Comparison of Predictive and Experimental Data From Graphite Irradiations in the Advanced Test Reactor Irradiation Test Vehicle

2003 ◽  
Author(s):  
Richard G. Ambrosek ◽  
Debbie J. Utterbeck
Keyword(s):  
Physical Property ◽  
The United States ◽  
Physical Structure ◽  
Experimental Results ◽  
United States Department ◽  
Test Vehicle ◽  
Irradiation Test ◽  
Environmental Laboratory ◽  
Test Reactor ◽  
The Individual

In 2000, British Nuclear Fuels Limited (BNFL) commissioned an irradiation program at the United States Department of Energy’s Idaho National Engineering and Environmental Laboratory (INEEL) to assess the effects of extended operating scenarios upon the integrity of Magnox reactor cores. In this program, predictions of thermal and physical effects on these graphite cores were developed using analytical computer models. To benchmark results, experimental graphite assemblies representative of the Magnox graphite were irradiated in the Advanced Test Reactor (ATR). This paper analyzes and contrasts the thermal predictions with those experimental results. These investigations were conducted to extend existing graphite physical property databases for higher radiolytic weight loss (35–50% density reduction) than occur during the economic planning life of these reactors. These data then can be used to make extended life projections regarding the suitable function of the graphite in its various roles of providing the physical structure for the fuel, neutron moderator, medium for instrumentation, and coolant channels. Extended irradiation effects will be obtained with samples of archived, pre-characterized graphite used in the Magnox type reactors. The new Irradiation Test Vehicle (ITV) facility in the ATR contained the experiments and provided the desired irradiation conditions as well as on-line temperature control. The capability to provide both oxidizing and inert gas atmospheres for the graphite specimens was added to the ITV to enable assessment of the individual and combined effects of oxidation and neutron damage to the specimens. In this paper the thermal evaluations (performed to size the control gaps to obtain the desired thermal performance) are contrasted to actual experimental results.

Mission and Status of the First Two Next Generation Nuclear Plant Fuel Irradiation Experiments in the Advanced Test Reactor

2010 ◽  
Author(s):  
S. Blaine Grover ◽  
David A. Petti ◽  
John T. Maki
Keyword(s):  
United States ◽  
Fission Product ◽  
The United States ◽  
Nuclear Plant ◽  
United States Department ◽  
Next Generation ◽  
States Department ◽  
On Line ◽  
Test Reactor ◽  
And Control

The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Advanced Gas Reactor (AGR) Fuel Development and Qualification Program will be irradiating up to nine low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the United States Department of Energy’s lead laboratory for nuclear energy development. These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States, and the irradiations will be completed over the next five to six years to support demonstration and qualification of new TRISO coated particle fuel for use in high temperature gas reactors. The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of multiple separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006 and completed a very successful irradiation in early November 2009. The second experiment (AGR-2) is currently being fabricated and assembled for insertion in the ATR in the early to mid calendar 2010. The design of test trains, the support systems and the fission product monitoring system used to monitor and control the experiment during irradiation will be discussed. In addition, the purpose and differences between the first two experiments will be compared, and updated information on the design and status of AGR-2 is provided. The preliminary irradiation results for the AGR-1 experiment are also presented.

scholarly journals Status of the Combined Third and Fourth NGNP Fuel Irradiations in the Advanced Test Reactor

2013 ◽  
Author(s):  
S. Blaine Grover ◽  
David A. Petti ◽  
Michael E. Davenport
Keyword(s):  
United States ◽  
Fission Product ◽  
National Laboratory ◽  
The United States ◽  
Operating Conditions ◽  
United States Department ◽  
Next Generation ◽  
Monitoring And Control ◽  
On Line ◽  
Test Reactor

The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is irradiating up to seven low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States. The experiments will be irradiated over the next several years to demonstrate and qualify new TRISO coated particle fuel for use in high temperature gas reactors. The goals of the experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of several independent capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006 and was completed in November 2009. The second experiment (AGR-2) started irradiation in June 2010 and is currently scheduled to be completed in September 2013. The third and fourth experiments have been combined into a single experiment designated (AGR-3/4), which started its irradiation in December 2011 and is currently scheduled to be completed in April 2014. Since the purpose of this combined experiment is to provide data on fission product migration and retention in the NGNP reactor, the design of this experiment is significantly different from the first two experiments, though the control and monitoring systems are extremely similar. The design of the experiment will be discussed followed by its progress and status to date.

