Nuclide Migration Field Experiments in Tuff, G Tunnel, Nevada Test Site

1981 ◽  
Vol 6 ◽  
Author(s):  
B. R. Erdal ◽  
R. S. Rundberg ◽  
W. R. Daniels ◽  
K. Wolfsberg ◽  
A. M. Friedman ◽  
...  
Keyword(s):  
Field Experiments ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Test Site ◽  
Current Status ◽  
Real Field ◽  
Small Scale ◽  
Single Fracture ◽  
Radionuclide Migration ◽  
Porous Rock

ABSTRACTA project to begin to address the phenomena of flow and element migration in fractured porous rock has recently been started by the Los Alamos National Laboratory, Sandia National Laboratories, and Argonne National Laboratory. The work has three objectives: 1) to develop the experimental, instrumental, and safety techniques necessary to conduct controlled, small-scale, radionuclide migration, field experiments; 2) to use these techniques to define radionuclide migration through rock by performing generic, at-depth experiments under closely controlled conditions in a single fracture in porous rock; and 3) to determine whether available lithologic, geochemical, and hydraulic properties together with existing or developed transport models are sufficient and appropriate to describe real field conditions (i.e., to scale from small-scale laboratory studies to bench-size studies to field studies). The detailed scope of this project and its current status are described.

The Nagra/Pnc Grimsel test site Radionuclide Migration Experiment: Rigorous Field Testing of Transport Models

1994 ◽  
Vol 353 ◽  
Author(s):  
H. Umeki ◽  
K. Hatanaka ◽  
W.R. Alexander ◽  
I.G. Mckinley ◽  
U. Frick
Keyword(s):  
Field Experiments ◽  
Field Testing ◽  
Test Site ◽  
Testing Procedure ◽  
Crystalline Rock ◽  
Radionuclide Migration ◽  
Transport Models ◽  
Geochemical Behaviour ◽  
Migration Experiment ◽  
Rigorous Model

AbstractThe long-term programme of in-situ radionuclide migration experiments in the underground test site at Grimsel (GTS) involves the development and testing of radionuclide transport models with their associated databases. The field experiments are carried out in a water-bearing shear zone in crystalline rock utilising a suite of tracers of differing geochemical behaviour. A rigorous model testing procedure has been developed for the GTS radionuclide migration experiment. This paper describes application of this testing procedure to a solute transport code developed by PNC.

Radionuclide Migration: Laboratory Experiments with Isolated Fractures

1981 ◽  
Vol 6 ◽  
Author(s):  
R. S. Rundberg ◽  
J. L. Thompson ◽  
S. Maestas
Keyword(s):  
Laboratory Experiments ◽  
Field Experiments ◽  
National Laboratory ◽  
Test Site ◽  
Matrix Diffusion ◽  
Fracture Flow ◽  
Flow Equations ◽  
Welded Tuff ◽  
The Matrix ◽  
Element Migration

ABSTRACTLaboratory experiments examining flow and element migration in rocks containing isolated fractures have been initiated at the Los Alamos National Laboratory. Techniques are being developed to establish simple fracture flow systems which are appropriate to models using analytical solutions to the matrix diffusion - flow equations, such as those of I. Neretnieks [1]. These experiments are intended to be intermediate steps toward larger scale field experiments where it may become more difficult to establish and control the parameters important to nuclide migration in fractured media.Laboratory experiments have been run on fractures ranging in size from 1 to 20 cm in length. The hydraulic flow in these fractures was studied to provide the effective apertures. The flows established in these fracture systems are similar to those in the granite fracture flow experiments of Witherspoon et al. [2]. Traced solutions containing 85Sr and 137Cs were flowed through fractures in Climax Stock granite and welded tuff (Bullfrog and Tram members, Yucca Mountain, Nevada Test Site). The results of the elutions through granite agree with the matrix diffusion calculations based on independent measurements of Kd. The results of the elutions through tuff, however, agree only if the Kd values used in the calculations are lower than the Kd values measured using a batch technique. This trend has been previously observed in chromatographic column experiments with tuff.

Experimental and Theoretical Analyses of Small-Scale Radionuclide Migration Field Experiments

1981 ◽  
Vol 6 ◽  
Author(s):  
K. L. Erickson ◽  
D. R. Fortney
Keyword(s):  
Distribution Coefficient ◽  
Field Experiments ◽  
Fluid Velocity ◽  
Small Scale ◽  
Fracture Aperture ◽  
Radionuclide Migration ◽  
Experimental Conditions ◽  
Dissolved Species ◽  
Key Variables ◽  
Aperture Distribution

ABSTRACTAnalyses have been completed which provide guidance for conducting radionuclide migration field experiments. Characterization of nonwelded tuffs and laboratory experiments defining dominant chemical phenomena were used to develop a model for describing migration in fractured porous rock. Criteria for obtaining optimum experimental conditions were developed in terms of the key variables dominating migration in a given rock type, namely the fracture aperture, distribution coefficient, and average fluid velocity. For simple dissolved species, which are reversibly sorbed, variations in fracture aperture and fluid velocity affect experiment results much more than variations in distribution coefficient. Therefore, the experiment should be designed to optimize hydrogeologic conditions rather than sorption properties.

