The patent badge is an abbreviated version of the USPTO patent document. The patent badge does contain a link to the full patent document.

The patent badge is an abbreviated version of the USPTO patent document. The patent badge covers the following: Patent number, Date patent was issued, Date patent was filed, Title of the patent, Applicant, Inventor, Assignee, Attorney firm, Primary examiner, Assistant examiner, CPCs, and Abstract. The patent badge does contain a link to the full patent document (in Adobe Acrobat format, aka pdf). To download or print any patent click here.

Date of Patent:
Jul. 19, 2016

Filed:

Nov. 21, 2012
Applicant:

Kabushiki Kaisha Toshiba, Minato-Ku, JP;

Inventors:

Hiroaki Kenjyo, Fujisawa, JP;

Yasushi Goto, Yokohama, JP;

Toshiaki Ito, Yokohama, JP;

Assignee:

KABUSHIKI KAISHA TOSHIBA, Minato-ku, JP;

Attorney:
Primary Examiner:
Assistant Examiner:
Int. Cl.
CPC ...
G21C 17/022 (2006.01); G01F 23/24 (2006.01); G21C 17/035 (2006.01); G21C 17/112 (2006.01);
U.S. Cl.
CPC ...
G01F 23/246 (2013.01); G21C 17/035 (2013.01); G21C 17/112 (2013.01);
Abstract

It is provided with a reactor water-level measurement system being possible to measure water-level in a reactor core regardless of a state in the reactor core. The reactor water-level measurement system includes a core bottom water-level measuring device that includes a heating element, a heat insulating element installed by surrounding part of the heating element in a height direction of the heating element, and a temperature difference measuring element that measures a temperature difference between an insulated portion of the heating element surrounded by the heat insulating element and a non-insulated portion not surrounded by the heat insulating element, a water-level evaluation device that evaluates a water level of a reactor based on the temperature difference, wherein the core bottom water-level measuring device measures at least a water level from a lower end of a reactor core contained in a reactor pressure vessel to a bottom of the reactor pressure vessel.


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