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Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
As an integral part of the plutonium disposition program, formulation and process development is being performed for the immobilization of surplus plutonium in a titanate-based ceramic. Small-scale process prototypic and lab-scale functionally prototypic equipment have been tested to help define the immobilization process. The testing has included non-radioactive surrogates and actual actinide oxides contained in the immobilized form. A summary of the process development studies, as well as the formulation studies relevant to the process, will be provided.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
As an integral part of the plutonium disposition program, formulation and process development is being performed for the immobilization of surplus plutonium in a titanate-based ceramic. Small-scale process prototypic and lab-scale functionally prototypic equipment have been tested to help define the immobilization process. The testing has included non-radioactive surrogates and actual actinide oxides contained in the immobilized form. A summary of the process development studies, as well as the formulation studies relevant to the process, will be provided.
Author: Publisher: ISBN: Category : Languages : en Pages : 5
Book Description
This report gives an overview of the Ceramic Prototype Testing Facility (CPTF) objectives and process and also details the development of the key pieces of equipment. Westinghouse Savannah River Company (WSRC), in cooperation with the Clemson Environmental Technologies Laboratory (CETL) is developing the CPTF in support of the Plutonium Immobilization Program (PIP), a Department of Energy (DOE) initiative.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The Plutonium Immobilization Project (PIP) is one of several fissile materials disposition projects managed by the Department of Energy (DOE) Office of Fissile Materials Disposition (OFMD). The PIP is expected to evolve from the current Development and Testing (D and T) effort, to design, to construction, and finally to operations. Overall management and technical management of the D and T effort resides at the Lead Laboratory, Lawrence Livermore National Laboratory (LLNL), through the LLNL Manager, Fissile Materials Disposition Program (FMDP). Day to day project activities are managed by the D and T Technical Project Office (TPO), which reports to the LLNL Manager, FMDP. The D and T TPO consists of the Technical Manager, the TPO Quality Assurance (QA) Program Manager, and TPO Planning and Support Staff. This Quality Assurance Program Description (QAPD) defines the QA policies and controls that will be implemented by these TPO personnel in their management of D and T activities. This QAPD is consistent with and responsive to the Department of Energy Fissile Materials Disposition Program Quality Assurance Requirements Document (FMDP QARD). As the Project and upper level requirement's documents evolve, this QAPD will be updated as necessary to accurately define and describe the QA Program and Management of the PIP. The TPO has a policy that all development and testing activities be planned, performed and assessed in accordance with its customer's requirements, needs and expectations, and with a commitment to excellence and continuous improvement. The TPO QAPD describes implementation requirements which, when completed, will ensure that the project development and testing activities conform to the appropriate QA requirements. For the program to be effective, the TPO QA Program Manager will ensure that each site participating in D and T activities has developed a QAPD, which meets the customer's requirements, and has a designated quality leader in place. These customer requirements, needs, and expectations are defined in the FMDP QARD. Compliance with the TPO QAPD and procedures will ensure that our D and T deliverables meet the high standards of quality expected by the Department of Energy.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
This integrated plan for the DOE Office of Fissile Materials Disposition describes the technology development and major project activities necessary to support the deployment of the immobilization approach for disposition of surplus weapons-usable plutonium. The plan describes details of the development and testing tasks needed to provide technical data for design and operation of a plutonium immobilization plant based on the ceramic can-in-canister technology. The plan also presents tasks for characterization and performance testing of the immobilization form to support a repository licensing application and to develop the basis for repository acceptance of the plutonium form. Essential elements of the plant project (design, construction, facility activation, etc.) are described, but not developed in detail, to indicate how the test results tie into the overall plant project. Given the importance of repository acceptance, specific activities to be conducted by the Office of Civilian Radioactive Waste Management to incorporate the plutonium form in the repository licensing application are provided in this document, together with a summary of how immobilization activities provide input to the license activity and waste qualification. The ultimate goal of the immobilization project is to develop, construct, and operate facilities that will immobilize from about 18 to 50 tonnes of US surplus plutonium materials in a manner that meets the ''spent fuel'' standard and is acceptable for disposal in a geologic repository. The can-in-canister technology is accomplished by encapsulating the plutonium-containing ceramic forms within large canisters of high level waste glass.