Ge-hitachi Nuclear Energy Americas LLC

General Electric Company

Yogeshwar Dayal

Steven Dale Sawyer

William Francis Splichal, Jr

Bruce John Lentner

Mark Heinold

Martin W Brittingham

Eric Rankin Gardner

Philip O Eisermann

Jack Toshio Matsumoto

John F Berger

Gary A Runkle

Lealon C Wimpee

Walter K Green

Earl F Saito

John P Sturtz

John P Niessel

Shelton Steinle

Jonathan R Earnhart

Jeffrey M Hare

Stephen K Morales

Keith D Requard

Andrew F Fidler

William Francis Splichal Jr

Mark R Heinold

Bruce J Lentner

A remote pulse TDR liquid level measurement system and method may include inserting a probe into a body of water. The probe has a probe/air interface, and the body of water includes an air/water interface. A narrow pulse is remotely transmitted to the probe via a coaxial cable. A first impedance mismatch is received from the probe/air interface in a form of a positive reflected pulse, and a second impedance mismatch is received from the air/water interface in a form of a negative reflected pulse. A time between the positive reflected pulse and the negative reflected pulse is calculated, and the time is converted to a distance, the distance being indicative of the water level.

Systems and methods for remotely measuring a liquid level using time-domain reflectometry (TDR)

A system for measuring a level of a liquid may include a receptacle, a probe, a pulsing unit, and a digitizer. The receptacle has a top and a bottom and is configured to contain the liquid. The probe may extend into the receptacle through the bottom. The pulsing unit is configured to transmit a pulse to the probe. The digitizer is configured to receive at least a first reflected pulse and a second reflected pulse from the probe. The time between the first reflected pulse and the second reflected pulse may be calculated and converted to a distance that is indicative of the level of the liquid in the receptacle.

System and method using time-domain reflectometry to measure a level of a liquid

Apparatuses and methods produce radioisotopes in instrumentation tubes of operating commercial nuclear reactors. Irradiation targets may be inserted and removed from instrumentation tubes during operation and converted to radioisotopes otherwise unavailable during operation of commercial nuclear reactors. Example apparatuses may continuously insert, remove, and store irradiation targets to be converted to useable radioisotopes or other desired materials at several different origin and termination points accessible outside an access barrier such as a containment building, drywell wall, or other access restriction preventing access to instrumentation tubes during operation of the nuclear plant.

Systems and methods for processing irradiation targets through a nuclear reactor

Systems produce desired isotopes through irradiation in nuclear reactor instrumentation tubes and deposit the same in a robust facility for immediate shipping, handling, and/or consumption. Irradiation targets are inserted and removed through inaccessible areas without plant shutdown and placed in the harvesting facility, such as a plurality of sealable and shipping-safe casks and/or canisters. Systems may connect various structures in a sealed manner to avoid release of dangerous or unwanted matter throughout the nuclear plant, and/or systems may also automatically decontaminate materials to be released. Useable casks or canisters can include plural barriers for containment that are temporarily and selectively removable with specially-configured paths inserted therein. Penetrations in the facilities may limit waste or pneumatic gas escape and allow the same to be removed from the systems without over-pressurization or leakage. Methods include processing irradiation targets through such systems and securely delivering them in such harvesting facilities.

Systems and methods for harvesting and storing materials produced in a nuclear reactor

A retainer is placed on a conduit to control movement of objects within the conduit in access-restricted areas. Retainers can prevent or allow movement in the conduit in a discriminatory fashion. A fork with variable-spacing between prongs can be a retainer and be extended or collapsed with respect to the conduit to change the size of the conduit. Different objects of different sizes may thus react to the fork differently, some passing and some being blocked. Retainers can be installed in inaccessible areas and allow selective movement in remote portions of conduit where users cannot directly interface, including below nuclear reactors. Position detectors can monitor the movement of objects through the conduit remotely as well, permitting engagement of a desired level of restriction and object movement. Retainers are useable in a variety of nuclear power plants and with irradiation target delivery, harvesting, driving, and other remote handling or robotic systems.

Systems and methods for retaining and removing irradiation targets in a nuclear reactor

Assuming knowledge of the number and species of gases present within an enclosed environment such as the atmosphere of a containment vessel of a nuclear plant, an apparatus and process for receiving a gas sample from said atmosphere and measuring the percentages of the various known number and species of gases present is disclosed. Assuming N number of gas species present, N-1 discrete chambers are utilized. Each chamber confines the sample gas, includes a discrete permeation cell having an internal volume isolated from the rest of the chamber by a permeable membrane, and has a pressure sensor for measuring the pressure within the permeation cell resulting from gas permeating through the permeable membrane. Each chamber is isothermal and maintained at its own discrete temperature. Sample gas is introduced into each chamber and allowed to come to equilibrium with the temperature of the chamber. When thermal equilibrium is attained, the permeation cell in each chamber is evacuated by a vacuum pump. Thereafter, gas permeation through each membrane occurs for a given and measured period of time. This period of time is chosen so that the pressure buildup resulting from gas permeating into the cell is but a small fraction of the total sample gas pressure in each chamber. Thereafter, the permeation rates for each cell at each cell's temperature together with the total sample gas pressure are solved in a simultaneous equation format to determine the percentage of each of the N gas species present.

Permeation cell gas detector

A method and apparatus for monitoring the output of an ion chamber type in-core neutron detector is disclosed. Neutron detectors of this type are known to produce both alternating current and direct current signals which are used as measures of the neutron flux in the chamber. The monitor employs a ratio of the alternating current and direct current signals to detect ion chamber leaks, to correct the output of the detector after a leak, to predict the end-of-life of the detector and to determine the non-linearity of the detector at different power levels.

Method and apparatus for monitoring the output of a neutron detector

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San Jose, CA, United States of America

Yogeshwar Dayal