Makassed General Hospital Reduce INMM Paper
Abstract not provided.
Publications
RADIOLOGICAL SECURITY THROUGH CESIUM IRRADIATOR REPLACEMENT IN THE UNITED STATES
Abstract not provided.
HFIR Fuel Development Efforts
Abstract not provided.
Global Threat Reduction Initiative and the Egyptian Atomic Energy Authority Amnesty Recovery Project
Global Threat Reduction Initiative : Program Introduction
Abstract not provided.
Global Threat Reduction Initiative and the Egyptian Atomic Energy Authority Amnesty Recovery Program
SPA Tool Case Studies
Abstract not provided.
An overview of the Global Threat Reduciton Initiative Work in Tanzania
Abstract not provided.
An overview of the global threat reduction initiative's physical protection work in Tanzania
The U.S. Department of Energy's (DOE) National Nuclear Security Administration (NNSA) established the Global Threat Reduction Initiative's (GTRI) mission to reduce and protect nuclear and radiological materials located at civilian sites worldwide. Internationally, over 80 countries are cooperating with GTRI to enhance security of facilities with these materials. In 2004, a GTRI delegation began working with the Tanzania Atomic Energy Commission, (TAEC). The team conducted site assessments for the physical protection of radiological materials in Tanzania. Today, GTRI and the Government of Tanzania continue cooperative efforts to enhance physical security at several radiological sites, including a central sealed-source storage facility, and sites in the cities of Arusha, Dar Es Salaam, and Tanga. This paper describes the scope of physical protection work, lessons learned, and plans for future cooperation between the GTRI program and the TAEC. Additionally the paper will review the cooperative efforts between TAEC and the International Atomic Energy Agency (IAEA) with regards to a remote monitoring system at a storage facility and to the repackaging of radioactive sources.
An overview of The Global Threat Reduction Initiative's Physical Protection Work in Tanzania
Abstract not provided.
In-drift natural convection analysis of the low temperature operating mode design
Proposed for publication in Nuclear Technology.
Yucca Mountain has been designated as the nation's high-level radioactive waste repository, and the U.S. Department of Energy has been approved to apply to the U.S. Nuclear Regulatory Commission for a license to construct a repository. The temperature and humidity inside the emplacement drift will affect the degradation rate of the waste packages and waste forms as well as the quantity of water available to transport dissolved radionuclides out of the waste canister. Thermal radiation and turbulent natural convection are the main modes of heat transfer inside the drift. This paper presents the result of three-dimensional computational fluid dynamics simulations of a segment of emplacement drift. The model contained the three main types of waste packages and was run at the time that the peak waste package temperatures are expected. Results show that thermal radiation is the dominant mode of heat transfer inside the drift. Natural convection affects the variation in surface temperature on the hot waste packages and can account for a large fraction of the heat transfer for the colder waste packages. The paper also presents the sensitivity of model results to uncertainties in several input parameters. The sensitivity study shows that the uncertainty in peak waste package temperatures due to in-drift parameters is <3 C.
CFD calculation of internal natural convection in the annulus between horizontal concentric cylinders
Abstract not provided.
Two-Dimensional CFD Calculations for YMP Natural Convection Tests
Abstract not provided.
CFD Modeling of Natural Convection Heat Transfer and Fluid Flow in Yucca Mountain Project (YMP) Enclosures
Abstract not provided.
CFD calculation of internal natural convection in the annulus between horizontal concentric cylinders
Proceedings of the ASME Summer Heat Transfer Conference
Thermally-induced natural convection heat transfer in the annulus between horizontal concentric cylinders has been studied using the commercial code Fluent. The boundary layers are meshed all the way to the wall because forced convection wall functions are not appropriate. Various one-and two-equation turbulence models have been considered. Overall and local heat transfer rates are compared with existing experimental data.
Pre- and post-closure natural convection effects in Yucca Mountain drifts
Abstract not provided.
Review of Chemical Sensors for In-Situ Monitoring of Volatile Contaminants
Sandia National Laboratories has sponsored an LDRD (Laboratory Directed Research and Development) project to investigate and develop micro-chemical sensors for in-situ monitoring of subsurface contaminants. As part of this project, a literature search has been conducted to survey available technologies and identify the most promising methods for sensing and monitoring subsurface contaminants of interest. Specific sensor technologies are categorized into several broad groups, and these groups are then evaluated for use in subsurface, long-term applications. This report introduces the background and specific scope of the problem being addressed by this LDRD project, and it provides a summary of the advantages and disadvantages of each sensor technology identified from the literature search.
Abstraction of Thermal Hydrology and Coupled Processes for TSPA
The thermal-hydrologic (TH) and coupled process models describe the evolution of a potential geologic repository as heat is released from emplaced waste. The evolution (thermal, hydrologic, chemical, and mechanical) of the engineered barrier and geologic systems is heavily dependent on the heat released by the waste packages and how the heat is transferred from the emplaced wastes through the drifts and through the repository host rock. The essential elements of this process are extracted (or abstracted) from the process-level models that incorporate the basic energy and mass conservation principles and applied to the total system models used to describe the overall performance of the potential repository. The process of total system performance assessment (TSPA) abstraction is the following. First is a description of the parameter inputs used in the process-level models. A brief description is given hereof past inputs for the viability assessment (e.g., for TSPA-VA) and current inputs for the site recommendation (TSPA-SR). This is followed by a highlight of the process-level models from which the abstractions are made. These include descriptions of TH, thermal-hydrologic-chemical (THC), and thermal-mechanical (TM) processes used to describe the performance of individual waste packages and waste emplacement drifts as well as the repository as a whole. Next is a description of what (and how) information is abstracted from the process-level models. This also includes an accounting of the features, events, and processes (FEPs) that are important to both the regulators and the international repository community in general. Finally, an identification of the TSPA model components that utilize the abstracted information to characterize the overall performance of a potential geologic repository is given.
18 Results