discs to reduce or eliminate associated back pain. Specifically, the invention encompasses intervertebral nucleus and annulus implants that are resistant to migration in and/or expulsion from an intervertebral disc space. The invention further encompasses kits including the implantable devices of the invention and associated delivery tools to treat annular and nuclear tissue.

A universal linker structure is provided, in which a functional group and activating leaving group are placed on a tether, allowing the placement of an electrophile at the end of any nucleic acid sequence. The electrophile on the tether can react with a second nucleic acid carrying a nucleophile when the two nucleic acids are hybridized near one another, resulting in release of the leaving group, and creation of a functional change. The linker can be designed to destabilize the ligation product without slowing the rate of reaction. This lowers product inhibition, and the target DNA or RNA can become a catalyst for isothermally generating multiple signals for detection. This enhanced signal is demonstrated in solution experiments and in solid supported assays. The universal linkers of the present invention are simple and inexpensive to prepare, and can be appended to any polynucleotide in automated steps on a standard DNA synthesizer.

Provided is an oligonucleotide containing an azobenzene derivative, represented by Formula (1) or (2) below: (in the formulae, A1 and A2 each independently represent a hydrogen atom, nucleotide or oligonucleotide, B1 and B2 each independently represent a hydroxyl group, nucleotide or oligonucleotide, R11 and R12 each independently represent a C1-20 alkyl group, R21 and R22 each independently represent a hydrogen atom or C1-20 alkyl group, and R13 to R18 and R23 to R28 each independently represent a hydrogen atom; a C1-20 alkyl group or alkoxy group optionally substituted with a halogen atom, hydroxyl group, amino group, nitro group or carboxyl group; a C2-20 alkenyl group or alkynyl group optionally substituted with a halogen atom, hydroxyl group, amino group, nitro group or carboxyl group; a hydroxyl group; a halogen atom; an amino group; a nitro group; or a carboxyl group).

A spent fuel reprocessing method including the steps of partitioning U and Pu(III) in a solvent by solvent extraction and subsequently polishing the solvent in a neptunium rejection operation for removing Np therefrom. The solvent obtained from the neptunium rejection operation (the polished solvent or NpA solvent product) is then recycled to a U/Pu partitioning operation. The method enables a reduction in solvent feed and solvent effluent volumes.

The present invention relates to a process to dissolve plutonium or a plutonium alloy, by placing it in contact with an aqueous dissolution mixture, wherein said dissolution mixture comprises nitric acid, a carboxylic acid with complexing properties with respect to plutonium, and a compound comprising at least one —NH2 radical such as urea. The invention also relates to a process to convert plutonium or a plutonium alloy into plutonium oxide and to manufacture nuclear fuel from said oxide.The invention particularly applies to the dismantling of plutonium contained in nuclear weapons with a view to its use in civilian nuclear reactors, particularly in the form of MOX fuel.

This invention is provided for improvement of corrosion-resistant property of a crucible and for promotion of safety in a pyrochemical reprocessing method for the spent nuclear fuel. The spent nuclear fuel is dissolved in a molten salt placed in the crucible. In a pyrochemical reprocessing method, the nuclear fuel is deposited, and the crucible (2) is heated by induction heating. Cooling media (5, 6) are supplied to cool down, and a molten salt layer (7) is maintained by keeping balance between the heating and the cooling, and a solidified salt layer (8) is formed on inner wall surface of the crucible.

The invention provides a method of separating uranium from at least fission products in irradiated nuclear fuel, said method comprising reacting said irradiated nuclear fuel with a solution of ammonium fluoride in hydrogen fluoride fluorinating said reacted irradiated nuclear fuel to form a volatile uranium fluoride compound and separating said volatile uranium fluoride compound from involatile fission products. The invention thus provides a reprocessing scheme for irradiated nuclear fuel. The method is also capable of reacting, and breaking down Zircaloy cladding and stainless steel assembly components. Thus, whole fuel elements may be dissolved as one thereby simplifying procedures over conventional Purex processes.

