scholarly journals Gas Generation Testing of Uranium Metal in Simulated K Basins Sludge and Grouted Sludge Waste Forms

2004 ◽  
Author(s):  
Calvin H Delegard ◽  
Andrew J Schmidt ◽  
Rachel L Sell ◽  
Sergei I Sinkov ◽  
Samuel A Bryan
Keyword(s):  
Gas Generation ◽  
Uranium Metal ◽  
Waste Forms ◽  
Sludge Waste

scholarly journals Final Report - Gas Generation Testing of Uranium Metal in Simulated K Basin Sludge and in Grouted Sludge Waste Forms

2004 ◽  
Author(s):  
Calvin H Delegard ◽  
Andrew J Schmidt ◽  
Rachel L Sell ◽  
Sergei I Sinkov ◽  
Samuel A Bryan ◽  
...  
Keyword(s):  
Final Report ◽  
Gas Generation ◽  
Uranium Metal ◽  
Waste Forms ◽  
Sludge Waste

Generation Mechanism of Hydrogen Gas from Hardened Cement Paste by γ-Irradiation

1994 ◽  
Vol 353 ◽  
Author(s):  
K. Noshita ◽  
T. Nishi ◽  
M. Matsuda
Keyword(s):  
Hydrogen Generation ◽  
Hydrogen Gas ◽  
Generation Rate ◽  
Hardened Cement ◽  
Gas Generation ◽  
Γ Irradiation ◽  
Waste Forms ◽  
Two Factors ◽  
G Value ◽  
Hydrogen Radicals

AbstractHydrogen gas is generated from cementitious waste forms by radiolysis of water. In the case of low level radioactive waste, gas yields have been confirmed to be sufficiently low by irradiation experiments. However, studies have suggested that the hydrogen generation rate in cementitious waste forms is larger than the rate calculated from the g-value (H2 yields for 100eV absorbed). In this paper, the factors that increase the gas generation were investigated quantitatively. Two factors were identified, the effect of an organic diethylene glycol which reacts with hydrogen radicals to produce hydrogen, and the effect of electrons generated in the cementitious matrix which decompose water to hydrogen. The hydrogen generation rate was confirmed to drop less than the rate calculated from the g-value when these factors were eliminated.

Leach Tests of Simulated Low-Level Transuranic Waste Forms Containing Transuranic Elements

1982 ◽  
Vol 15 ◽  
Author(s):  
Jane M. Welch ◽  
Claude W. Sill ◽  
John E. Flinn
Keyword(s):  
Alpha Spectrometry ◽  
Soil Samples ◽  
Deionized Water ◽  
The Other ◽  
Low Level ◽  
Rocky Flats ◽  
Leach Rate ◽  
Waste Forms ◽  
Sludge Waste ◽  
Transuranic Waste

ABSTRACTSimulations of waste forms that might be produced by slagging pyrolysis incineration of low-level transuranic (TRU) wastes stored at the Idaho National Engineering Laboratory (INEL) have been fabricated containing the transuranic isotopes 237Np, 239pu, 24lAm, 244Cm at levels of approximately 1 μCi per gram of each.Leach tests were performed using frit and vitrified monolithic specimens of average INEL TRU waste, portland cement monoliths made with frit as aggregate, and vitrified monoliths of INEL soil and simulated Rocky Flats sludge. Static leach tests were performed at 90, 70, 40, and 25°C in deionized water for up to 364 days. Leachates were analyzed for the TRU elements by alpha spectrometry. The following generalizations can be made:1. Cemented frit and vitrified sludge waste forms produce leachates with the highest pHs (>11) and have the lowest TRU leach rates, 10−4 g/m2.d at 90°C.2. Neptunium has a higher leach rate than the other three TRU elements by as much as two orders of magnitude for all waste forms tested except cemented frit.3. Only the vitrified soil samples display a marked temperature dependence for leach rates of all four TRU elements.

Dissolution of uranium metal without hydride formation or hydrogen gas generation

2008 ◽  
Vol 378 (3) ◽  
pp. 299-304 ◽  
Author(s):  
Chuck Soderquist ◽  
Bruce McNamara ◽  
Brian Oliver
Keyword(s):  
Hydrogen Gas ◽  
Gas Generation ◽  
Uranium Metal ◽  
Hydride Formation

LiNO3 Addition to Cement Which Prevents Aluminum Corrosion

1997 ◽  
Vol 506 ◽  
Author(s):  
T. Matsuo ◽  
T. Izumida ◽  
M. Hironaga ◽  
Y. Horikawa ◽  
T. Shiomi
Keyword(s):  
Underground Water ◽  
Hydrogen Gas ◽  
Disposal Site ◽  
Chemical Analyses ◽  
Metallic Aluminum ◽  
Gas Generation ◽  
Water Penetration ◽  
Waste Forms ◽  
Aluminum Corrosion ◽  
Land Disposal

