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Neutronics, Steady-State, and Transient Analyses for the Poland Maria Reactor for Irradiation Testing of Leu Lead Test Fuel Assemblies From Cerca : Anl Independent Verification Results.

Description: The MARIA reactor at the Institute of Atomic Energy (IAE) in Swierk (30 km SE of Warsaw) in the Republic of Poland is considering conversion from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel assemblies (FA). The FA design in MARIA is rather unique; a suitable LEU FA has never been designed or tested. IAE has contracted with CERCA (the fuel supply portion of AREVA in France) to supply 2 lead test assemblies (LTA). The LTAs will be irradiated in MARIA to burnup level of at least… more
Date: June 7, 2011
Creator: Garner, P. L. & Hanan, N. A. (Nuclear Engineering Division)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Completion Report for Well ER-EC-15 Corrective Action Units 101 and 102: Central and Western Pahute Mesa

Description: Well ER-EC-15 was drilled for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office in support of the Nevada Environmental Restoration Project at the Nevada National Security Site (formerly known as the Nevada Test Site), Nye County, Nevada. The well was drilled in October and November 2010, as part of the Pahute Mesa Phase II drilling program. The primary purpose of the well was to provide detailed hydrogeologic information in the Tertiary volcanic section … more
Date: May 31, 2011
Creator: National Security Technologies, LLC
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advanced High Temperature Reactor Systems and Economic Analysis

Description: The Advanced High Temperature Reactor (AHTR) is a design concept for a large-output [3400 MW(t)] fluoride-salt-cooled high-temperature reactor (FHR). FHRs, by definition, feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The AHTR's large thermal output enables direct comparison of its performance and requirements with other high output reactor concepts. As high-temperature plants, FHRs can support eit… more
Date: September 1, 2011
Creator: Holcomb, David Eugene; Peretz, Fred J & Qualls, A L
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRISMATIC CORE COUPLED TRANSIENT BENCHMARK

Description: The Prismatic Modular Reactor (PMR) is one of the High Temperature Reactor (HTR) design concepts that have existed for some time. Several prismatic units have operated in the world (DRAGON, Fort St. Vrain, Peach Bottom) and one unit is still in operation (HTTR). The deterministic neutronics and thermal-fluids transient analysis tools and methods currently available for the design and analysis of PMRs have lagged behind the state of the art compared to LWR reactor technologies. This has motivate… more
Date: June 1, 2011
Creator: Ortensi, J.; Pope, M.A.; Strydom, G.; Sen, R.S.; DeHart, M.D.; Gougar, H.D. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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An Assessment of Energy Potential at Non-Powered Dams in the United States

Description: fleet by 15%. A majority of this potential is concentrated in just 100 NPDs, which could contribute approximately 8 GW of clean, reliable hydropower; the top 10 facilities alone could add up to 3 GW of new hydropower. Eighty-one of the 100 top NPDs are U.S. Army Corps of Engineers (USACE) facilities, many of which, including all of the top 10, are navigation locks on the Ohio River, Mississippi River, Alabama River, and Arkansas River, as well as their major tributaries. This study also shows t… more
Date: April 1, 2012
Creator: Hadjerioua, Boualem; Wei, Yaxing & Kao, Shih-Chieh
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

IMPACT OF CURING TEMPERATURE ON THE SATURATED LIQUID PERMEABILITY OF SALTSTONE

Description: This report focuses on the impact of curing temperature on the performance properties of simulated Saltstone mixes. The key performance property of interest is saturated liquid permeability (measured as hydraulic conductivity), an input to the Performance Assessment (PA) modeling for the Saltstone Disposal Facility (SDF). Therefore, the current study was performed to measure the dependence of saturated hydraulic conductivity on curing temperature of Saltstone mixes, to correlate these results w… more
Date: February 14, 2011
Creator: Williams, F. & Harbour, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Modeling Single Well Injection-Withdrawal (SWIW) Tests for Characterization of Complex Fracture-Matrix Systems

Description: The ability to reliably predict flow and transport in fractured porous rock is an essential condition for performance evaluation of geologic (underground) nuclear waste repositories. In this report, a suite of programs (TRIPOLY code) for calculating and analyzing flow and transport in two-dimensional fracture-matrix systems is used to model single-well injection-withdrawal (SWIW) tracer tests. The SWIW test, a tracer test using one well, is proposed as a useful means of collecting data for site… more
Date: November 1, 2010
Creator: Cotte, F.P.; Doughty, C. & Birkholzer, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

AFIP-6 Breach Assessment Report

Description: Analysis of the AFIP-6 experiment is summarized in this report in order to determine the cause of gaseous fission product release observed during irradiation. During the irradiation, a series of small fission product releases were observed. In order to limit the potential for primary coolant contamination, the operating cycle was terminated and the AFIP-6 experiment was removed for examination. Both in-canal and post-irradiation examination revealed the presence of an unusually thick oxide laye… more
Date: February 1, 2011
Creator: Wachs, Dan; Robinson, Adam & Medvedev, Pavel
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bentonite alteration due to thermal-hydro-chemical processes during the early thermal period in a nuclear waste repository

