Development and Evaluation of a Tracer-Injection Hydrothermal Technique for Studies of Waste Package Interactions

1986 ◽  
Vol 84 ◽  
Author(s):  
Thomas E. Jones ◽  
D.G. Coles ◽  
R.C. Britton ◽  
J.R. Burnell
Keyword(s):  
Hydrothermal Fluid ◽  
Injection System ◽  
Hydrothermal Conditions ◽  
Tracer Injection ◽  
Waste Package ◽  
Hydrothermal Experiments ◽  
Simulated Waste ◽  
Simulated Groundwater ◽  
Liquid Chromatographic ◽  
Package Materials

AbstractA tracer-injection system has been developed for use in characterizing reactions of waste package materials under hydrothermal conditions. High-pressure liquid chromatographic instrumentation has been coupled with Dickson-type rocking autoclaves to allow injection of selected components into the hydrothermal fluid while maintaining run temperature and pressure. Hydrothermal experiments conducted using this system included the interactions of depleted uranium oxide and Zircaloy-4 metal alloy discs with trace levels of 99Tc and non-radioactive Cs and I in a simulated groundwater matrix. After waste-package components and simulated waste forms were pre-conditioned in the autoclave systems (usually 4 to 6 weeks), known quantities of tracer-doped fluids were injected into the autoclaves' gold reaction bag at run conditions. Time-sequenced sampling of the hydrothermal fluid provided kinetic data on the reactions of tracers with waste package materials. The injection system facilitates the design of experiments that will better define “steady-state” fluid compositions in hydrothermal reactions. The injection system will also allow for the formation of tracer-bearing solid phases in detectable quantities.

The Effect of Waste Package Components on Radionuclides Released from Spent Fuel Under Hydrothermal Conditions

1987 ◽  
Vol 112 ◽  
Author(s):  
Shirley A. Rawson ◽  
William L. Neal ◽  
James R. Burnell
Keyword(s):  
Low Carbon Steel ◽  
Fission Products ◽  
Nuclear Waste Repository ◽  
Low Carbon ◽  
Spent Fuel ◽  
Hydrothermal Conditions ◽  
Waste Package ◽  
Dissolved Species ◽  
Radionuclide Release ◽  
Time Invariant

AbstractThe Basalt Waste Isolation Project has conducted a series of hydrothermal experiments to characterize waste/barrier/rock interactions as a part of its study of the Columbia River basalts as a potential medium for a nuclear waste repository. Hydrothermal tests of 3–15 months duration were performed with light water reactor spent fuel and simulated groundwater, in combination with candidate container materials (low-carbon steel or copper) and/or basalt, in order to evaluate the effect of waste package materials on spent fuel radionuclide release behavior. Solutions were filtered through 400 and 1.8 nm filters to distinguish colloidal from dissolved species. In all experiments, 14C, 129I, and 137Cs occurred only as dissolved species, whereas the actinides occurred in 400 nm filtrates primarily as spent fuel particles. Actinide concentrations in 1.8 nm filtrates were below detection in steel-bearing experiments. In the system spent fuel + copper, apparent time-invariant concentrations of 14C and 137Cs were obtained, but in the spent fuel + steel system, the concentrations of 14C and 137Cs increased gradually throughout the experiments. In experiments containing basalt or steel + basalt, 137Cs concentrations decreased with time. In tests with copper + basalt, 14C and 129I concentrations attained time-invariant values and 137Cs concentrations decreased. Concentrations for the actinides and fission products measured in these experiments were below those calculated from Federal regulations governing radionuclide release.

How to Inject Ictal SPECT? From Manual to Automated Injection

2021 ◽  
Author(s):  
Xavier Setoain ◽  
Francisco Campos ◽  
Antonio Donaire ◽  
Maria Mayoral ◽  
Andres Perissinotti ◽  
...  
Keyword(s):  
Injection System ◽  
Control Group ◽  
Epileptogenic Zone ◽  
Drug Resistant ◽  
Injection Time ◽  
Tracer Injection ◽  
Ictal Spect ◽  
Seizure Focus ◽  
Drug Resistant Epilepsy ◽  
Automated Injection

