Mitsubishi Heavy Industries Limited

Toyobo Co., Ltd.

Toyobo Mc Corporation

Hideyuki Sakata

Kenji Kashihara

Takafumi Ogino

Taiki Asahara

Yutaka Tanaka

Takashi Nakahara

Shigeyuki Watanabe

Shigeto Hirai

Akihiro Toda

Masamichi Iino

Takanori Okazaki

Akira Kirita

Toshihiro Sato

Hiroyuki Kojima

Hiroshi Matsuoka

Jun Shimizu

Kazuo Hirota

Makoto Nakajima

Hideyuki Morita

Takeshi Ito

Chikara Kurimura

Toshio Ichikawa

Nobuki Uda

Yasunao Yamaguchi

Takuya Yokomichi

Yuji Momose

Setsuo Tokunaga

Shohei Okano

Momoko Nakajima

An object of this invention is to provide an adhesive composition that comprises a moisture-curable resin and a modified polyolefin and that achieves an excellent liquid state and excellent adhesion to polyolefin resin substrates. Provided is a moisture-curable adhesive resin composition comprising a moisture-curable resin (A) and a modified polyolefin resin (B), wherein the content of the modified polyolefin resin (B) is 2 parts by mass or more per 100 parts by mass of the moisture-curable resin (A).

Moisture-curable adhesive composition

A flow damper including a cylindrical vortex chamber, a small flow-rate pipe connected to a peripheral plate of the vortex chamber along a tangential direction, a large flow-rate pipe connected to the peripheral plate with a predetermined angle with respect to the small flow-rate pipe, an outlet pipe connected to an outlet formed in a central part of the vortex chamber, and a pressure equalization pipe with respective ends being connected to the peripheral plate on opposite sides of the outlet and at positions closer to a connection portion between the small flow-rate pipe and the large flow-rate pipe than positions facing each other, putting the outlet therebetween. The pressure equalization pipe is arranged with at least a part thereof is located at a higher position than a top plate of the vortex chamber, and an outgassing hole is provided at an uppermost part of the pressure equalization pipe.

Flow damper, pressure-accumulation and water-injection apparatus, and nuclear installation

To include a cylindrical vortex chamber, a small flow-rate pipeconnected to a peripheral plateC of the vortex chamberalong a tangential direction thereof, a large flow-rate pipeconnected to the peripheral plateC with a predetermined angle with respect to the small flow-rate pipe, an outlet pipe connected to an outletformed in a central part of the vortex chamber, and a straightening platethat is arranged in a part between the outletand the peripheral plateC of the vortex chamber, and when jets flow into the vortex chamberfrom the small flow-rate pipeand the large flow-rate pipe, straightens impinging jets from the small flow-rate pipeand from the large flow-rate pipehaving flowed into the vortex chambertoward the outlet

A liquid level detection device for a liquid supplying facility includes: a lower pipe which is in communication with a liquid-phase section of an interior space of a tank, the liquid-phase section being occupied by a liquid; an upper pipe which is in communication with a gas-phase section of the interior space of the tank, the gas-phase section being disposed above the liquid-phase section and occupied by a high-pressure gas; a differential pressure gauge for detecting a differential pressure between the lower pipe and the upper pipe; and a liquid level calculation part for calculating a liquid level of the tank on the basis of a differential pressure detection result of the differential pressure gauge. An inside of the upper pipe is filled with a filling liquid at least in a partial range.

Liquid level detection device of liquid supplying facility, liquid level detection method of liquid supplying facility, and liquid supplying facility having the liquid level detection device

Acquiring sets of test data on amounts of foreign matter passed through a recirculation sump screen when different amounts of foreign matter are input; forming a passed foreign matter amount approximate line that approximates the amounts of passed foreign matter with respect to the amounts of input foreign matter on the basis of the sets of test data on the amounts of passed foreign matter; forming a passed foreign matter amount envelope tangent to the passed foreign matter amount approximate line; and estimating a total passed foreign matter amount with respect to the amounts of input foreign matter on the basis of the passed foreign matter amount envelope to evaluate the recirculation sump screen are provided.

Method of evaluating amount of foreign matter passed through recirculation sump screen

This invention provides a novel polyolefin modified with a nitrogen-containing heterocyclic compound containing no harmful halogen atoms such as chlorine, and an adhesive composition between a polyolefin substrate and an inorganic substrate such as a glass substrate. A polyolefin modified with a nitrogen-containing heterocyclic compound (C) having a nitrogen-containing heterocyclic compound (B) at the side chain of an acid-modified polyolefin (A).

Polyolefin modified with nitrogen-containing heterocyclic compound, and adhesive composition containing same

Provided is an adhesive composition comprising a modified polyolefin and an epoxy resin, the composition having excellent pot life, and excellent adhesion to both a metal substrate and a polyolefin resin substrate. The adhesive composition comprises a modified polyolefin (A), a glycidyl amine-type epoxy resin (B1), a glycidyl ether-type epoxy resin (B2), and an organic solvent (C); wherein the modified polyolefin (A) is (A1) or (A2) below:

Polyolefin-based adhesive composition

An upper holeA and a lower holeB are provided at two positions, namely, upper and lower portions, of a side surface of a guide tube, and a thimble tubeis pressed against an inner circumferential surface of the guide tube, by a differential pressure between coolant inside and outside the upper holeA and the lower holeB. It is preferable that an upper pressure adjustment hole and a lower pressure adjustment hole are provided at two positions, namely, upper and lower portions, of a side surface of an upper core support column, and a coolant flowing into the guide tube from an upper end of the guide tube flows out to the outside from inside the guide tube through a gap between the thimble tube and the upper hole, and also flows out to the outside from inside the upper core support column through the upper pressure adjustment hole, and a coolant flowing into the guide tube from a lower end of the guide tube flows out to the outside from inside the guide tube through a gap between the thimble tube and the lower hole, and also flows out to the outside from inside the upper core support column through the lower pressure adjustment hole.

Structure for suppressing flow vibration of instrumentation guide tube

Provided is a fuel assemblyfor a PWR nuclear reactor capable of stably creating transverse flows of coolant for pressing and securing control rods so as to restrain vibration of the control rods in order to restrain the outer surfaces of the control rods and the inner surfaces of control rod guide tubes from being worn, wherein an upper nozzle arranged above the fuel assembly comprises an adapter plateconstituting the lower structure of the upper nozzle, a side wall extended along the periphery of the adapter plate, an overhang projected into a space above the adapter plate from the upper part of the side wall, and apertures for attaching control guide tubes and passage holes, which are formed in the passage surface of the adapter plate, and wherein thoseA,B,C of the passage holes which are located at positions where the coolant impinges upon the overhang are generally arranged, line-symmetric with respect to diagonal lines of the passage surface serving as symmetric axes Q, and ligamentsaround the passage holes located inside and outside of thoseof the attaching apertures which are located on the outer peripheral side are set to be larger than ligamentsaround the passage holes which are located on opposite transverse sides of those of the attaching apertures.

Fuel assembly for PWR nuclear reactor

Growing community of inventors

Hyogo, Japan

Hideyuki Sakata