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Contained within this report are summaries of the available interim and final data summary reports provided by ANSTO, ANL, LLNL, and WSRC in support of work in the Form Development activity in the Plutonium Immobilization Development and Testing Program. Milestone reports and technical papers prepared for journals or conference proceedings are not included in this list. This document covers work from about 1997 to the present. All of the following reports are available from the Plutonium Immobilization Program Document Control Center (DCC) at LLNL. In most cases, the documents can also be obtained from the libraries the originating site or from the document's authors. All samples of the various formulations discussed in the following summaries were prepared by one of four processes: Wet-milling, dry-milling, an alkoxide-nitrate process, or attritor milling. The fabrication processes differ primarily in the mixing steps. The wet milling process is the one most commonly used. It is a simple ball milling process where water is added that provides intimate mixing of the materials. The dry milling process is a worst case dry mixing process. The alkoxide-nitrate process provides for very intimate mixing and is used when equilibrium samples are desired. The attritor milling process simulates the process being developed for the Plutonium Immobilization Plant. After mixing, the subsequent calcination and consolidation steps are generally the same. Most samples were consolidated by cold pressing and sintering although some of the earlier samples or Some of the single-phase samples were prepared by hot pressing. The sample identification numbers (ID's) that are referenced in the summaries (e.g. A-0, B3-13, etc.) are described in the Sample Test Matrix (PIP-99-012 and PIP-00-016). Samples which contain both plutonium and uranium are given the designation Hf-Pu-U samples. When Ce was used as a surrogate for Pu, the designation is Hf-Ce-U. When Th was used as a surrogate for Pu, the designation is Hf-Th-U. When Ce was used as a surrogate for Pu and U, the designation is Hf-Ce-Ce. Lastly, when Zr was used as a surrogate for Hf and Ce was used as a surrogate for Pu and U, the designation is Zr-Ce-Ce.
Author: Publisher: ISBN: Category : Languages : en Pages : 5
Book Description
In FY00, a matrix for process development testing was created to identify those items related to the ceramic process that had not been fully developed or tested and to help identify variables that needed to be tested. This matrix, NMTP/IP-99-003, was jointly created between LLNL and SRTC and was issued to all affected individuals. The matrix was also used to gauge the progress of the development activities. As part of this matrix, several series of tests were identified for the granulation process. This summary provides the data and results from the granulation testing. The results of the granulation matrix testing were used to identify the baseline process for testing in the PuCTF with cold surrogates in B241 at LLNL.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
''The quality assurance activity involves the establishment and implementation of the Quality Assurance Program and the development of a Quality Assurance Plan and Procedures. Quality Assurance provides the plans, procedures and controls that are required for repository acceptance and the immobilization plant licensing and design activities.'' The Plutonium Immobilization Project (PIP) has a policy that all development, testing and operational activities be planned and performed in accordance with its customer's needs and expectations, and with a commitment to excellence and continuous improvement. The Immobilization Development and Testing (D & T) Quality Assurance Program establishes implementation requirements which, when completed, will ensure that the program development and test activities conform to the appropriate QA requirements. In order for the program to be effective, a designated quality lead must be in place at the Project Office and each participating site.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The Plutonium Immobilization Project is currently undertaking formulation and process development to demonstrate the immobilization of surplus plutonium in a titanate-based ceramic. These ceramic forms will be encapsulated within canisters containing high level waste glass for geologic disposal. Process development work is being conducted with sub-scale, process prototypic equipment. Final validation of the process will be done using actual plutonium material and functionally prototypic equipment within a glovebox. Due to the radioactive nature of the material, remote material handling is necessary to reduce the radiation exposure to the operators. A remote operated Material Transfer System to interface with process equipment has been developed.
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