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Remote Handling in the Plutonium Immobilization Project -- Second Stage Immobilization

Remote Handling in the Plutonium Immobilization Project -- Second Stage Immobilization PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
The Savannah River Site (SRS) will immobilize excess plutonium in ceramic pucks and seal the pucks inside welded cans. Automated equipment will place these cans in magazines and the magazines in a Defense Waste Processing Facility (DWPF) canister. The DWPF will fill the canister with glass for permanent storage. Due to the radiation, remote equipment will perform these operations in a contained environment. The Plutonium Immobilization Project is in the conceptual design stage and the facility will begin operation in 2008. This paper discusses the Plutonium Immobilization Project phase 2 automation equipment conceptual design, equipment design, and work completed.

Remote Handling in the Plutonium Immobilization Project -- Second Stage Immobilization

Remote Handling in the Plutonium Immobilization Project -- Second Stage Immobilization PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
The Savannah River Site (SRS) will immobilize excess plutonium in ceramic pucks and seal the pucks inside welded cans. Automated equipment will place these cans in magazines and the magazines in a Defense Waste Processing Facility (DWPF) canister. The DWPF will fill the canister with glass for permanent storage. Due to the radiation, remote equipment will perform these operations in a contained environment. The Plutonium Immobilization Project is in the conceptual design stage and the facility will begin operation in 2008. This paper discusses the Plutonium Immobilization Project phase 2 automation equipment conceptual design, equipment design, and work completed.

Remote Handling in the Plutonium Immobilization Project

Remote Handling in the Plutonium Immobilization Project PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
Since the break up of the Soviet Union at the end of the Cold War, the US and Russia have been negotiating ways to reduce their nuclear stockpiles. Economics is one of the reasons behind this, but another important reason is safeguarding these materials from unstable organizations and countries. With the downsizing of the nuclear stockpiles, large quantities of plutonium are being declared excess and must be safely disposed of. The Savannah River Site (SRS) has been selected as the site where the immobilization facility will be located. Conceptual design and process development commenced in 1998. SRS will immobilize excess plutonium in a ceramic waste form and encapsulate it in vitrified high level waste in the Defense Waste Processing Facility (DWPF) canister. These canisters will then be interred in the national repository at Yucca Mountain, New Mexico. The facility is divided into three distinct operating areas: Plutonium Conversion, First Stage Immobilization, and Second Stage Immobilization. This paper will discuss the first two operations.

Remote Material Handling in the Plutonium Immobilization Project. Revision 1

Remote Material Handling in the Plutonium Immobilization Project. Revision 1 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
With the downsizing of the US and Russian nuclear stockpiles, large quantities of weapons-usable plutonium in the US are being declared excess and will be disposed of by the Department of Energy Fissile Materials Disposition Program. To implement this program, DOE has selected the Savannah River Site (SRS) for the construction and operation of three new facilities: pit disassembly and conversion; mixed oxide fuel fabrication; and plutonium immobilization. The Plutonium Immobilization Project (PIP) will immobilize a portion of the excess plutonium in a hybrid ceramic and glass form containing high level waste for eventual disposal in a geologic repository. The PIP is divided into three distinct operating areas: Plutonium Conversion, First Stage Immobilization, and Second Stage Immobilization. Processing technology for the PIP is being developed jointly by the Lawrence Livermore National Laboratory and Westinghouse Savannah River Company. This paper will discuss development of the automated unpacking and sorting operations in the conversion area, and the automated puck and tray handling operations in the first stage immobilization area. Due to the high radiation levels and toxicity of the materials to be disposed of, the PIP will utilize automated equipment in a contained (glovebox) facility. Most operations involving plutonium-bearing materials will be performed remotely, separating personnel from the radiation source. Source term materials will be removed from the operations during maintenance. Maintenance will then be performed hands on within the containment using glove ports.

