scholarly journals ORNL Special Form Testing of Sealed-Source Encapsulations

2015 ◽  
Author(s):  
Oscar Martinez ◽  
Christopher Blessinger
Keyword(s):  
Special Form ◽  
National Laboratory ◽  
Competent Authority ◽  
The United States ◽  
Radioactive Material ◽  
Test Unit ◽  
Thermal Tests ◽  
Oak Ridge ◽  
Sealed Source ◽  
The Impact

In the United States of America all transportation of radioactive material is regulated by the Department of Transportation (DOT), along with input from the Nuclear Regulatory Commission. Beginning in 2008 a new type of sealed-source encapsulation package was developed at Oak Ridge National Laboratory (ORNL); these packages contain radioactive material and are regulated and transported in accordance with the requirements set for DOT Class 7 hazardous material. DOT provides regulations pertaining to specific package contents categorized as special form designs. The special form designation indicates that the encapsulated radioactive contents have a very low probability of dispersion even when subjected to significant structural conditions. All ORNL DOT designs have been certified by DOT as being special form materials. The special form designs have been shown to simplify the delivery, transport, acceptance, and receipt process. Simplification of the transportation process makes the sealed-source encapsulation designs very advantageous for shipment to various facilities throughout the lifetime of the special form material. To this end, DOT Certificates of Competent Authority (CoCAs) have been sought for the design suitable for containing high-alpha-activity actinide materials. This design consists of a core of porous zirconia matrix pre-encapsulated within triangular canister (ZipCan) tiles that are then enclosed by a spherical shell. This new ZipCan design and a similar rectangular ZipCube design were tested for compliance with the regulations found in Title 49, Code of Federal Regulations, Section 173.469, Tests for Special Form Class 7 (Radioactive) (49 CFR 173.469) materials. The spherical enclosure was subjected to 9 m impact, 1 m percussion, and 10-minute thermal tests. Before and after each test the designs were subjected to a helium leak check and a bubble test. The ZipCan tiles and core were subjected to the tests required for ISO 2919:1999(E), including a Class 4 impact test and heat test, and were subsequently subjected to helium leakage rate tests [49 CFR 173.469(a)(4)(i)]. The impact tile test unit contained a nonradioactive surrogate; however, the thermal test unit contained a radioactive source. All three designs are still undergoing regulatory special form testing, and all three sealed-source encapsulation designs are to be submitted to DOT for CoCAs.

Development of Testing Methodologies for Onsite Radioactive Material Storage Containers

2008 ◽  
Author(s):  
Matthew R. Feldman
Keyword(s):  
Lawrence Livermore National Laboratory ◽  
National Laboratory ◽  
Nuclear Material ◽  
Department Of Energy ◽  
Radioactive Material ◽  
Development Effort ◽  
Nuclear Facilities ◽  
Los Alamos National Laboratory ◽  
Oak Ridge ◽  
Transportation Technologies

Based on a recommendation from the Defense Nuclear Facilities Safety Board, the Department of Energy (DOE) Office of Nuclear Safety Policy and Assistance (HS-21) has recently issued DOE Manual 441.1-1 entitled Nuclear Material Packaging Manual. This manual provides guidance regarding the use of non-engineered storage media for all special nuclear material throughout the DOE complex. As part of this development effort, HS-21 has funded the Oak Ridge National Laboratory (ORNL) Transportation Technologies Group (TTG) to develop and demonstrate testing protocols for such onsite containers. ORNL TTG to date has performed preliminary tests of representative onsite containers from Lawrence Livermore National Laboratory and Los Alamos National Laboratory. This paper will describe the testing processes that have been developed.

Control of radioactive substances

2015 ◽  
Author(s):  
Jill Reay ◽  
David Sutton ◽  
Colin J Martin
Keyword(s):  
Waste Disposal ◽  
Competent Authority ◽  
Radioactive Material ◽  
Critical Groups ◽  
Radioactive Materials ◽  
Security And Protection ◽  
The Public ◽  
Radioactive Substances ◽  
Essential Components ◽  
The Impact

The possession, use, transport, and disposal of radioactive materials are controlled through regulation to limit exposure of the public and workers. This chapter describes the methodologies employed. Regulation is enacted through a system of notification and licensing, based upon recommendations from the IAEA and ICRP. A competent authority is empowered to permit an organization to hold, use, or dispose of any radionuclide, provided certain conditions are met. These take the form of limits on the quantities of different radioactive materials held, and requirements for security and protection. They require an evaluation of the impact of waste disposal. Methodologies for estimating doses received by critical groups from release of radioactive material into the environment are explained. Minimization of the waste produced and regulation of its disposal are essential components in the overall strategy to protect the environment. Controls over the transport of radioactive materials and medical administrations to patients are considered.