ABSTRACTLiNO3 addition to cement was examined to prevent hydrogen gas generation from metallic aluminum in dry active wastes during waste solidification and under circumstances of underground water penetration into the land disposal site. And its reaction mechanism was identified by some chemical analyses. The volume of the hydrogen gas generation with LiNO3 addition was 10% as much as that without LiNO3, by formation of the insoluble Li-Al preservation film on aluminum. After the land disposal of waste forms, LiNO3 would be expected to be effective to prevent aluminum corrosion as long as the cement forms keep their alkaline character, and when it became ineffective, the circumstances around the waste forms can be made less corrosive for aluminum. The aluminum corrosion at that time would be as much as 10% of that without LiNO3 addition.

scholarly journals Room Closure Response to Gas Generation and Mechanical Strength of Different Waste Forms in a Bedded Salt Repository

1993 ◽  
Vol 333 ◽  
Author(s):  
F. T. Mendenhall ◽  
C.M. Stone
Keyword(s):  
Constitutive Models ◽  
Creep Model ◽  
Secondary Creep ◽  
Salt Formation ◽  
Gas Generation ◽  
Waste Forms ◽  
Time Period ◽  
Finite Element Calculations ◽  
Consolidation Model ◽  
History Of

ABSTRACTFinite element calculations of the porosity history of a nuclear waste disposal room for transuranic (TRU) waste in a bedded salt formation have been completed. The analyses include a reduced elastic/secondary creep model for the host halite and a nonlinear consolidation model for the crushed salt backfill. Separate gas generation and constitutive models were used for three distinct hypothetical waste forms: 1) unaltered defense-related, contact-handled transuranic (CH-TRU) waste, 2) shredded and cemented CH-TRU waste, and 3) incinerated and vitrified CH-TRU waste. Histories were determined for a 2000 year time period starting from the emplacement of room seals. The resulting final room porosities varied from roughly 55% to less than 10%, according to waste forms.

scholarly journals Mitigation of Hydrogen Gas Generation from the Reaction of Water with Uranium Metal in K Basins Sludge

2010 ◽  
Author(s):  
Sergey I. Sinkov ◽  
Calvin H. Delegard ◽  
Andrew J. Schmidt
Keyword(s):  
Hydrogen Gas ◽  
Gas Generation ◽  
Uranium Metal

Development of a New Mechanistic Low-Level Waste Source Term Model

1996 ◽  
Vol 465 ◽  
Author(s):  
Man-Sung Yim
Keyword(s):  
Source Term ◽  
Transport Model ◽  
Near Field ◽  
Cumulative Probability ◽  
Gas Generation ◽  
Low Level ◽  
Waste Forms ◽  
Term Model ◽  
Radionuclide Release ◽  
Source Term Model

ABSTRACTA new mechanistic low-level waste source term model was developed. Key features of this effort are: use of cumulative probability functions to describe the failures of waste containers; capability to describe diffusion controlled release which is dependent on the conditions of the waste package surroundings; consideration of the effects of gas generation on the source term, and; use of a source inventory characterization routine to provide a built-in capability for defining the distributions of radionuclides in various waste forms and streams. The model is capable of describing the diffusion of radionuclides in waste forms with the use of concentration and flux continuity boundary conditions. Release of radionuclides from various waste streams is modeled by the combination of diffusion, dissolution, and surface release. Failures of waste containers are portrayed by the use of probabilistic failure functions based on Weibull and lognormal distributions. The model for radionuclide release from waste packages is coupled with the near-field transport model to describe the effects of migration and dispersion within the disposal unit. Characteristics of the new model were evaluated through sensitivity analysis and compared with existing source term codes.

Standardized Waste Form Test Methods

1984 ◽  
Vol 44 ◽  
Author(s):  
Steven C. Slate
Keyword(s):  
Radiation Stability ◽  
Test Methods ◽  
Test Method ◽  
Waste Form ◽  
Current Status ◽  
High Level Waste ◽  
Gas Generation ◽  
Waste Forms ◽  
Leach Test ◽  
Compliance Testing

AbstractThe Materials Characterization Center (MCC) is developing standard tests to characterize nuclear waste forms. Development of the first thirteen tests was originally initiated to provide data to compare different high-level waste (HLW) forms and to characterize their basic performance. The current status of the first thirteen MCC tests and some sample test results are presented: The radiation stability tests (MCC-6 and 12) and the tensile-strength test (MCC-11) are approved; the static leach tests (MCC-1, 2, and 3) are being reviewed for full approval; the thermal stability (MCC-7) and microstructure evaluation (MCC-13) methods are being considered for the first time; and the flowing leach test methods (MCC-4 and 5), the gas generation methods (MCC-8 and 9), and the brittle fracture method (MCC-10) are indefinitely delayed. Sample static leach test data on the ARM-I approved reference material are presented.Established tests and proposed new tests will be used to meet new testing needs. For waste form production, tests on stability and composition measurement are needed to provide data to ensure waste form quality. In transportaion, data are needed to evaluate the effects of accidents on canisterized waste forms. The new MCC-15 accident test method and some data are presented. Compliance testing needs required by the recent draft repository waste acceptance specifications are described. These specifications will control waste form contents, processing, and performance.

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