Description: After closure of an underground nuclear waste repository, the decay of radionuclides will raise temperature in the repository, and the bentonite buffer will resaturate by water inflow from the surrounding host rock. The perturbations from these thermal and hydrological processes are expected to dissipate within hundreds to a few thousand years. Here, we investigate coupled thermal-hydro-chemical processes and their effects on the short-term performance of a potential nuclear waste repository lo… more
Date: February 1, 2011
Creator: Xu, T.; Senger, R. & Finsterle, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Aquifer Testing and Rebound Study in Support of the 100-H Deep Chromium Investigation

Description: The 100-HR-3 Groundwater Operable Unit (OU) second Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) 5-year review (DOEIRL-2006-20, The Second CERCLA Five-Year Review Report for the Hanford Site) set a milestone to conduct an investigation of deep hexavalent chromium contamination in the sediments of the Ringold upper mud (RUM) unit, which underlies the unconfined aquifer in the 100-H Area. The 5-year review noted that groundwater samples from one deep well … more
Date: November 5, 2010
Creator: Smoot, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Marine Hydrokinetic Turbine Power-Take-Off Design for Optimal Performance and Low Impact on Cost-of-Energy: Preprint

Description: Marine hydrokinetic devices are becoming a popular method for generating marine renewable energy worldwide. These devices generate electricity by converting the kinetic energy of moving water, wave motion or currents, into electrical energy through the use of a Power-Take-Off (PTO) system. Most PTO systems incorporate a mechanical or hydraulic drive train, power generator and electric control/conditioning system to deliver the generated electric power to the grid at the required state. Like win… more
Date: April 1, 2012
Creator: Beam, M.; Kline, B.; Elbing, B.; Straka, W.; Fontaine, A.; Lawson, M. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

AFIP-6 Irradiation Summary Report

Description: The Advanced Test Reactor (ATR) Full size plate In center flux trap Position (AFIP) experiment AFIP-6 was designed to evaluate the performance of monolithic uranium-molybdenum (U-Mo) fuels at a length prototypic to that of the ATR fuel plates (45 inches in length). The AFIP-6 test was the first test with plates in a swaged condition with longer fuel zones of approximately 22.5 inches in length1,2. The following report summarizes the life of the AFIP-6 experiment through end of irradiation, incl… more
Date: September 1, 2011
Creator: Perez, Danielle M; Lillo, M. A.; Chang, G. S.; Roth, G. A.; Woolstenhulme, N. E. & Wachs, D. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

T-TY Tank Farm Interim Surface Barrier Demonstration—Vadose Zone Monitoring Plan

Description: The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank of the 241-T Tank Farm in 1973. Five tanks are assumed to have leaked in the TY Farm. Many of the contaminants from those leaks still reside within the vadose zone within the T and TY Tank Farm… more
Date: September 27, 2010
Creator: Zhang, Z. F.; Strickland, Christopher E.; Field, Jim G. & Parker, Danny L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Pahute Mesa Well Development and Testing Analyses for Wells ER-20-7, ER-20-8 #2, and ER-EC-11, Revision 1

Description: This report analyzes the following data collected from ER-20-7, ER-20-8 No.2, and ER-EC-11 during WDT operations: (1) Chemical indicators of well development (Section 2.0); (2) Static hydraulic head (Section 3.0); (3) Radiochemistry and geochemistry (Section 4.0); (4) Drawdown observed at locations distal to the pumping well (Section 5.0); and (5) Drilling water production, flow logs, and temperature logs (Section 6.0). The new data are further considered with respect to existing data as to how… more
Date: December 1, 2011
Creator: Ruskauff, Greg
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Power distributions in fresh and depleted LEU and HEU cores of the MITR reactor.

Description: The Massachusetts Institute of Technology Reactor (MITR-II) is a research reactor in Cambridge, Massachusetts designed primarily for experiments using neutron beam and in-core irradiation facilities. It delivers a neutron flux comparable to current LWR power reactors in a compact 6 MW core using Highly Enriched Uranium (HEU) fuel. In the framework of its non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used… more
Date: April 4, 2012
Creator: Wilson, E. H.; Horelik, N. E.; Dunn, F. E.; Newton, T. H., Jr.; Hu, L.; Stevens, J. G. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

AFIP-4 Irradiation Summary Report

Description: The Advanced Test Reactor (ATR) Full size plate In center flux trap Position (AFIP) experiment AFIP-4 was designed to evaluate the performance of monolithic uranium-molybdenum (U-Mo) fuels at a scale prototypic of research reactor fuel plates. The AFIP-4 test further examine the fuel/clad interface and its behavior under extreme conditions. After irradiation, fission gas retention measurements will be performed during post irradiation (PIE). The following report summarizes the life of the AFIP-… more
Date: September 1, 2011
Creator: Perez, Danielle M.; Lillo, Misti A.; Chang, Gray S.; Roth, Glenn A.; Woolstenhulme, Nicolas & Wachs, Daniel M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Computational Fluid Dynamics Modeling of the John Day Dam Tailrace

