摘要:
A fuel assembly for a nuclear reactor includes a number of fuel rods filled with a fuel material. A water rod having a cross sectional area larger than that of each fuel rod is disposed at substantially the central portion of the fuel assembly. The fuel rods include first fuel rods having a whole effective fuel zone filled with a fuel material throughout the entire length thereof and second fuel rods each having an interposed zone in which enrichment of a fissile nuclide is significantly reduced or the fissile nuclide does not exist at all. The second fuel rods are arranged so as to surround the water rod so that the interposed zones are positioned on an axial level including a portion at which subcriticality is made small at a period in which maintenance of reactor shut-down margine is made difficult during the reactor operation period. The water rod may be provided with a lower portion having a cross sectional area smaller than that of an upper portion and short fuel rods are disposed so as to surround the lower portion of the water rod.
摘要:
A fuel assembly for a nuclear reactor includes a number of fuel rods filled with a fuel material. A plurality of fuel rods have a partial effective fuel area filled with a fuel material and has a portion in which enrichment of a fissile nuclide is significantly reduced or the fissile nuclide does not exist at all on an axial level including a reactor shut-down zone at which subcriticality becomes small during a reactor operation period. The other fuel rods are filled with the fuel material throughout the entire axial length thereof. The first mentioned fuel rod may be provided with a partially interposed zone or may be constructed by a fuel rod having a length shorter than that of the other fuel rod. The tube means may be arranged in the fuel assembly so as to pass the moderator therethrough.
摘要:
A first intensity Az expressed as Az=az×Eα, a first reference intensity Ao expressed as Ao=ao×Eα, a second intensity Bz expressed as Bz=bz×E, and a second reference intensity Bo=bo×E, are evaluated. The first intensity and the first reference intensity are of radioactive nuclides generated by a neutron capture reaction of a heavy nuclide or a fission product nuclide. The second intensity and the second reference intensity are of radioactive fission product nuclides except nuclides generated by a neutron capture reaction. The reference intensities are measured where the void fraction is known. Also a correlation curve of (az/ao) and a void fraction is evaluated. Finally an axial void fraction distribution is evaluated based on the value of (az/ao) and the correlation curve.
摘要翻译:表示为第一参考强度A 的第一强度A z sub> > o SUB>表示为第二强度B SUB表达的第二强度B SUP> 作为Bζz z x x x x x are are are are are,,,,evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated evaluated 。 第一强度和第一参考强度是由重核素或裂变产物核素的中子捕获反应产生的放射性核素。 第二强度和第二参考强度是放射性裂变产物核素,除了由中子俘获反应产生的核素外。 在已知空隙率的情况下测量参考强度。 此外,还评估了(a z> / / o o o o)和空隙率的相关曲线。 最后,基于(a 1 / z 2 / a 2)的值和相关曲线来评估轴向空隙率分布。
摘要:
A first intensity Az expressed as Az=az×Eα, a first reference intensity A0 expressed as A0=a0×Eα, a second intensity Bz expressed as Bz=bz×E, and a second reference intensity B0=b0×E, are evaluated. The first intensity and the first reference intensity are of radioactive nuclides generated by a neutron capture reaction of a heavy nuclide or a fission product nuclide. The second intensity and the second reference intensity are of radioactive fission product nuclides except nuclides generated by a neutron capture reaction. The reference intensities are measured where the void fraction is known. Also a correlation curve of (az/a0) and a void fraction is evaluated. Finally an axial void fraction distribution is evaluated based on the value of (az/a0) and the correlation curve.
摘要:
A first intensity Az expressed as Az=az×Eα, a first reference intensity A0 expressed as A0=a0×Eα, a second intensity Bz expressed as Bz=bz×E, and a second reference intensity B0=b0×E, are evaluated. The first intensity and the first reference intensity are of radioactive nuclides generated by a neutron capture reaction of a heavy nuclide or a fission product nuclide. The second intensity and the second reference intensity are of radioactive fission product nuclides except nuclides generated by a neutron capture reaction. The reference intensities are measured where the void fraction is known. Also a correlation curve of (az/a0) and a void fraction is evaluated. Finally an axial void fraction distribution is evaluated based on the value of (az/a0) and the correlation curve.
摘要:
A core of a light-water reactor comprises a plurality of fuel assemblies each including a number of fuel rods. The fuel rod is provided with at least one area interposed between fuel areas in a clad of the fuel rod. The interposed area contains extremely reduced or substantially no fissile nuclide. At least two areas or layers with high enrichment of the fissile nuclide are formed in the axial direction of the reactor by the location of the interposed areas throughout the whole fuel assemblies arranged in the light-water reactor core.
摘要:
A fuel assembly for a nuclear reactor comprises a fuel bundle in which a number of fuel rods are regularly arranged and a channel box surrounding the outer periphery of the fuel bundle. The interior of the channel box is designed so that the inner cross sectional area of the channel box increases from the upstream side of the coolant flow towards the downstream side thereof, for example, by stepwisely shaving the inner surface of the channel box. The corner portions of the channel box may be chamfered to improve the stress due to the inner pressure.
摘要:
The present invention has its object to provide a method for producing an L-amino acid comprising reacting a keto acid with an amino acid dehydrogenase and an enzyme having coenzyme regenerating ability to convert to a L-amino acid, wherein a coenzyme is added in two or more portions in the reaction. The method of the present invention enables efficient production of an L-amino acid useful as a synthetic intermediate such as a pharmaceutical intermediate with high optical purity by an enzymatic reductive amination independent of the purity of the keto acid used as a substrate.
摘要:
The present invention is to provide a process for efficiently producing an optically active alcohol including (R)-3-hydroxy-3-phenylpropanenitrile. One of the features of the present invention is a polypeptide having an activity of asymmetrically reducing 3-oxo-3-phenylpropanenitrile isolated from a microorganism belonging to the genus Candida to produce (R)-3-hydroxy-3-phenylpropanenitrile, DNA encoding the polypeptide and a transformant of producing the polypeptide. Another feature of the present invention is a process for producing an optically active alcohol such as (R)-3-hydroxy-3-phenylpropanenitrile by reducing a carbonyl compound such as 3-oxo-3-phenylpropanenitrile by use of the polypeptide or the transformant.
摘要:
An upper detector and a lower detector that face at least one side of a fuel assembly, on which neutrons are irradiated in a nuclear reactor, and detect radiation are set at a predetermined interval in an axial direction of the fuel assembly. Distributions of radiation signals are measured by the upper detector and the lower detector while the fuel assembly and the upper detector and the lower detectors are relatively moved along the axial direction of the fuel assembly. Soundness of radiation signals measured by the upper detector and the lower detector is determined in every measurement by comparing radiation signal distributions obtained by measuring the same portion in the axial direction of the fuel assembly in a multiplexed manner with the upper detector and the lower detector. Thereafter, relative burn-up is calculated by utilizing the measured radiation signals to measure a burn-up profile. According to the present invention, it is possible to measure a burn-up profile of the fuel assembly while securing reliability of a measurement result.