Building the TeraGrid

2005 ◽  
Vol 363 (1833) ◽  
pp. 1715-1728 ◽  
Author(s):  
Peter H Beckman
Keyword(s):  
High Performance ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
The United States ◽  
Parallel Computer ◽  
Software Environment ◽  
Distributed Resources ◽  
Oak Ridge ◽  
California Institute Of Technology ◽  
Institute Of Technology

On 1 October 2004, the most ambitious high-performance Grid project in the United States—the TeraGrid—became fully operational. Resources at nine sites—the San Diego Supercomputer Center, the California Institute of Technology, the National Center for Supercomputing Applications, the University of Chicago/Argonne National Laboratory, Pittsburgh Supercomputing Center, Texas Advanced Computing Center, Purdue University, Indiana University and Oak Ridge National Laboratory—were joined via an ultra-fast optical network, unified policies and security procedures and a sophisticated distributed computing software environment. Funded by the National Science Foundation, the TeraGrid enables scientists and engineers to combine distributed, multiple data sources with computation at any of the sites or link massively parallel computer simulations to extreme-resolution visualizations at remote sites. A single shared utility lets multiple resources be easily leveraged and provides improved access to advanced computational capabilities. One of the demonstrations of this new model for using distributed resources, Teragyroid, linked the infrastructure of the TeraGrid with computing resources in the United Kingdom via a transatlantic data fibre link. Once connected, the software framework of the RealityGrid project was used to successfully explore lattice-Boltzmann simulations involving lattices of over one billion sites.

Production function for short-rotation woody-crop Populus spp. plantations

1994 ◽  
Vol 24 (1) ◽  
pp. 180-184 ◽  
Author(s):  
David A. Lortz ◽  
David R. Betters ◽  
Lynn L. Wright
Keyword(s):  
Production Function ◽  
Cultural Practices ◽  
National Laboratory ◽  
Development Program ◽  
The United States ◽  
Oak Ridge ◽  
Short Rotation ◽  
Wide Range ◽  
Woody Crop ◽  
Populus Spp

Short-rotation woody-crop Populus spp. plantations have the potential to produce large amounts of biomass in short time periods, typically 4–8 years. A production function equation is shown to predict yields for such plantations. The equation is based, in part, on information from biomass production experiments conducted across the United States. These experimental plots are sponsored by the Biofuels Feedstock Development Program of Oak Ridge National Laboratory. The equation uses nine parameters including both cultural practices and climatic and soil site conditions as independent variables. The equation (R2 = 0.86) is accurate and applicable to a wide range of conditions.

Probabilistic Structural Mechanics Analysis of the Degraded Davis-Besse RPV Head

2006 ◽  
Author(s):  
Paul T. Williams ◽  
Shengjun (Sean) Yin ◽  
B. Richard Bass
Keyword(s):  
National Laboratory ◽  
Damage Model ◽  
The United States ◽  
Structural Mechanics ◽  
Companion Paper ◽  
Experimental Program ◽  
Oak Ridge ◽  
Steel Technology ◽  
Sensitivity Studies ◽  
Technical Basis

The Heavy-Section Steel Technology (HSST) Program at Oak Ridge National Laboratory (ORNL) performed a probabilistic structural mechanics (PSM) analysis of the damaged Davis Besse reactor pressure vessel head in support of the United States Nuclear Regulatory Commission’s ongoing forensic investigations. This paper presents a summary of the results of that PSM analysis, including a description of the Davis-Besse wastage-area damage model, the technical basis for the model, and the results of sensitivity studies based on a cladding capacity analysis (CCA) and an Accident Sequence Precursor (ASP) investigation of the wastage cavity. A companion paper describes the HSST experimental program carried out at ORNL in parallel with the PSM analysis.

Effects of Chemical Content Variation on the Fracture Probability of PWR Pressure Vessel Subjected to PTS Events

2015 ◽  
Author(s):  
Pin-Chiun Huang ◽  
Hsoung-Wei Chou ◽  
Yuh-Ming Ferng
Keyword(s):  
Pressure Vessel ◽  
National Laboratory ◽  
Nickel Content ◽  
The United States ◽  
Fracture Probability ◽  
Pressure Vessels ◽  
Pressurized Water ◽  
Oak Ridge ◽  
Content Variation ◽  
Chemical Content

This paper is to study the effects of copper and nickel content variations on the fracture probability of the pressurized water reactor (PWR) pressure vessel subjected to pressurized-thermal-shock (PTS) transients. The probabilistic fracture mechanics (PFM) code, FAVOR, which was developed by the Oak Ridge National Laboratory in the United States, is employed to perform the analyses. A Taiwan domestic PWR pressure vessel with varied copper and nickel contents of beltline region welds and plates is investigated in the study. Some PTS transients analyzed from Beaver Valley Unit 1 for establishing the USNRC’s new PTS rule are applied as the loading conditions. It is found that the content variation of copper and nickel will significantly affect the radiation embrittlement and the fracture probability of PWR pressure vessels. The results can be regarded as the risk incremental factors for comparison with the safety regulation requirements on vessel degradation as well as a reference for the operation of PWR plants in Taiwan.

