Search Results

Advanced search parameters have been applied.
open access

Japan 2011 Disaster: CRS Experts

Description: The following table provides access to names and contact information for CRS experts on policy concerns relating to the nuclear and humanitarian disaster unfolding in Japan. Specific policy areas are identified.
Date: March 15, 2011
Creator: Dolven, Ben
Partner: UNT Libraries Government Documents Department
open access

Fukushima Nuclear Crisis

Description: This report briefly discusses the March 11, 2001, earthquake off the east coast of Honshu, Japan's largest island. The earthquake caused an automatic shutdown of eleven of Japan's fifty-five operating nuclear power plants. The plants closes to the earthquake's epicenter, Fukushima and Onagawa, were damaged by the earthquake and resulting tsunami. This report also discusses efforts by the United States and other countries to provide assistance to Japan to deal with the nuclear crisis.
Date: March 15, 2011
Creator: Campbell, Richard J.
Partner: UNT Libraries Government Documents Department
open access

Effects of Radiation from Fukushima Daiichi on the U.S. Marine Environment

Description: The massive Tohoku earthquake and tsunami of March 11, 2011, caused extensive damage in northeastern Japan, including damage to the Fukushima Dai-ichi nuclear power installation, which resulted in the release of radiation. This report discusses concerns about the potential effects of this released radiation on the U.S. marine environment and resources.
Date: April 5, 2011
Creator: Buck, Eugene H.; Upton, Harold F. & Folger, Peter
Partner: UNT Libraries Government Documents Department
open access

Fukushima Nuclear Crisis

Description: This report briefly discusses the March 11, 2001 earthquake off the east coast of Honshu, Japan's largest island. The earthquake caused an automatic shutdown of eleven of Japan's fifty-five operating nuclear power plants, though the plants closest to the earthquake's epicenter, Fukushima and Onagawa, were damaged by the earthquake and resulting tsunami. This report also discusses efforts by the United States and other countries to provide assistance to Japan to deal with the nuclear crisis.
Date: April 4, 2011
Creator: Campbell, Richard J. & Holt, Mark
Partner: UNT Libraries Government Documents Department
open access

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)
Partner: UNT Libraries Government Documents Department
open access

10 CFR 830 Major Modification Determination for the ATR Diesel Bus (E-3) and Switchgear Replacement

Description: Near term replacement of aging and obsolescent original ATR equipment has become important to ensure ATR capability in support of NE’s long term national missions. To that end, a mission needs statement has been prepared for a non-major system acquisition which is comprised of three interdependent subprojects. The first project, subject of this determination, will replace the existent diesel-electrical bus (E-3) and associated switchgear. More specifically, INL proposes transitioning ATR to 100… more
Date: May 1, 2011
Creator: Duckwtiz, Noel
Partner: UNT Libraries Government Documents Department
open access

FY2010 ANNUAL REVIEW E-AREA LOW-LEVEL WASTE FACILITY PERFORMANCE ASSESSMENT AND COMPOSITE ANALYSIS

Description: The E-Area Low-Level Waste Facility (ELLWF) consists of a number of disposal units described in the Performance Assessment (PA)(WSRC, 2008b) and Composite Analysis (CA)(WSRC, 1997; WSRC, 1999): Low-Activity Waste (LAW) Vault, Intermediate Level (IL) Vault, Trenches (Slit Trenches [STs], Engineered Trenches [ETs], and Component-in-Grout [CIG] Trenches), and Naval Reactor Component Disposal Areas (NRCDAs). This annual review evaluates the adequacy of the approved 2008 ELLWF PA along with the Spec… more
Date: January 1, 2011
Creator: Butcher, T.; Swingle, R.; Crapse, K.; Millings, M. & Sink, D.
Partner: UNT Libraries Government Documents Department
open access

Establishment of a Hub for the Light Water Reactor Sustainability Online Monitoring Community

Description: Implementation of online monitoring and prognostics in existing U.S. nuclear power plants will involve coordinating the efforts of national laboratories, utilities, universities, and private companies. Internet-based collaborative work environments provide necessary communication tools to facilitate interaction between geographically diverse participants. Available technologies were considered, and a collaborative workspace was established at INL as a hub for the light water reactor sustainabil… more
Date: August 1, 2011
Creator: Lybeck, Nancy J.; Tawfik, Magdy S. & Pham, Binh T.
Partner: UNT Libraries Government Documents Department
open access