Plutonium Immobilization Project - Can-In-Canister Hardware Development

Plutonium Immobilization Project - Can-In-Canister Hardware Development PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
The Plutonium Immobilization Project (PIP) is a program funded by the U.S. Department of Energy to develop technology to disposition excess weapons grade plutonium. This program introduces the ''Can-in-Canister'' (CIC) technology that immobilizes the plutonium by encapsulating it in ceramic forms (or pucks) and ultimately surrounding it with high-level waste glass to provide a deterrent to recovery. Since there are significant radiation, contamination and security concerns, the project team is developing unique technologies to remotely perform plutonium immobilization tasks. This paper covers the design, development and testing of the magazines (cylinders containing cans of ceramic pucks) and the rack that holds them in place inside the waste glass canister. Several magazine and rack concepts were evaluated to produce a design that gives the optimal balance between resistance to thermal degradation and facilitation of remote handling. This paper also reviews the effort to develop a join ted arm robot that can remotely load seven magazines into defined locations inside a stationary canister working only through the 4 inch (102 mm) diameter canister throat.

Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management, San Diego, California, June 4-8, 2000

Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management, San Diego, California, June 4-8, 2000 PDF Author:
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 556

Book Description


Plutonium Disposition by Immobilization

Plutonium Disposition by Immobilization PDF Author:
Publisher:
ISBN:
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.

Plutonium Immobilization Project -- Robotic Canister Loading

Plutonium Immobilization Project -- Robotic Canister Loading PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
The Plutonium Immobilization Program (PIP) is a joint venture between the Savannah River Site (SRS), Lawrence Livermore National Laboratory (LLNL), Argonne National Laboratory (ANL), and Pacific Northwest National Laboratory (PNNL). When operational in 2008, the PIP will fulfill the nation's nonproliferation commitment by placing surplus weapons-grade plutonium in a permanently stable ceramic form and making it unattractive for reuse. Since there are significant radiation and security concerns, the program team is developing novel and unique technology to remotely perform plutonium immobilization tasks. The remote task covered in this paper employs a jointed arm robot to load seven 3.5 inch diameter, 135-pound cylinders (magazines) through the 4 inch diameter neck of a stainless steel canister. Working through the narrow canister neck, the robot secures the magazines into a specially designed rack pre-installed in the canister. To provide the deterrent effect, the canisters are filled with a mixture of high-level waste and glass at the Defense Waste Processing Facility (DWPF).

Material Transfer System in Support of the Plutonium Immobilization Program

Material Transfer System in Support of the Plutonium Immobilization Program PDF 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.

Plutonium Immobilization Project -- Can Loading

Plutonium Immobilization Project -- Can Loading PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
The Savannah River Site (SRS) will immobilize excess plutonium in the proposed Plutonium Immobilization Project (PIP). The PIP scope includes unloading transportation containers, preparing the feed streams, converting the metal feed to an oxide, adding the ceramic precursors, pressing the pucks, inspecting pucks, and sintering pucks. The PIP scope also includes loading the pucks into metal cans, sealing the cans, inspecting the cans, loading the cans into magazines, loading magazines into Defense Waste Processing Facility (DWPF) canisters, and transporting the canisters to the DWPF. The DWPF fills the canister with a mixture of high level radioactive waste and glass for permanent storage. Due to the radiation, remote equipment must perform PIP operations in a contained environment.

Plutonium Immobilization Project - Cold Pour Phase 2 Test Results

Plutonium Immobilization Project - Cold Pour Phase 2 Test Results PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
The Plutonium Immobilization Project (PIP) is a program funded by the U.S. Department of Energy to develop technology for dispositioning excess weapons grade plutonium. This program introduces the ''Can-in-Canister'' (CIC) technology that immobilizes the plutonium by encapsulating it in ceramic forms (or pucks) and ultimately surrounding it with high-level waste glass to provide a deterrent to recovery. A cold (non-radioactive) test program was conducted to develop and verify the baseline design for the canister and internal hardware. Tests were conducted in two phases. Phase 1 Cold Pour Tests, conducted in 1999, were scoping tests. This paper describes the Phase 2 tests conducted in 2000 which verified the adequacy of the baseline CIC design and assured that the system would meet repository quality assurance requirements.