Supplement Analysis for the Immobilization of Plutonium-bearing Materials at the Plutonium Finishing Plant, Hanford Site, Richland, Washington

Supplement Analysis for the Immobilization of Plutonium-bearing Materials at the Plutonium Finishing Plant, Hanford Site, Richland, Washington PDF Author: United States. Department of Energy. Richland Operations Office
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Category : Plutonium
Languages : en
Pages : 6

Book Description


Supplement Analysis

Supplement Analysis PDF Author: United States. Department of Energy. Richland Operations Office
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Category : Plutonium as fuel
Languages : en
Pages : 0

Book Description


Sludge Stabilization at the Plutonium Finishing Plant, Hanford Site, Richland, Washington

Sludge Stabilization at the Plutonium Finishing Plant, Hanford Site, Richland, Washington PDF Author:
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Category :
Languages : en
Pages :

Book Description


Plutonium Immobilization Material Characterization

Plutonium Immobilization Material Characterization PDF Author:
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Category :
Languages : en
Pages :

Book Description
The objective of this task is to analyze impure oxide materials exiting from front-end processing prior to storage for feed blending. There are three goals to be accomplished with this task: reduce reblending (currently projected at 7% with an optimized ordering of the incoming material streams), determine if impure feed prep operations are performing adequately, and reduce plant operating costs by replacing wet prep elemental analyses whether conducted in the immobilization facility or in existing laboratories. An additional potential application is the analysis of blended oxide prior to first-stage UO2 and precursor addition.

Plutonium Recycle Critical Facility Final Safeguards Analysis

Plutonium Recycle Critical Facility Final Safeguards Analysis PDF Author: F. Swanberg
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Category : Nuclear reactors
Languages : en
Pages : 126

Book Description


An Analysis of Plutonium Immobilization Versus the "spent Fuel" Standard

An Analysis of Plutonium Immobilization Versus the Author:
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Category :
Languages : en
Pages :

Book Description
Safe Pu management is an important and urgent task with profound environmental, national, and international security implications. Presidential Policy Directive 13 and analyses by scientific, technical, and international policy organizations brought about a focused effort within the Department of Energy (DOE) to identify and implement long-term disposition paths for surplus Pu. The principal goal is to render surplus Pu as inaccessible and unattractive for reuse in nuclear weapons as Pu in spent reactor fuel. In the Programmatic Environmental Impact Statement and Record of Decision for the Storage and Disposition of Weapons- Usable Fissile Materials (1997), DOE announced pursuit of two disposition technologies: (1) irradiation of Pu as MOX fuel in existing reactors and (2) immobilization of Pu into solid forms containing fission products as a radiation barrier. DOE chose an immobilization approach that includes use of the can-in-canister option. . for a portion of the surplus, non-pit Pu material. In the can-in-canister approach, cans of glass or ceramic forms containing Pu are encapsulated within canisters of HLW glass. In support of the selection process, a technical evaluation of retrievability and recoverability of Pu from glass and ceramic forms by a host nation and by rogue nations or subnational groups was completed. The evaluation involved determining processes and flowsheets for Pu recovery, comparing these processes against criteria and metrics established by the Fissile Materials Disposition Program and then comparing the recovery processes against each other and against SNF processes.

Integrated Development and Testing Plan for the Plutonium Immobilization Project

Integrated Development and Testing Plan for the Plutonium Immobilization Project PDF Author:
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Category :
Languages : en
Pages : 180

