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Uranium solubility studies during waste evaporation (open access)

Uranium solubility studies during waste evaporation

The liquid waste streams from chemical processing of reactor-irradiated targets and fuel are neutralized with excess NaOH and discharged to mild steel waste tanks for interim storage. To reduce the number of tanks required, and thus the cost of waste storage, the supernate is evaporated to about 70% solids, discharged while hot into clean waste tanks. As the solution cools, solids crystallize from the saturated solution and form a solid layer on the bottom of the tank. The supernate is re-evaporated to concentrate the volume further. Evaporation and crystallization are continued until, for tank 41, the tank is almost filled with crystallized salts. In the DWPF processing scheme, these salts will be redissolved in water and {sup 137}Cs precipitated with sodium tetraphenylborate in the in-tank precipitation facility. The decontaminated supernate is now mixed with cement and stored as a solid monolith; the precipitated Cs and the base-insoluble solids are encapsulated in glass for permanent storage. Questions have been raised about the nuclear safety of these operations, particularly for tank 41, where the waste source was waste from the H-Area fuel processing. One scenario for a potential nuclear accident considers that the salts in tank 41 would dissolve in water, but …
Date: August 16, 1993
Creator: Karraker, D. G.
System: The UNT Digital Library
Introduction to the nuclear criticality safety evaluation of facility X-705, Portsmouth Gaseous Diffusion Plant (open access)

Introduction to the nuclear criticality safety evaluation of facility X-705, Portsmouth Gaseous Diffusion Plant

This report is the first in a series of documents that will evaluate nuclear criticality safety in the Decontamination and Recovery Facility, X-705, Portsmouth Gaseous Diffusion Plant. It provides an overview of the facility, categorizes its functions for future analysis, reviews existing NCS documentation, and explains the follow-on effort planned for X-705. A detailed breakdown of systems, subsystems, and operational areas is presented and cross-referenced to existing NCS documentation.
Date: August 16, 1993
Creator: Sheaffer, M. K. & Keeton, S. C.
System: The UNT Digital Library
Effect of pretreating of host oil on coprocessing. Quarterly progress report, April 1, 1993--June 30, 1993 (open access)

Effect of pretreating of host oil on coprocessing. Quarterly progress report, April 1, 1993--June 30, 1993

The principal objective of this research is to gain information on the role that host petroleum-derived oils (1000 F+), as well as that of catalytically treated host oils, play when used as liquefaction solvents in coprocessing with coal. The host oil will be extensively characterized and then pretreated in a number of ways which involve catalytic reactions such as hydrogenation, hydrocracking, and isomerization. The pretreated oils will then be characterized by elemental analysis, catalytic dehydrogenation, distillation, GC-MS, and NMR. The effects of the host oil on coprocessing with coal will be compared to those obtained using catalytically modified heavy oils. When appropriate, model compounds will be used to study specific reactions brought about by the pretreatments. In the progress report for January, 1993--March, 1993, we concluded that the dispersed iron based catalysts were not effective in hydrotreating the AMOCO VTR at 400{degree}C. During the second quarter of this year, several pretreatment runs were conducted at 440{degree}C using molybdenum naphthenate, a known active hydrotreatment catalyst. The reaction time was increased from one hour to two hours, during which time the reaction pressure leveled off. hen Mo naphthenate was added at a concentration of 500 ppM of Mo, coke production was drastically …
Date: August 16, 1993
Creator: Wender, I. & Tierney, J. W.
System: The UNT Digital Library
Radiation environment and shielding for the GEM experiment at the SSC (open access)

Radiation environment and shielding for the GEM experiment at the SSC

We have performed a comprehensive study of the radiation environment for the proposed GEM detector at the SSC. As a result of this study, we have developed a shielding scenario that will ensure that the detector will operate with its design performance for at least 10 years at the luminosity of 10{sup 33} cm {sup {minus}2}{sub s}{sup {minus}1}.
Date: August 16, 1993
Creator: Diwan, M.; Fisyak, Y. & Mokhov, N.
System: The UNT Digital Library
Why Russia is not a state (open access)

Why Russia is not a state

This article makes two principal points. First the author argues that the Russian federation has never been a state and is not sustainable as a state. Four centrifugal indicators are presented to support this claim: ethnic divisiveness; uncertainty about the legitimacy of Russia`s current borders; competing claims for legitimacy on the part of federal and regional leaders; and army units` unpredictable allegiances. Second, she argues that Soviet policies intended to facilitate central control of the periphery had the perverse effect of creating ethnic identity and demands for national autonomy where, in many cases, they did not exist prior to the Communist regime. Following the introduction, part one briefly reviews the concepts of state, nation, and nationalism and the roles they play in Russia. Criteria for state-hood are discussed. Part two lists the main ethnic groups in Russia and considers the roots of ethnic nationalism in the Russian Federation. Part three discusses confusion over the legitimacy of the physical, economic, and political boundaries of the Russian Federation. Part four discusses political disarray in the center and the regions and the lack of unity among order-enforcing entities. The Volga-Ural region -- where there is a large concentration of nuclear weapons and facilities, …
Date: August 16, 1993
Creator: Stern, J. E.
System: The UNT Digital Library
Technology Development saltcrete evaluation (open access)

Technology Development saltcrete evaluation

The objective of the project was to identify, define, and resolve the issues pertaining to the production of a certifiable cemented salt waste form (``saltcrete``) using the existing cementation equipment in the Building 374 liquid waste treatment facility. This reportdescribes the saltcrete process, issues precluding waste form certification, issues resolution where appropriate, and formulation optimization results. This report summarizes acceptance criteria, waste characterization, problem assessment, and formulation study results for the period October 1, 1992, to June 30, 1993.
Date: August 16, 1993
Creator: Connell, J. M.; Faucette, A. M.; Jorgensen, S. C.; Oldham, J. H. & Swan-Bogard, K. M.
System: The UNT Digital Library
Studies of local electron heat transport on TFTR (open access)

Studies of local electron heat transport on TFTR

The anomalously fast relaxation of the perturbations to the electron temperature profile caused by a sawtooth crash has been studied extensively on TFTR. We will show that on a short timescale the heat pulse is not simply diffusive as has been generally assumed, but that modeling of the heat pulse requires a transient enhancement in {chi}{sub e} following the sawtooth crash. It will be shown that the time-dependent enhancement in {chi}{sub e} predicted by non-linear thermal transport models, i.e., incremental {chi} models or the Rebut-Lallia-Watkins transport model, is much smaller than that required to explain the anomalies in the heat pulse propagation.
Date: August 16, 1993
Creator: Fredrickson, E. D.; Chang, Z. Y.; Janos, A.; McGuire, K. M.; Scott, S. & Taylor, G.
System: The UNT Digital Library