A vol-oxidizer of spent nuclear fuel, the spent nuclear fuel is injected to a reaction portion, the reaction portion is connected to a driving portion and oxidizes the spent nuclear fuel by rotating and back-rotating the spent nuclear fuel. The oxidized powder of the spent nuclear fuel is gathered in a discharge portion located in a lower portion of the reaction portion. By providing minute powder particles for recycling and a post process of the spent nuclear fuel, even though a size of an apparatus is small, processing a large amount is possible. Time required for oxidation can be reduced, and the powder is readily discharged by gravity since the apparatus is vertically configured.

Disclosed is a separation and receiving apparatus for a spent nuclear fuel rod. The spent nuclear fuel rod is mounted and downwardly transferred by a pin. At this time, a blade peels the hull of the spent nuclear fuel rod. The hull and a pellet positioned therein are separated by a separator. The peeled hull and pellet are each received in respective receiving vessels. Accordingly, since the hull and pellet made of uranium oxide (UO2) may be automatically separated and received in each respective vessel, safety and automation may be guaranteed.

A method of repairing a nuclear fuel cell wall and tools useful for performing that repair are described. A repair tool may be used to align a jack near a region of a bent or distorted structural component of nuclear fuel cell and that jack may be used to apply a force to that structural component. Application of such a force may serve to bend the structural component of a nuclear fuel cell in a way to restore the structural component to its position before damage occurred. The repair tool includes a way of mounting that tool to a fuel cell, positioning elements to align the tool near a structural deformation or bent element and a jack that may be use to apply a force to at least one structural component in a fuel cell.

Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system.

Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

A method for design of a fuel assembly for nuclear reactors, including structural components made from zirconium alloy: the mean uniaxial tensile or compressive stress to which the components are subjected during the assembly life is calculated, the zirconium alloy of which the components are made is selected according to the following criteria: those components subjected to an axial or transverse compressive stress of between −10 et −20 MPa are made from an alloy with a content of Sn between Sn=(=0.025σ−0.25)% and Sn=−0.05σ%: those components subjected to such a stress of between 0 et −10 MPa are made from an alloy the Sn content of which is between Sn=traces and Sn=(0.05σ+1)%: those components subjected to such a stress of between 0 and +10 MPa are made from an alloy the Sn content of which is between Sn=0.05% and Sn=(0.07σ+1)%: and those components subjected to such a stress of between +10 and +20 MPa are made from an alloy the content of SN of which is between 0.05% and 1.70%. A fuel assembly made according to the method.

Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

A storage rack arrangement (10) for the storage of nuclear fuel elements in a storage pool includes at least two storage racks (1.1-1.3) which each contain a plurality of vertical channels (9) arranged next to one another for the reception of the fuel elements, with positioning elements (6) being provided at the storage racks at the bottom. The storage racks are connected to one another at the top and the storage rack arrangement (10) additionally includes one or more base plates (2.1-2.3) which are provided with positioning members (8) which fit with the positioning elements (6) of the storage racks (1.1-1.3) and which, together with the positioning elements, position the storage racks with respect to the base plate or base plates (2.1-2.3) to prevent a displacement of the storage racks on the base plate or plates.

Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system.

A method for measuring the neutron flux in the core of a nuclear reactor, the method including several steps recurrently performed at instants separated by a period, the method comprising at each given instant the following steps: acquiring a total signal by a cobalt neutron detector placed inside the core of the reactor; assessing a calibration factor representative of the delayed component of the total signal due to the presence of cobalt 60 in the neutron detector; assessing a corrected signal representative of the neutron flux at the detector from the total signal and from the calibration factor; assessing a slope representative of the time-dependent change of the calibration factor between the preceding instant and the given instant; the calibration factor at the given instant being assessed as a function of the calibration factor assessed at the preceding instant, of the slope, and of the time period separating the given instant from the preceding instant.

Disclosed embodiments include methods of assembling a vented nuclear fission fuel module. Given by way of non-limiting example and not of limitation, an illustrative method of assembling a vented nuclear fission fuel module includes receiving a nuclear fission fuel element capable of generating a gaseous fission product. A valve body is coupled to the nuclear fission fuel element, and the valve body defines a plenum therein for receiving the gaseous fission product. A valve is disposed in communication with the plenum for controllably venting the gaseous fission product from the plenum. A flexible diaphragm is coupled to the valve for moving the valve. A cap is mounted on the valve, and a manipulator extendable to the cap for manipulating the cap is received.

