摘要:
The present invention is for a fiber optic flow cell. The flow cell comprises a substrate having at least one sample channel and at least one optical fiber channel holder. At least one optical fiber is disposed within each optical fiber channel holder. Each optical fiber has at least one grating wherein each grating is in contact with each sample channel, defining a sensing area. At least one sample port is positioned in an operable relationship to at least one sample channel. Alternatively, at least one sample outlet is positioned in an operable relationship to at least one sample channel. The flow cell may be of a modular design providing a flow cell kit that contains pieces that may be assembled to form custom-made flow cells. The flow cell is used for conducting measurement studies on a sample.
摘要:
A system and method for increasing claim recovery efficiency wherein an input engine receives claim data and is operatively coupled to both a clearinghouse system and an accounts receivable management system, which systems cooperatively identify errors in the claim record and prevent erred claim records from progressing to a payor. The clearinghouse system provides supplementation of the claim data for each claim record with additional data useful in electronic invoicing, assembly of claims for electronic invoicing, and submittal of claims for payment electronically. The clearinghouse is interactively coupled with the accounts receivable management system, which establishes and maintains an activity record for recovery efforts of each claim record, records process progression of each claim, coordinates error correction action, and assembles final disposition of each claim
摘要:
Disclosed are methods for assuring that requirements for fissile material transportation are met to comply with the double contingency principle for preventing nuclear criticality by excluding moderator in-leakage. In one embodiment, a method includes designing and fabricating a canister to achieve an acceptable application, and verifying pre-shipment operation to assure that a transport system is properly assembled to meet its licensed transport configuration.
摘要:
A transport or storage cask comprises a cask body, a modular thermal conducting and shielding system and a mechanical attachment. The modular thermal conducting and shielding system includes a modular fin and a modular neutron shield. The mechanical attachment retains the modular thermal conducting and shielding system to the cask body. The modular fin is disposed between the modular neutron shield and the cask body. The modular fin is capable of dissipating thermal energy from the cask body.
摘要:
Disclosed are the apparatus and methods for closing a canister that stores and transports spent nuclear fuel. In one embodiment, the canister includes a canister shell that includes an open end. A closure lid is inserted within the open end of the canister shell. The closure lid engages the open end of the canister shell to provide a weld area that is substantially on the outer circumference of the closure lid. The weld area includes a first weld layer and a second weld layer. The first weld layer welds the closure lid to the canister shell at the weld area and closes the canister. The second weld layer also welds the closure lid to the canister shell at the weld area, providing a redundant closure seal, and is disposed substantially on top of the first weld layer. The method for closing the canister is provided herein.
摘要:
Disclosed are methods for transporting and canistering nuclear spent fuel. In one embodiment, the method for transporting and canistering nuclear spent fuel comprises providing a canister that includes a mechanical closure for a lid on a container. The canister containing the nuclear spent fuel is loaded into a transport cask, and the transport cask is sealed at the power plant. It is preferred that the lid is not installed on the canister at the power plant. The transport cask containing the canister and nuclear spent fuel is transported to a remote facility. At the remote facility, the transport cask is opened and the lid of the canister is installed using the mechanical closure to seal the canister after the canister is transported to the remote facility. The canister containing the spent nuclear fuel is placed into an overpack, which is stored at the remote facility.