Abstract BackgroundSuccessful surgery depends on the accurate localization of epileptogenic zone before surgery. Ictal SPECT is the only imaging modality that allows identification of the ictal onset zone by measuring the regional cerebral blood flow at the time of injection. The main limitations of ictal SPECT in epilepsy are the complex methodology of the tracer injection during a seizure. To overcome these limitations, we present the main features of the first automated injector for ictal SPECT (epijet, LemerPax; La Chapelle -sur-Erdre; France). In this study we compared traditional manual injection with automated injection for ictal SPECT in122 patients with drug-resistant epilepsy. MethodsThe study included 55 consecutive prospective patients with drug-resistant epilepsy undergoing injection with the automated injector. The control group was our retrospective database of a historic pool of 67 patients, injected manually from 2014-2016. Calculated annual exposure/radioactive dose for operators was measured. Injection time, seizure focus localization with ictal SPECT, as well as repeated hospitalizations related to fails injections were compared in these two groups of patients. ResultsThere were no differences in the average injection time with epijet (13 s) compared with the traditional manual injection (14s). The seizure focus was successfully localized with ictal SPECT with epijet in 44/55 (80%) patients and with manual injection in 46/67 (68%) patients (p=0.694). Repeated studies were required in 16/67 (23%) patients in the manual injection group compared to 4 patients (7%) in the epijet group (p=0.022). Calculated annual exposure/dose for operators of 0.39 mSv/year and administered dose error inferior to 5% are other advantages of epijet. ConclusionThe first results using epijet are promising in adjustment of the injection dose, reducing the rate of radiation exposure for patients and nurses, maintaining the same injection time and allowing high SPECT accuracy. These preliminary results support the use of an automated injection system to inject radioactive ictal SPECT doses in epilepsy units.

The Expected Environment for Waste Packages in a Salt Repository

1983 ◽  
Vol 26 ◽  
Author(s):  
L. R. Pederson ◽  
D. E. Clark ◽  
F. N. Hodges ◽  
G. L. Mcvpy ◽  
D. Rai
Keyword(s):  
Rock Salt ◽  
Near Field ◽  
Materials Testing ◽  
Site Specific ◽  
Waste Package ◽  
Barrier Materials ◽  
Waste Forms ◽  
Temperature Irradiation ◽  
Salt Brine ◽  
Package Materials

ABSTRACTThis paper discusses results of recent efforts to define the very near-field (within approximately 2m) environmental conditions to which waste packages will be exposed in a salt repository. These conditions must be considered in the experimental design for waste package materials testing, which includes corrosion of barrier materials and leaching of waste forms. Site-specific brine compositions have been determined, and “standard” brine compositions have been selected for testing purposes. Actual brine compositions will vary depending on origin, temperature, irradiation history, and contact with irradiated rock salt. Results of irradiating rock salt, synthetic brines, rock salt/brine mixtures, and reactions of irradiated rock salt with brine solutions are reported.

HYDROTHERMAL MODELING OF SECONDARY RESERVOIR FORMATI ON IN SILICEOUS LIMESTONS (H2O–CO2 SYSTEM)

2020 ◽  
pp. 43-58
Author(s):  
M. Yu. Zubkov ◽  
Keyword(s):  
Carbon Dioxide ◽  
High Temperature ◽  
Amorphous Silica ◽  
Hydrothermal Fluid ◽  
West Siberia ◽  
Hydrothermal Conditions ◽  
Secondary Porosity ◽  
First Results ◽  
Siliceous Limestone ◽  
First Time

We have discussed the first results of hydrothermal modeling of the formation of secondary reservoirs (hydrothermal silicites) in siliceous limestones, which are widespread in the Pre-Jurassic complex of West Siberia, namely, in the H2O-CO2 system, in which the mole fraction of CO2 varied from 0.0 to 1.0, and the temperature from 215 to 410оС. It has been found that in this system there is a predominant dissolution of carbonates and, first of all, dolomite, as a result of which the surface of siliceous limestone is silicified and secondary porosity is formed in them. In some samples, quartz microcrystals with varying degrees of perfection of crystal faceting are shaped. It is found that pyrite is also unstable under these hydrothermal conditions and decomposes forming iron-containing carbonates at its sacrifice. Its transformation into pyrrhotite and copper and nickel sulfides is also observed. Biogenic quartz dissolved by a hydrothermal fluid is released from it either in the form of microcrystalline quartz, or in the form of quenching phases represented by cristobalite and/or amorphous silica. It is also found that at temperatures above 360°C, instead of iron-containing carbonates, chlorite is formed due to pyrite, while kaolinite also decomposes along with pyrite. It was experimentally established for the first time that at a high temperature (410°C), carbon dioxide acquires oxidizing properties and, as a result of its interaction with copper, oxide and red oxide of copper are formed. In addition, under these conditions, pyrite passes into iron-containing carbonates rather than chlorite. The main regularities of the formation of secondary reservoirs, i. e. hydrothermal silicites, in the Paleozoic siliceous limestone have been revealed.