A perpendicular magnetic recording disk has a graded-anisotropy recording layer (RL) formed of at least two ferromagnetically exchange coupled CoPtCr-oxide magnetic layers (MAG1 and MAG2) with two nucleation films (NF1 and NF2) between the magnetic layers. NF1 is a metal film, preferably Ru or a Ru-based alloy like RuCr, sputter deposited on MAG1 at low pressure to a thickness between about 0.1-1.5 nm. NF2 is a metal oxide film, preferably an oxide of Ta, sputter deposited on NF1 at high pressure to a thickness between about 0.2-1.0 nm. MAG2 is sputter deposited over NF2. NF1 and NF2 provide a significant reduction in average grain size in the RL from a graded-anisotropy RL without nucleation films between MAG1 and MAG2, while also assuring that MAG1 and MAG2 are strongly exchange coupled.

This invention provides recombinant DNA constructs and methods for manipulating expression of a target gene that is regulated by a small RNA, by interfering with the binding of the small RNA to its target gene. More specifically, this invention discloses recombinant DNA constructs encoding cleavage blockers, 5-modified cleavage blockers, and translational inhibitors useful for modulating expression of a target gene and methods for their use. Further disclosed are miRNA targets useful for designing recombinant DNA constructs including miRNA-unresponsive transgenes, miRNA decoys, cleavage blockers, 5-modified cleavage blockers, and translational inhibitors, as well as methods for their use, and transgenic eukaryotic cells and organisms containing such constructs.

The invention relates to compounds that specifically bind a T1R1/T1R3 or T1R2/T1R3 receptor or fragments or sub-units thereof. The present invention also relates to the use of hetero-oligomeric and chimeric taste receptors comprising T1R1/T1R3 and T1R2/T1R3 in assays to identify compounds that respectively respond to umami taste stimuli and sweet taste stimuli. Further, the invention relates to the constitutive of cell lines that stably or transiently co-express a combination of T1R1 and T1R3; or T1R2 and T1R3; under constitutive or inducible conditions. The use of these cells lines in cell-based assays to identify umami and sweet taste modulatory compounds is also provided, particularly high throughput screening assays that detect receptor activity by use of fluorometric imaging.

The present invention relates to a novel method for analyzing nucleic acid sequences based on real-time detection of DNA polymerase-catalyzed incorporation of each of the four nucleotide bases, supplied individually and serially in a microfluidic system, to a reaction cell containing a template system comprising a DNA fragment of unknown sequence and an oligonucleotide primer. Incorporation of a nucleotide base into the template system can be detected by any of a variety of methods including but not limited to fluorescence and chemiluminescence detection. Alternatively, microcalorimetic detection of the heat generated by the incorporation of a nucleotide into the extending template system using thermopile, thermistor and refractive index measurements can be used to detect extension reactions.

An automated method for detecting the presence of a nucleic acid in a sample, where the method is performed within a housing of a self-contained, stand-alone analyzer. The method includes purifying the nucleic acid after it has been immobilized on a magnetically-responsive solid support. A pipette of the analyzer is used to form a reaction mixture comprising the purified nucleic acid and all reagents required to perform a nucleic acid amplification. Amplification products are synthesized that include a nucleotide sequence contained in the nucleic acid or the complement of the nucleic acid. The amplification products are exposed to a probe in a mixture, where the probe forms a hybrid with one of the amplification products. The formation of the hybrid in the mixture provides an indication of the presence of the nucleic acid in the sample.

This invention relates to the field of biotechnology or genetic engineering. Specifically, this invention relates to the field of gene expression. More specifically, this invention relates to novel substitution mutant receptors and their use in a nuclear receptor-based inducible gene expression system and methods of modulating the expression of a gene in a host cell for applications such as gene therapy, large scale production of proteins and antibodies, cell-based high throughput screening assays, functional genomics and regulation of traits in transgenic organisms.

A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (10), an outer volume of protective material (22), and an integrated middle volume (20) of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume (20) resulting in structural integrity for the cladding.