Patents by Inventor Naoto Kasahara

Naoto Kasahara has filed for patents to protect the following inventions. This listing includes patent applications that are pending as well as patents that have already been granted by the United States Patent and Trademark Office (USPTO).

  • Thermal load reducing system for nuclear reactor vessel
    Patent number: 8036335
    Abstract: In a reactor vessel thermal load reducing system near the surface level of a coolant, the present invention is characterized in that a heat conductive member is installed not contacting the reactor vessel wall in an area above and below the coolant liquid surface, and the heat conducting member is attached to a guard vessel, the heat conducting member being made of material of good heat conductivity.
    Type: Grant
    Filed: June 4, 2007
    Date of Patent: October 11, 2011
    Assignee: Japan Nuclear Cycle Development Institute
    Inventors: Naoto Kasahara, Masanori Ando
  • Thermal load reducing system for nuclear reactor vessel
    Publication number: 20080107226
    Abstract: In a reactor vessel thermal load reducing system near the surface level of a coolant, the present invention is characterized in that a heat conductive member is installed not contacting the reactor vessel wall in an area above and below the coolant liquid surface, and the heat conducting member is attached to a guard vessel, the heat conducting member being made of material of good heat conductivity.
    Type: Application
    Filed: June 4, 2007
    Publication date: May 8, 2008
    Applicant: JAPAN NUCLEAR CYCLE DEVELOPMENT INSTITUTE
    Inventors: Naoto Kasahara, Masanori Ando
  • Thermal load reducing system for nuclear reactor vessel
    Publication number: 20070280399
    Abstract: In a reactor vessel thermal load reducing system near the surface level of a coolant, the present invention is characterized in that a heat conductive member is installed not contacting the reactor vessel (1) wall in an area above and below the coolant liquid surface, and the heat conducting member is a guard vessel (2) made of good heat conductivity, or a heat conductive plate (20) made of good heat conductivity.
    Type: Application
    Filed: April 16, 2007
    Publication date: December 6, 2007
    Inventors: Naoto Kasahara, Masanori Ando
  • Thermal load reducing system for nuclear reactor vessel
    Publication number: 20050135545
    Abstract: In a reactor vessel thermal load reducing system near the surface level of a coolant, the present invention is characterized in that a heat conductive member is installed not contacting the reactor vessel (1) wall in an area above and below the coolant liquid surface, and the heat conducting member is a guard vessel (2) made of good heat conductivity, or a heat conductive plate (20) made of good heat conductivity.
    Type: Application
    Filed: October 14, 2003
    Publication date: June 23, 2005
    Applicant: JAPAN NUCLEAR CYCLE DEVELOPMENT INSTITUTE
    Inventors: Naoto Kasahara, Masanori Ando
  • Thermal load reducing system for nuclear reactor vessel
    Patent number: 6594333
    Abstract: The present invention is used to reduce thermal load itself, being the cause to generate stress, which develops near liquid surface in a nuclear reactor wall and to contribute to further improvement of safety. A partition member (5) is arranged above a coolant liquid surface (9) in an annulus space (3) between a reactor vessel (1) and a guard vessel (2), a low-temperature gas is circulated through the annulus space above the partition member to cool down, the gas is circulated through the annulus space from under the coolant liquid surface to the partition member, and the high-temperature gas heated under the coolant liquid surface is used to raise the temperature above the coolant liquid surface.
    Type: Grant
    Filed: April 5, 2002
    Date of Patent: July 15, 2003
    Assignee: Japan Nuclear Cycle Development Institute
    Inventors: Naoto Kasahara, Masanori Ando
  • THERMAL LOAD REDUCING SYSTEM FOR NUCLEAR REACTOR VESSEL
    Publication number: 20030095620
    Abstract: The present invention is used to reduce thermal load itself, being the cause to generate stress, which develops near liquid surface in a nuclear reactor wall and to contribute to further improvement of safety. A partition member (5) is arranged above a coolant liquid surface (9) in an annulus space (3) between a reactor vessel (1) and a guard vessel (2), a low-temperature gas is circulated through the annulus space above the partition member to cool down, the gas is circulated through the annulus space from under the coolant liquid surface to the partition member, and the high-temperature gas heated under the coolant liquid surface is used to raise the temperature above the coolant liquid surface.
    Type: Application
    Filed: April 5, 2002
    Publication date: May 22, 2003
    Applicant: Japan Nuclear Cycle Development Institute
    Inventors: Naoto Kasahara, Masanori Ando