scholarly journals A Simplified Methodology to Estimate Energy Savings in Commercial Buildings from Improvements in Airtightness

Energies ◽  
2018 ◽  
Vol 11 (12) ◽  
pp. 3322 ◽  
Author(s):  
Mahabir Bhandari ◽  
Diana Hun ◽  
Som Shrestha ◽  
Simon Pallin ◽  
Melissa Lapsa
Keyword(s):  
Energy Use ◽  
Energy Savings ◽  
The United States ◽  
Commercial Buildings ◽  
Air Leakage ◽  
Oak Ridge ◽  
Simple Regression Model ◽  
Online Calculator ◽  
The Impact ◽  
Us Cities

Air leakage through the envelope of commercial buildings in the United States accounts for approximately 6% of their energy use. Various simulation approaches have been proposed to estimate the impact of air leakage on building energy use. Although approaches that are based on detailed airflow modeling appear to be the most accurate to calculate infiltration heat transfer in simulation models, these approaches tend to require significant modeling expertise and effort. To make these energy savings estimates more readily available to building owners and designers, Oak Ridge National Laboratory, the National Institute of Standards and Technology, the Air Barrier Association of America, and the US Department of Energy (DOE) are developing a user-friendly online calculator that applies a detailed airflow modeling approach to examine energy savings due to airtightness in commercial buildings. The calculator, however, is limited to 52 US cities and a few cities in Canada and China. This paper describes the development of an alternative, simplified method to estimate energy savings from improved airtightness. The proposed method uses the same detailed approach for hourly infiltration calculations as the online calculator but it expands the ability to estimate energy savings to all US cities using hourly outdoor air temperature as the only input. The new simple regression model-based approach was developed and tested with DOE’s standalone retail prototype building model. Results from the new approach and the calculator show good agreement. Additionally, a simple approach to estimate percent energy savings for retrofitted buildings was also developed; results were within 5% of the energy saving estimates from the online calculator.

scholarly journals Batch-Scale Hydrofluorination of Li27BeF4 to Support Molten Salt Reactor Development

2015 ◽  
Vol 1 (4) ◽  
Author(s):  
Brian C. Kelleher ◽  
Kieran P. Dolan ◽  
Paul Brooks ◽  
Mark H. Anderson ◽  
Kumar Sridharan
Keyword(s):  
Molten Salt ◽  
Nuclear Reactor ◽  
National Laboratory ◽  
The United States ◽  
Hydraulic Testing ◽  
Molten Salt Reactor ◽  
Fluoride Salt ◽  
Oak Ridge ◽  
University Of Wisconsin ◽  
Analysis Process

Li 2 BeF 4 , or flibe, is the primary candidate coolant for the fluoride-salt-cooled high-temperature nuclear reactor (FHR). Kilogram quantities of pure flibe are required for repeatable corrosion tests of modern reactor materials. This paper details fluoride salt purification by the hydrofluorination–hydrogen process, which was used to regenerate 57.4 kg of flibe originating from the secondary loop of the molten salt reactor experiment (MSRE) at Oak Ridge National Laboratory (ORNL). Additionally, it expounds upon necessary handling precautions required to produce high-quality flibe and includes technological advancements which ease the purification and analysis process. Flibe batches produced at the University of Wisconsin are the largest since the MSRE program, enabling new corrosion, radiation, and thermal hydraulic testing around the United States.

Commercialization Status of Ni3Al-Based Alloys

1996 ◽  
Vol 460 ◽  
Author(s):  
V. K. Sikka
Keyword(s):  
National Laboratory ◽  
Melting Process ◽  
Heat Treating ◽  
The United States ◽  
Operating Conditions ◽  
Current Status ◽  
Oak Ridge ◽  
Technical Developments ◽  
Property Data ◽  
Component Manufacturing

ABSTRACTThe Ni3Al-based alloys have been under development at the Oak Ridge National Laboratory (ORNL) and other research institutions in the United States and around the world for the last ten years. The incremental developments of composition, melting process, casting methods, property data, corrosion data, weldability development, and prototype component testing under production-like operating conditions have pushed the ORNL-developed Ni3Al-based alloys closer to commercialization. This paper will present the highlights of incremental technical developments along with the approach and current status of commercialization. It is concluded that cast components are the primary applications of Ni3Al-based alloys, and applications range from heat-treating fixtures to forging dies. It is also concluded that the commercialization process is accelerated when technology is licensed to an organization that can produce the alloy, has component manufacturing capability, and is also a user.

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