Modeling of the SNL S-CO2 Loop With ANL Plant Dynamics Code

2012 ◽  
Author(s):  
Anton Moisseytsev ◽  
James J. Sienicki
Keyword(s):  
Experimental Data ◽  
Steady State ◽  
Performance Prediction ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Small Scale ◽  
Brayton Cycle ◽  
A Value ◽  
Plant Dynamics ◽  
Good Agreement

The ANL Plant Dynamics Code (PDC) for the analysis of supercritical carbon dioxide (S-CO2) Brayton cycle power converters has been under development at Argonne National Laboratory for several years. In previous years, limited validation of the PDC models on an individual basis was carried out using experimental data obtained from facilities directed at individual components. Recently, experimental data from the SNL/BNI small-scale S-CO2 Brayton cycle demonstration that is being assembled in a staged fashion has been provided to ANL. The loop configuration with a single turbo-alternator-compressor (TAC) was modeled with the Plant Dynamics Code and the performance prediction of individual components and the entire loop obtained from the PDC was compared with the experimental data. Overall, reasonably good agreement is obtained for steady state conditions around the loop when a value is inferred for the heat loss downstream of the turbine such that a steady state loop energy balance can be established.

Codes, Standards, Rules and Assumptions on Environment Assisted Fatigue for Fatigue Management of Primary Piping

2020 ◽  
Author(s):  
Jussi Solin ◽  
Tommi Seppänen ◽  
Rami Vanninen ◽  
Erkki Pulkkinen ◽  
Petri Lemettinen ◽  
...  
Keyword(s):  
National Laboratory ◽  
Argonne National Laboratory ◽  
Current Status ◽  
Basic Material ◽  
Primary Circuit ◽  
Final Report ◽  
Regulatory Requirement ◽  
Cyclic Operation ◽  
The Us ◽  
Code Language

Abstract All international codes used for design, operation and inspection of NPP primary circuit pressure boundaries are rooted to the ASME Boiler and Pressure Vessel Code, Section III, Nuclear Vessels, 1963. Article 4, N-415 “Analysis for cyclic operation” instructed calculation of stress intensities for fatigue transients and provided two design curves for basic material types. Different codes such as ASME, RCC-M, KTA, PNAE and JSME have much in common, but partial deviations exist. In 2007 the US NRC Regulatory Guide 1.207 endorsed a methodology for accounting the environmental effects. It was mainly based on extensive work in Japan and the Argonne National Laboratory. The final report of ANL, NUREG/CR-6909 became a major reference and subject of criticism. However, the first approach for environment assisted fatigue (EAF) written in ‘code language’ was published in Japan and a regulatory requirement for consideration of EAF both for operating reactors and new designs appeared first in Finland. This paper discusses challenges in management of fatigue and the evolving state-of-the-art in different codes, standards, rules and assumptions. The roots and current status of fatigue curves and design criteria applied in Finnish NPP’s are explained.

Electron and ion irradiation-induced dissolution of mechanical twins in the intermetalic U3Si: An in situ HVEM study

1989 ◽  
Vol 47 ◽  
pp. 652-653
Author(s):  
Charles W. Allen ◽  
Robert C. Birtcher
Keyword(s):  
Elevated Temperatures ◽  
Ion Irradiation ◽  
Ion Beam ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Heavy Ion ◽  
High Energy ◽  
Mechanical Twinning ◽  
In Situ Experiments

The uranium silicides, including U3Si, are under study as candidate low enrichment nuclear fuels. Ion beam simulations of the in-reactor behavior of such materials are performed because a similar damage structure can be produced in hours by energetic heavy ions which requires years in actual reactor tests. This contribution treats one aspect of the microstructural behavior of U3Si under high energy electron irradiation and low dose energetic heavy ion irradiation and is based on in situ experiments, performed at the HVEM-Tandem User Facility at Argonne National Laboratory. This Facility interfaces a 2 MV Tandem ion accelerator and a 0.6 MV ion implanter to a 1.2 MeV AEI high voltage electron microscope, which allows a wide variety of in situ ion beam experiments to be performed with simultaneous irradiation and electron microscopy or diffraction.At elevated temperatures, U3Si exhibits the ordered AuCu3 structure. On cooling below 1058 K, the intermetallic transforms, evidently martensitically, to a body-centered tetragonal structure (alternatively, the structure may be described as face-centered tetragonal, which would be fcc except for a 1 pet tetragonal distortion). Mechanical twinning accompanies the transformation; however, diferences between electron diffraction patterns from twinned and non-twinned martensite plates could not be distinguished.

Environmental cell studies of deformation and fracture

1990 ◽  
Vol 48 (4) ◽  
pp. 516-517
Author(s):  
H. K. Birnbaum ◽  
I. M. Robertson
Keyword(s):  
National Laboratory ◽  
Argonne National Laboratory ◽  
Damage Threshold ◽  
Chromatic Aberration ◽  
Good Choice ◽  
Point Of View ◽  
Deformation And Fracture ◽  
Environmental Cell ◽  
Gas Molecules ◽  
The University

Studies of the effects of hydrogen environments on the deformation and fracture of fcc, bcc and hep metals and alloys have been carried out in a TEM environmental cell. The initial experiments were performed in the environmental cell of the HVEM facility at Argonne National Laboratory. More recently, a dedicated environmental cell facility has been constructed at the University of Illinois using a JEOL 4000EX and has been used for these studies. In the present paper we will describe the general design features of the JEOL environmental cell and some of the observations we have made on hydrogen effects on deformation and fracture.The JEOL environmental cell is designed to operate at 400 keV and below; in part because of the available accelerating voltage of the microscope and in part because the damage threshold of most materials is below 400 keV. The gas pressure at which chromatic aberration due to electron scattering from the gas molecules becomes excessive does not increase rapidly with with accelerating voltage making 400 keV a good choice from that point of view as well. A series of apertures were placed above and below the cell to control the pressures in various parts of the column.

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