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Hanford/Tomsk reciprocal site visit: Plutonium agreement compliance talks

Hanford/Tomsk reciprocal site visit: Plutonium agreement compliance talks

Date: November 1, 1994
Creator: Libby, R.A.; Sorenson, R.; Six, D. & Schiegel, S.C.
Description: The objective of the visit to Hanford Site was to: demonstrate equipment, technology, and methods for calculating Pu production, measuring integrated reactor power, and storing and safeguarding PuO{sub 2}; demonstrate the shutdown of Hanford production reactors; and foster openness and transparency of Hanford operations. The first day`s visit was an introduction to Hanford and a review of the history of the reactors. The second day consisted of discussions on the production reactors, reprocessing operations, and PuO{sub 2} storage. The group divided on the third day to tour facilities. Group A toured the N reactor, K-West reactor, K-West Basins, B reactor, and participated in a demonstration and discussion of reactor modeling computer codes. Group B toured the Hanford Pu Storage Facility, 200-East Area, N-cell (oxide loadout station), the Automated Storage Facility, and the Nondestructive Assay Measurement System. Group discussions were held during the last day of the visit, which included scheduling of a US visit to Russia.
Contributing Partner: UNT Libraries Government Documents Department
Proceedings -- US Russian workshop on fuel cell technologies

Proceedings -- US Russian workshop on fuel cell technologies

Date: April 1, 1996
Creator: Baker, B. & Sylwester, A.
Description: On September 26--28, 1995, Sandia National Laboratories sponsored the first Joint US/Russian Workshop on Fuel Cell Technology at the Marriott Hotel in Albuquerque, New Mexico. This workshop brought together the US and Russian fuel cell communities as represented by users, producers, R and D establishments and government agencies. Customer needs and potential markets in both countries were discussed to establish a customer focus for the workshop. Parallel technical sessions defined research needs and opportunities for collaboration to advance fuel cell technology. A desired outcome of the workshop was the formation of a Russian/American Fuel Cell Consortium to advance fuel cell technology for application in emerging markets in both countries. This consortium is envisioned to involve industry and national labs in both countries. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.
Contributing Partner: UNT Libraries Government Documents Department
Record of the first meeting of the Joint Coordinating Committee for Radiation Effects Research

Record of the first meeting of the Joint Coordinating Committee for Radiation Effects Research

Date: December 31, 1994
Creator: unknown
Description: This conference was held July 27--28, 1994 in Moscow. The main purpose of the meeting was to implement an agreement between the Russian Federation and the US to facilitate cooperative research on health and environmental effects of radiation. It was hoped that the exchange of information would provide a good basis for employing new scientific knowledge to implement practical measures to facilitate the rehabilitation of radioactively contaminated areas and to treat radiation illnesses. The Russian Federation suggested five main scientific areas for cooperative research. They will prepare proposals on 4--5 projects within the scope of the scientific areas discussed and forward them to the US delegation for consideration of the possibility to facilitate joint research.
Contributing Partner: UNT Libraries Government Documents Department
Saja orang Marine, toeroetlah saja! : Koninklijke Marine.

Saja orang Marine, toeroetlah saja! : Koninklijke Marine.

Date: unknown
Creator: unknown
Description: A young dark-haired man in a sailor's uniform smiles at the viewer. On the band of his hat are the words "Koninklijke Marine" (Royal Netherlands Navy). In the background is a ship with spotlights shining.
Contributing Partner: UNT Libraries Government Documents Department
Spatially fractionated microirradiation of normal CNS and gliosarcomas of the rat with synchrotron photons: Cell and tissue lesions; Raeumlich fraktionierte Mikrobestrahlung von normalem ZNS und Gliosarkomen der Ratte mit Synchrotron-Photonen: Zell- und Gewebelaesionen

Spatially fractionated microirradiation of normal CNS and gliosarcomas of the rat with synchrotron photons: Cell and tissue lesions; Raeumlich fraktionierte Mikrobestrahlung von normalem ZNS und Gliosarkomen der Ratte mit Synchrotron-Photonen: Zell- und Gewebelaesionen

Date: December 31, 1995
Creator: Laissue, J.A.; Spanne, P.; Dilmanian, F.A.; Nawrocky, M.N.; Slatkin, D.N.; Joel, D.D. et al.
Description: Rats were implanted intracerebrally with 9L gliosarcoma cells were used to experimentally determine the curative effectiveness of synchrotron radiation produced by the National Synchrotron Radiation Source. Radiation was delivered in beams with each ray 25 micrometers thick and arranged in an array of 4 mm corners. All experimental animals receiving the gliosarcoma cells and not treated died within four weeks. Treated animals surviving 113 days were sacrificed and their brains were examined histologically.
Contributing Partner: UNT Libraries Government Documents Department
The United States of America and the People`s Republic of China experts report on integrated gasification combined-cycle technology (IGCC)

The United States of America and the People`s Republic of China experts report on integrated gasification combined-cycle technology (IGCC)

Date: December 1, 1996
Creator: unknown
Description: A report written by the leading US and Chinese experts in Integrated Gasification Combined Cycle (IGCC) power plants, intended for high level decision makers, may greatly accelerate the development of an IGCC demonstration project in the People`s Republic of China (PRC). The potential market for IGCC systems in China and the competitiveness of IGCC technology with other clean coal options for China have been analyzed in the report. Such information will be useful not only to the Chinese government but also to US vendors and companies. The goal of this report is to analyze the energy supply structure of China, China`s energy and environmental protection demand, and the potential market in China in order to make a justified and reasonable assessment on feasibility of the transfer of US Clean Coal Technologies to China. The Expert Report was developed and written by the joint US/PRC IGCC experts and will be presented to the State Planning Commission (SPC) by the President of the CAS to ensure consideration of the importance of IGCC for future PRC power production.
Contributing Partner: UNT Libraries Government Documents Department
Zirconium and technetium recovery and partitioning in the presence of actinides in modified Purex process for ATW program. Final report

Zirconium and technetium recovery and partitioning in the presence of actinides in modified Purex process for ATW program. Final report

Date: December 31, 1994
Creator: Dzekun, E.G.; Fedorov, Y.S.; Galkin, B.Y.; Lyubtsev, R.I.; Mashkin, A.N.; Mishin, E.N. et al.
Description: The modified Purex process flowsheet is based on combination of all irradiated materials, their joint dissolution and reprocessing as a NPP spent fuel solution with abnormal Pu content after addition of recycled depleted U concentrate. Some groups of long-lived radionuclides could be completely recovered and localized at the stage of extraction reprocessing using 30% TBP. Studies were conducted for 10 y to develop the process for recovery, concentration, and localization of U, Pu, Np, Tc, and Zr within 1st extraction cycle. Actinides are recovered from high-level raffinate of this cycle after evaporation and feed adjustment. Results in this report show that combined deep recovery of several elements from highly irradiated materials by TBP extraction, for further transmutation, is possible. Selective stripping of Zr from solvent phase containing U, Pu, Np, and Tc is quite effective. Development of the modified Purex process is not complete; main problem to be solved should be oxide separation from the loop and permissible storage duration before reprocessing and reuse in the loop.
Contributing Partner: UNT Libraries Government Documents Department