Description: US Army Corps of Engineers - Portland District required that a two-dimensional (2D) depth-averaged and a three-dimensional (3D) free-surface numerical models to be developed and validated for the John Day tailrace. These models were used to assess potential impact of a select group of structural and operational alternatives to tailrace flows aimed at improving fish survival at John Day Dam. The 2D model was used for the initial assessment of the alternatives in conjunction with a reduced-scale … more
Date: July 8, 2010
Creator: Rakowski, Cynthia L.; Perkins, William A.; Richmond, Marshall C. & Serkowski, John A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Qualification of the Joints for the ITER Central Solenoid

Description: The ITER Central Solenoid has 36 interpancake joints, 12 bus joints, and 12 feeder joints in the magnet. The joints are required to have resistance below 4 nOhm at 45 kA at 4.5 K. The US ITER Project Office developed two different types of interpancake joints with some variations in details in order to find a better design, qualify the joints, and establish a fabrication process. We built and tested four samples of the sintered joints and two samples with butt-bonded joints (a total of eight jo… more
Date: September 1, 2011
Creator: Martovetsky, N.; Berryhill, A. & Kenney, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Annual Report of Monitoring at Barnes, Kansas, in 2010

Description: The Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) operated a grain storage facility at Barnes, Kansas, in 1949-1974. Carbon tetrachloride contamination was initially detected in 1986 in the town's public water supply wells. In 2006-2007, the CCC/USDA conducted a comprehensive targeted investigation at and near its former property in Barnes to characterize this contamination. Those results were reported previously (Argonne 2008a). The results of that investigation… more
Date: May 25, 2011
Creator: LaFreniere, L. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Carbon Mineralization by Aqueous Precipitation for Beneficial Use of CO2 from Flue Gas

Description: Calera's innovative Mineralization via Aqueous Precipitation (MAP) technology for the capture and conversion of CO{sub 2} to useful materials for use in the built environment was further developed and proven in the Phase 1 Department of Energy Grant. The process was scaled to 300 gallon batch reactors and subsequently to Pilot Plant scale for the continuous production of product with the production of reactive calcium carbonate material that was evaluated as a supplementary cementitious materia… more
Date: June 30, 2010
Creator: Constantz, Brent; Seeker, Randy & Devenney, Martin
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DYNAMIC MODELING STRATEGY FOR FLOW REGIME TRANSITION IN GAS-LIQUID TWO-PHASE FLOWS

Description: In modeling gas-liquid two-phase flows, the concept of flow regime has been used to characterize the global interfacial structure of the flows. Nearly all constitutive relations that provide closures to the interfacial transfers in two-phase flow models, such as the two-fluid model, are often flow regime dependent. Currently, the determination of the flow regimes is primarily based on flow regime maps or transition criteria, which are developed for steady-state, fully-developed flows and widely… more
Date: September 1, 2011
Creator: Wang, X.; Sun, X. & Zhao, H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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TANKS 18 AND 19-F STRUCTURAL FLOWABLE GROUT FILL MATERIAL EVALUATION AND RECOMMENDATIONS

Description: Cementitious grout will be used to close Tanks 18-F and 19-F. The functions of the grout are to: (1) physically stabilize the final landfill by filling the empty volume in the tanks with a non compressible material; (2) provide a barrier for inadvertent intrusion into the tank; (3) reduce contaminant mobility by (a) limiting the hydraulic conductivity of the closed tank and (b) reducing contact between the residual waste and infiltrating water; and (4) providing an alkaline, chemically reducing… more
Date: November 1, 2011
Creator: Stefanko, D. & Langton, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Combined Neutronic-Thermal Hydraulic Model of CERMET NTR Reactor

Description: Abstract. Two different CERMET fueled Nuclear Thermal Propulsion reactors were modeled to determine the optimum coolant channel surface area to volume ratio required to cool a 25,000 lbf rocket engine operating at a specific impulse of 940 seconds. Both reactor concepts were computationally fueled with hexagonal cross section fuel elements having a flat-to-flat distance of 3.51 cm and containing 60 vol.% UO2 enriched to 93wt.%U235 and 40 vol.% tungsten. Coolant channel configuration consisted o… more
Date: February 1, 2011
Creator: Webb, Jonathan A.; Gross, Brian & Taitano, William T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

MODELING STRATEGIES TO COMPUTE NATURAL CIRCULATION USING CFD IN A VHTR AFTER A LOFA

Description: A prismatic gas-cooled very high temperature reactor (VHTR) is being developed under the next generation nuclear plant program (NGNP) of the U.S. Department of Energy, Office of Nuclear Energy. In the design of the prismatic VHTR, hexagonal shaped graphite blocks are drilled to allow insertion of fuel pins, made of compacted TRISO fuel particles, and coolant channels for the helium coolant. One of the concerns for the reactor design is the effects of a loss of flow accident (LOFA) where the coo… more
Date: November 1, 2012
Creator: Tung, Yu-Hsin; Johnson, Richard W.; Chieng, Ching-Chang & Ferng, Yuh-Ming
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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