Book Description
This integrated plan for the DOE Office of Fissile Materials Disposition (MD) 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 (D & T) tasks needed to provide technical data for design and operation of a plutonium immobilization plant based on the ceramic can-in-canister technology (''Immobilization Fissile Material Disposition Program Final Immobilization Form Assessment and Recommendation'', UCRL-ID-128705, October 3, 1997). 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 D & T 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 (RW) to incorporate the plutonium form in the repository licensing application are provided in this document, together with a summary of how immobilization D & T activities provide input to the license activity. The ultimate goal of the Immobilization Project is to develop, construct, and operate facilities that will immobilize from about 18 to 50 tonnes (MT) of U.S. surplus weapons usable plutonium materials in a manner that meets the ''spent fuel'' standard (Fissile Materials Storage and Disposition Programmatic Environmental Impact Statement Record of Decision, ''Storage and Disposition Final PEIS'', issued January 14, 1997, 62 Federal Register 3014) and is acceptable for disposal in a geologic repository. In the can-in-canister technology, this is accomplished by encapsulating the plutonium-containing ceramic forms within large canisters of high level waste (HLW) glass. Deployment of the immobilization capability should occur by 2006 and be completed within 10 years.

CSER 01-008 Canning of Thermally Stabilized Plutonium Oxide Powder in PFP Glovebox HC-21A.

CSER 01-008 Canning of Thermally Stabilized Plutonium Oxide Powder in PFP Glovebox HC-21A. PDF Author:
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Category :
Languages : en
Pages : 64

Book Description
This document presents the analysis performed to support the canning operation in HC-21A. Most of the actual analysis was performed for the operation in HC-18M and HA-20MB, and is documented in HNF-2707 Rev I a (Erickson 2001a). This document will reference Erickson (2001a) as necessary to support the operation in HC-21A. The plutonium stabilization program at the Plutonium Finishing Plant (PFP) uses heat to convert plutonium-bearing materials into dry powder that is chemically stable for long term storage. The stabilized plutonium is transferred into one of several gloveboxes for the canning process, Gloveboxes HC-18M in Room 228'2, HA-20MB in Room 235B, and HC-21A in Room 230B are to be used for this process. This document presents the analysis performed to support the canning operation in HC-21A. Most of the actual analysis was performed for the operation in HC-I8M and HA-20MB, and is documented in HNF-2707 Rev l a (Erickson 2001a). This document will reference Erickson (2001a) as necessary to support the operation in HC-21A. Evaluation of this operation included normal, base cases, and contingencies. The base cases took the normal operations for each type of feed material and added the likely off-normal events. Each contingency is evaluated assuming the unlikely event happens to the conservative base case. Each contingency was shown to meet the double contingency requirement. That is, at least two unlikely, independent, and concurrent changes in process conditions are required before a criticality is possible.

Hydroxylamine Nitrate Reduction of Plutonium (IV)

Hydroxylamine Nitrate Reduction of Plutonium (IV) PDF Author: G. Scott Barney
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Category : Hydroxylamine
Languages : en
Pages : 24

Book Description


Plutonium Disposition by Immobilization

Plutonium Disposition by Immobilization PDF Author:
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Category :
Languages : en
Pages :

Book Description
The ultimate goal of the Department of Energy (DOE) Immobilization Project is to develop, construct, and operate facilities that will immobilize between 17 to 50 tonnes (MT) of U.S. surplus weapons-usable plutonium materials in waste forms that meet the ''spent fuel'' standard and are acceptable for disposal in a geologic repository. Using the ceramic can-in-canister technology selected for immobilization, surplus plutonium materials will be chemically combined into ceramic forms which will be encapsulated within large canisters of high level waste (HLW) glass. Deployment of the immobilization capability should occur by 2008 and be completed within 10 years. In support of this goal, the DOE Office of Fissile Materials Disposition (MD) is conducting development and testing (D & T) activities at four DOE laboratories under the technical leadership of Lawrence Livermore National Laboratory (LLNL). The Savannah River Site has been selected as the site for the planned Plutonium Immobilization Plant (PIP). The D & T effort, now in its third year, will establish the technical bases for the design, construction, and operation of the U.S. capability to immobilize surplus plutonium in a suitable and cost-effective manner. Based on the D & T effort and on the development of a conceptual design of the PIP, automation is expected to play a key role in the design and operation of the Immobilization Plant. Automation and remote handling are needed to achieve required dose reduction and to enhance operational efficiency.