Reactivity of High Plutonium-containing Glasses for the Immobilization of Surplus Fissile Materials PDF Download

Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Reactivity of High Plutonium-containing Glasses for the Immobilization of Surplus Fissile Materials PDF full book. Access full book title Reactivity of High Plutonium-containing Glasses for the Immobilization of Surplus Fissile Materials by . Download full books in PDF and EPUB format.

Reactivity of High Plutonium-containing Glasses for the Immobilization of Surplus Fissile Materials

Reactivity of High Plutonium-containing Glasses for the Immobilization of Surplus Fissile Materials PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


Reactivity of High Plutonium-containing Glasses for the Immobilization of Surplus Fissile Materials

Reactivity of High Plutonium-containing Glasses for the Immobilization of Surplus Fissile Materials PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


Performance of High Plutonium-containing Glasses for the Immobilization of Surplus Fissile Materials

Performance of High Plutonium-containing Glasses for the Immobilization of Surplus Fissile Materials PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 9

Book Description
Plutonium from dismantled weapons is being evaluated for geological disposal. While a final waste form has not been chosen, borosilicate glass will be one of the waste forms to be evaluated. The reactivity of the reference blend glass containing the standard amount of Pu ((approximately)0.01 wt %) to be produced by the Defense Waste Processing Facility (DWPF) is compared to that of glasses made from the same nominal frit composition but doped with 2 and 7 wt % Pu, and also equal mole percentages of Gd2O3. The Gd is added to act as a neutron poison to address criticality concerns. The four different glasses have been reacted using the PCT-B method with a SA/V of 20,000 m−1 and the Argonne Vapor Hydration Test (VHT) method. Both test methods accelerate the reaction of the glass. PCT-B is used to determine the reactivity of the glass by analyzing the solution and reacted test components, while the VHT is used to evaluate the long-term reactivity of the glass and the distribution of Pu to secondary phases that will control the long-term reaction of the glass. The results of the tests with high levels of Pu are compared to those with the nominal levels to be produced in the standard DWPF glass.

The Office of Environmental Management Technical Reports

The Office of Environmental Management Technical Reports PDF Author:
Publisher:
ISBN:
Category : Environmental management
Languages : en
Pages : 972

Book Description


Radioactive Waste Management

Radioactive Waste Management PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 388

Book Description


Compositions and Durabilities of Glasses for Immobilization of Plutonium and Uranium

Compositions and Durabilities of Glasses for Immobilization of Plutonium and Uranium PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 10

Book Description
As the nuclear weapon arsenals of the United States and the Former Soviet Union are reduced, metric tonnage quantities of fissile material must be dispositioned. One of the potential disposition options for fissile weapons material is vitrification into a stable form -- essentially a plutonium or uranium single phase glass product. Savannah River Technology Center (SRTC) at Savannah River Site (SRS) is actively developing suitable glass formulations for the long term safe storage of plutonium and uranium. These investigations are also being extended to develop glasses for the stabilization and storage of kilogram amounts of neptunium, americium, and curium that are currently stored as solutions in the process canyons at SRS -- thus the glasses are called actinide glasses. SRTC is also in the process of developing a remote process demonstration which can produce metric tonnage quantities of the glasses. This paper discusses the chemical compositions and durabilities of two types of actinide glasses under development. One of the glasses is a borosilicate, and the other an iron phosphate. In this initial study thorium and uranium were used as the actinides. Because of the low radioactivity of these elements, the glasses could be prepared and tested on the bench top. In studies beginning in FY '95, glasses containing neptunium, plutonium, americium and curium will be produced. These glasses will be prepared and tested remotely in the shielded cells and glovebox facilities at Savannah River Technology Center. In the initial study, a considerable number (>20) of thorium and uranium bearing glasses have been prepared. An equivalent number of rare earth surrogate (non-radioactive) glasses have also been prepared and tested. The glasses were prepared by mixing dry chemicals and melting them at 1425C for the borosilicate glasses and at 1100C for the iron phosphate glasses. (Abstract Truncated).

Surplus Plutonium Disposition (DOE/EIS-0283) for Siting, Construction and Operation of Three Facilities for Plutonium Disposition

Surplus Plutonium Disposition (DOE/EIS-0283) for Siting, Construction and Operation of Three Facilities for Plutonium Disposition PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 488

Book Description


The Office of Environmental Management Technical Reports

The Office of Environmental Management Technical Reports PDF Author:
Publisher:
ISBN:
Category : Environmental management
Languages : en
Pages : 968

Book Description


Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 834

Book Description


Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries

Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries PDF Author:
Publisher:
ISBN:
Category : Ceramic industries
Languages : en
Pages : 736

Book Description
Consists of proceedings of various symposia held during the Annual Meeting of the American Ceramic Society.

Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel & Fissile Material Management, Reno, Nevada, June 16-20, 1996

Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel & Fissile Material Management, Reno, Nevada, June 16-20, 1996 PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 522

Book Description