237Np aND 239Pu Solution Behavior During Hydrothermal Testing of Simulated Nuclear Waste Glass with Basalt and Steel

1984 ◽  
Vol 44 ◽  
Author(s):  
Janet A. Schramke ◽  
Scott A. Simonson ◽  
David G. Coles
Keyword(s):  
Nuclear Waste ◽  
Cast Steel ◽  
Size Fraction ◽  
Weight Ratio ◽  
Reaction Products ◽  
Solid Materials ◽  
Solution Behavior ◽  
Waste Package ◽  
Hydrothermal Experiments ◽  
Nuclear Waste Glass

AbstractA series of hydrothermal experiments were carried out on 237Np- and 239Pu-doped PNL 76–68 glass, synthetic basalt groundwater, basalt, and cast steel. These hydrothermal experiments are part of the Basalt Waste Isolation Project investigation of the interactions of waste package components in a basalt repository. Experiments of three months duration were conducted in Dickson-type rocking autoclaves at 200°C and 30 MPa, with an initial fluid to solid weight ratio of 10:1. All solid materials were ground and sieved to a narrow size fraction. The experiments carried out were: glass and groundwater; glass, basalt, and groundwater; glass, steel, and groundwater; and glass, steel, basalt, and groundwater. Unfiltered, 4000 Â filtered, and 18 Å filtered solutions were analyzed to determine the concentrations of radionuclides in solution and those associated with colloids.The quantities of 237Np and 239Pu in solution were very small. Worstcase calculations indicate that 0.01% or less of the total radionuclide inventories were present in solution. The highest solution concentrations of the actinide dopants were observed in the experiments with basalt, even though smaller amounts of glass were dissolved than in the experiments without basalt. The observed differences in the solution concentrations of 237Np and 239Pu were probably controlled by differences in the reaction products, which were clinoptilolite in the experiments with basalt, and an Fe-Zn smectite clay in the experiments without basalt.

scholarly journals Prototype heater test of the environment around a simulated waste package

1991 ◽  
Author(s):  
A.L. Ramirez ◽  
T.A. Buscheck ◽  
R. Carlson ◽  
W. Daily ◽  
V.R. Latorre ◽  
...  
Keyword(s):  
Waste Package ◽  
Simulated Waste

scholarly journals Evaluation of the Final Report: Waste Package Materials Performance Peer Review Panel

2002 ◽  
Author(s):  
J.N. Bailey ◽  
J.D. Cloud ◽  
T.E. Rodgers ◽  
S.E. Summers
Keyword(s):  
Peer Review ◽  
Final Report ◽  
Review Panel ◽  
Waste Package ◽  
Package Materials

scholarly journals Results from Simulated Remote-Handled Transuranic Waste Experiments at the Waste Isolation Pilot Plant (WIPP)

1992 ◽  
Vol 294 ◽  
Author(s):  
Martin A. Molecke
Keyword(s):  
Rock Salt ◽  
Pilot Plant ◽  
Near Field ◽  
Laboratory Data ◽  
Silica Sand ◽  
Waste Isolation Pilot Plant ◽  
Waste Package ◽  
Test Operation ◽  
Transuranic Waste ◽  
Package Materials

ABSTRACTMulti-year, simulated remote-handled transuranic waste (RH TRU, nonradioactive) experiments are being conducted underground in the Waste Isolation Pilot Plant (WIPP) facility. These experiments involve the near-reference (thermal and geometrical) testing of eight full-size RH TRU test containers emplaced into horizontal, unlined rock salt boreholes. Half of the test emplacements are partially filled with bentonite/silica-sand backfill material. All test containers were electrically heated at about 115 W/each for three years, then raised to about 300 W/each for the remaining time. Each test borehole was instrumented with a selection of remote-reading thermocouples, pressure gages, borehole vertical-closure gages, and vertical and horizontal borehole-diameter closure gages. Each test emplacements was also periodically opened for visual inspections of brine intrusions and any interactions with waste package materials, materials sampling, manual closure measurements, and observations of borehole changes. Effects of heat on borehole closure rates and near-field materials (metals, backfill, rock salt, and intruding brine) interactions were closely monitored as a function of time. This paper summarizes results for the first five years of in situ test operation with supporting instrumentation and laboratory data and interpretations. Some details of RH TRU waste package materials, designs, and assorted underground test observations are also discussed. Based on the results, the tested RH TRU waste packages, materials, and emplacement geometry in unlined salt boreholes appear to be quite adequate for initial WIPP repository-phase operations.

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