scholarly journals US Department of Defense Support of Civilian Vector Control Operations Following Natural Disasters

2020 ◽  
Vol 36 (2s) ◽  
pp. 82-89
Author(s):  
Erica J Lindroth ◽  
Mark S. Breidenbaugh ◽  
Jeffrey D. Stancil
Keyword(s):  
Vector Control ◽  
Air Force ◽  
Preventive Medicine ◽  
Department Of Defense ◽  
The United States ◽  
Primary Objective ◽  
Service Member ◽  
United States Department ◽  
The Individual ◽  
Military Services

ABSTRACT The United States Department of Defense (DoD) employs advanced-degreed entomologists as Preventive Medicine and Public Health Officers in the Army, Navy, and Air Force. While the primary objective of military entomologists is service member health and readiness (“force health protection”), military entomology resources can provide support to civil authorities as directed by the President or Secretary of Defense through Department of Defense Directive 3025.18, Defense Support of Civil Authorities (DSCA). The employment of DSCA is complex and involves the consideration of such factors as the proper request process, funding, legality, risk, appropriateness, and readiness. Once approved and mobilized, however, military preventive medicine assets can be of significant help to civil authorities when dealing with emergency vector control. This paper will address some of the policy issues surrounding the use of DSCA, outline the resources available from the individual military services, and provide examples of DoD contingency vector control support to civil authorities.

Commercial Spent Nuclear Fuel Integrity During Long-Term Dry Storage

2001 ◽  
Author(s):  
Leroy Stewart ◽  
Mikal A. McKinnon
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
The United States ◽  
Department Of Energy ◽  
United States Department ◽  
Spent Fuel ◽  
Fuel Rods ◽  
Dry Storage ◽  
Environmental Laboratory ◽  
Cooperative Project

Abstract The United States Department of Energy (DOE) Office of Civilian Radioactive Waste Management conducted spent nuclear fuel integrity and cask performance tests from 1984–1996 at the Idaho National Engineering and Environmental Laboratory (INEEL). Between 1994 and 1998, DOE also initiated a Spent Fuel Behavior Project that involved enhanced surveillance, monitoring, and gas-sampling activities for intact fuel in a GNS CASTOR V/21 cask and for consolidated fuel in a Sierra Nuclear VSC-17 cask. The results of these series of tests are reported in this paper. Presently, DOE is involved in a cooperative project to perform destructive evaluations of fuel rods that have been stored in the CASTOR V/21 cask. The results of those evaluations are presented elsewhere in these proceedings in a paper entitled “Examination of Spent PWR Fuel Rods after 15 years in Dry Storage”.

scholarly journals Status of the irradiation test vehicle for testing fusion materials in the Advanced Test Reactor

1998 ◽  
Author(s):  
H Tsai ◽  
I C Gomes ◽  
D L Smith ◽  
A J Palmer ◽  
F W Ingram ◽  
...  
Keyword(s):  
Test Vehicle ◽  
Fusion Materials ◽  
Irradiation Test ◽  
Test Reactor

Status of the Third NGNP Graphite Irradiation AGC-3 in the Advanced Test Reactor

2013 ◽  
Author(s):  
S. Blaine Grover ◽  
David A. Petti ◽  
Michael E. Davenport
Keyword(s):  
High Temperature ◽  
Compressive Load ◽  
The United States ◽  
Performance Data ◽  
United States Department ◽  
The Third ◽  
Test Reactor ◽  
Irradiation Performance ◽  
And Control ◽  
High Temperature Gas

