Global Nuclear Fuel - Americas, LLC

Other

General Electric Company

Carey Reid Merritt

David Joseph Kropaczek

Steven Barry Sutton

Christian Carlos Oyarzun

William Earl Russell, Ii

William Charles Cline

John Dean Fuller

Margaret Estelle Harding

Behnam Pourdeyhimi

H Troy Nagle

Tae-Ho Kang

Glen Alan Watford

Edward R Grant

James W Winkelman

Burcak Karaguzel

Ruth Silberman-Hazony

The apparatus for creating and editing a nuclear reactor core template includes a graphical user interface and a processor controlling the graphical user interface to allow a user to selectively populate a loading map with fuel bundles residing in at least one fuel pool.

Method and apparatus for moving nuclear fuel

A capacitive sensor device, including electrode materials carried by fabric substrates, is provided for monitoring relative movement of an expanding and/or contracting structure, such as the mammalian chest and/or torso, corresponding to a performance parameter related, for example, to respiratory function. Some embodiments include non-woven fabric substrates comprising compliant portions configured to stretch only in a selected direction and non-compliant portions upon which electrode materials are disposed. In some embodiments, layers of fabric substrates, carrying corresponding first and second electrode materials, are configured to cooperate to form a parallel plate capacitive sensor having a variable capacitance corresponding to a relative motion of the fabric substrates.

Sensor device for real-time monitoring or relative movement using capacitive fabric sensors

Method and apparatus for facilitating recovery of nuclear fuel from a fuel pool

The apparatus for creating and editing a nuclear reactor core template includes a graphical user interface and a processor controlling the graphical user interface to display a graphical representation of a nuclear reactor core. Via the graphical user interface, the processor provides a user with graphical tools for at least one of assigning fuel bundle categories to fuel bundle positions in the graphical representation and editing assigned fuel bundle categories to the fuel bundle positions in the graphical representation.

Method and apparatus for creating and editing a nuclear reactor core loading template

In the method, a set of limits applicable to a core may be defined, and a test core loading pattern design, to be used for loading the core, may be determined based on the limits. Reactor operation on at least a subset of the core may be simulated to produce a plurality of simulated results. The simulated results may be compared against the limits, and data from the comparison may indicate whether any of the limits were violated by the core during the simulation. A designer or engineer may use the data to modify the test core loading pattern, creating one or more derivative core loading pattern design(s) for simulation and eventual perfection as an acceptable core loading pattern design for the core.

Method and arrangement for developing core loading patterns in nuclear reactors

In the method, a set of limits applicable to a test rod pattern design are defined, and a sequence strategy for positioning one or more subsets of the test rod pattern design is established. Reactor operation on a subset of the test rod pattern design, which may be a subset of fuel bundles in a reactor core for example, is simulated to produce a plurality of simulated results. The simulated results are compared against the limits, and data from the comparison is provided to indicate whether any of the limits were violated by the test rod pattern design during the simulation. A designer or engineer may use the data to determine which operator parameters need to be adjusted (e.g., control blade notch positions for example) in order to create a derivative rod pattern design for simulation, and eventually perfect a rod pattern design for a particular core.

Method and arrangement for developing rod patterns in nuclear reactors

New compounds are described of the formula: ##STR1## wherein Z is selected from ##STR2## each x is selected from ##STR3## n is an integer from 1-10; each Y is selected from hydrogen, --NH.sub.2, --COQ, --COOQ, --COONHQ, --COOH, --OH, W, halogen and Q; wherein each Q is independently selected from substituted and unsubstituted lower alkenyl and lower alkyl and wherein the substitutuents are selected from --NH.sub.2 halogen, --OH, and --COOH; D is selected from hydroxy, hydrogen and --NH.sub.2 ; and W is selected from ##STR4## wherein each R is independently selected from hydrogen and lower alkyl; R' is selected from ethylene, propylene, isopropylene and phenylene; M is selected from chlorine and hydroxy; A is selected from hydrogen, lower alkyl, lower alkenyl, cycloalkyl, and phenyl; (B) is selected from ##STR5## --CO--, --NHCO--, --O--, --COO--, --N.dbd.N--, or represents a confugate bond; L.sub.1 and L.sub.2 are selected from hydroxy substituted or unsubstituted lower alkyl, cycloalkyl, lower alkenyl, or phenyl; providing L.sub.2 can be a conjugate bond. These compounds have specific utility in a process, for measuring c-reactive protein by binding with c-reactive protein and acting to release metal ions and/or inhibit the flow of the metal ion complex under electrochemically measurable conditions.

Compounds and process for measuring c-reactive protein

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Wilmington, NC, United States of America

Carey Reid Merritt