The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will irradiate up to six nuclear graphite creep experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The graphite experiments are being irradiated over an approximate eight year period to support development of a graphite irradiation performance data base on the new nuclear grade graphites now available for use in high temperature gas reactors. The goals of the irradiation experiments are to obtain irradiation performance data, including irradiation creep, at different temperatures and loading conditions to support design of the NGNP Very High Temperature Gas Reactor (VHTR), as well as other future gas reactors. The experiments each consist of a single capsule that contain six stacks of graphite specimens, with half of the graphite specimens in each stack under a compressive load, while the other half of the specimens are not be subjected to a compressive load during irradiation. The six stacks have differing compressive loads applied to the top half of diametrically opposite pairs of specimen stacks. A seventh specimen stack in the center of the capsule does not have a compressive load. The specimens are being irradiated in an inert sweep gas atmosphere with on-line temperature and compressive load monitoring and control. There are also samples taken of the sweep gas effluent to measure any oxidation or off-gassing of the specimens that may occur during initial start-up of the experiment. The first experiment, AGC-1, started its irradiation in September 2009, and the irradiation was completed in January 2011. The second experiment, AGC-2, started its irradiation in April 2011 and completed its irradiation in May 2012 [1]. The third experiment, AGC-3, is scheduled to start its irradiation in late November 2012 and complete in the late summer to fall of 2014. This paper will briefly discuss the design of the AGC-3 experiment and control systems, and present the irradiation results to date.

scholarly journals AXIAL FLUX PROFILE IN THE ADVANCED TEST REACTOR

2021 ◽  
Vol 247 ◽  
pp. 08007
Author(s):  
Nathan Manwaring ◽  
Michael Reichenberger
Keyword(s):  
Neutron Flux ◽  
Measurement Errors ◽  
The United States ◽  
Department Of Energy ◽  
United States Department ◽  
Axial Flux ◽  
Cooling Channels ◽  
Flux Profile ◽  
Test Reactor

This work demonstrates an approach to determine probability of perturbation of the axial profile of the thermal neutron flux in the Advanced Test Reactor. The axial flux profile is expected to follow a theoretical cosine shape, due to the minimal use of vertically-withdrawn shims. Reactivity is normally controlled by rotation of Outer Shim Control Cylinders, uniformly affecting neutron flux at all axial locations. The Advanced Test Reactor routinely accepts for irradiation experiments of a variety of designs. Among the analyses required by the safety basis approved by the United States Department of Energy is the characterization of a new experiment’s potential for perturbing the axial flux, which could exacerbate power peaking in the driver fuel. However, this perturbation can be more or less severe in different locations within the fuel. Therefore, the best characterization of axial flux perturbation requires knowledge of baseline axial flux. Such information is obtained by measuring decay in activated uranium flux wires irradiated at known positions in cooling channels in plate-type fuel elements. Due to variability in measured axial flux, it is not usually clear whether a given anomalous measurement is caused by an actual perturbation. Assuming normality in random measurement errors, the probability of an actual perturbation is quantified.

Demonstrating Nutrient Cost Gradients: A Brooklyn Case Study

2014 ◽  
Vol 84 (5-6) ◽  
pp. 244-251 ◽  
Author(s):  
Robert J. Karp ◽  
Gary Wong ◽  
Marguerite Orsi
Keyword(s):  
Low Income ◽  
Energy Content ◽  
Food Selection ◽  
The United States ◽  
United States Department ◽  
Micronutrient Deficiencies ◽  
Caloric Density ◽  
Low Income Families ◽  
The Cost ◽  
The Impact

Abstract. Introduction: Foods dense in micronutrients are generally more expensive than those with higher energy content. These cost-differentials may put low-income families at risk of diminished micronutrient intake. Objectives: We sought to determine differences in the cost for iron, folate, and choline in foods available for purchase in a low-income community when assessed for energy content and serving size. Methods: Sixty-nine foods listed in the menu plans provided by the United States Department of Agriculture (USDA) for low-income families were considered, in 10 domains. The cost and micronutrient content for-energy and per-serving of these foods were determined for the three micronutrients. Exact Kruskal-Wallis tests were used for comparisons of energy costs; Spearman rho tests for comparisons of micronutrient content. Ninety families were interviewed in a pediatric clinic to assess the impact of food cost on food selection. Results: Significant differences between domains were shown for energy density with both cost-for-energy (p < 0.001) and cost-per-serving (p < 0.05) comparisons. All three micronutrient contents were significantly correlated with cost-for-energy (p < 0.01). Both iron and choline contents were significantly correlated with cost-per-serving (p < 0.05). Of the 90 families, 38 (42 %) worried about food costs; 40 (44 %) had chosen foods of high caloric density in response to that fear, and 29 of 40 families experiencing both worry and making such food selection. Conclusion: Adjustments to USDA meal plans using cost-for-energy analysis showed differentials for both energy and micronutrients. These differentials were reduced using cost-per-serving analysis, but were not eliminated. A substantial proportion of low-income families are vulnerable to micronutrient deficiencies.

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