SOLVENT HOLD TANK SAMPLE RESULTS FOR MCU-11-314, MCU-11-315, MCU-11-316, MCU-11-317, MCU-11-318 AND MCU-11-319

Description: Savannah River National Laboratory (SRNL) analyzed solvent samples from Modular Caustic-Side Solvent Extraction Unit (MCU) in support of continuing operations. A quarterly analysis of the solvent is required to maintain solvent composition within specifications. Analytical results of the analyses of Solvent Hold Tank (SHT) samples MCU-11-314, MCU-11-315, MCU-11-316, MCU-11-317, MCU-11-318 and MCU-11-319 are reported. The results show that the solvent at MCU does not require an Isopar{reg_sign} … more
Date: June 9, 2011
Creator: Peters, T.; Washington, A.; Fondeur, F. & Fink, S.
Partner: UNT Libraries Government Documents Department
open access

TESTING OF ENHANCED CHEMICAL CLEANING OF SRS ACTUAL WASTE TANK 5F AND TANK 12H SLUDGES

Description: Forty three of the High Level Waste (HLW) tanks at the Savannah River Site (SRS) have internal structures that hinder removal of the last approximately five thousand gallons of waste sludge solely by mechanical means. Chemical cleaning can be utilized to dissolve the sludge heel with oxalic acid (OA) and pump the material to a separate waste tank in preparation for final disposition. This dissolved sludge material is pH adjusted downstream of the dissolution process, precipitating the sludge co… more
Date: August 22, 2011
Creator: Martino, C. & King, W.
Partner: UNT Libraries Government Documents Department
open access

OECD MCCI project Melt Eruption Test (MET) design report, Rev. 2. April 15, 2003.

Description: The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core-concrete interaction when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. The Mel… more
Date: May 23, 2011
Creator: Farmer, M. T.; Lomperski, S.; Kilsdonk, D. J.; Aeschlimann, R. W. & Basu, S.
Partner: UNT Libraries Government Documents Department
open access

LONG-TERM PERFORMANCE OF SOLID OXIDE STACKS WITH ELECTRODE-SUPPORTED CELLS OPERATING IN THE STEAM ELECTROLYSIS MODE

Description: Performance characterization and durability testing have been completed on two five-cell high-temperature electrolysis stacks constructed with advanced cell and stack technologies. The solid oxide cells incorporate a negative-electrode-supported multi-layer design with nickel-zirconia cermet negative electrodes, thin-film yttria-stabilized zirconia electrolytes, and multi-layer lanthanum ferrite-based positive electrodes. The per-cell active area is 100 cm2. The stack is internally manifolded w… more
Date: November 1, 2011
Creator: O'Brien, J. E.; O'Brien, R. C.; Zhang, X.; Tao, G. & Butler, B. J.
Partner: UNT Libraries Government Documents Department
open access

RADIATION DOSE ASSESSMENT FOR THE BIOTA OF TERRESTRIAL ECOSYSTEMS IN THE SHORELINE ZONE OF THE CHERNOBYL NUCLEAR POWER PLANT COOLING POND

Description: Radiation exposure of the biota in the shoreline area of the Chernobyl Nuclear Power Plant Cooling Pond was assessed to evaluate radiological consequences from the decommissioning of the Cooling Pond. The article addresses studies of radioactive contamination of the terrestrial faunal complex and radionuclide concentration ratios in bodies of small birds, small mammals, amphibians, and reptiles living in the area. The data were used to calculate doses to biota using the ERICA Tool software. Dos… more
Date: October 1, 2011
Creator: Farfan, E. & Jannik, T.
Partner: UNT Libraries Government Documents Department
open access

Evaluations of University of Wisconsin Silicon Carbide Temperature Monitors 300 LO and 400 LO B

Description: Silicon carbide (SiC) temperature monitors 05R4-02-A KG1403 (300 LO) and 05R4-01-A KG1415 (400 LO B) were evaluated at the High Temperature Test Lab (HTTL) to determine their peak irradiation temperatures. HTTL measurements indicate that the peak irradiation temperature for the 300 LO monitor was 295 {+-} 20 C and the peak irradiation temperature for the 400 LO B monitor was 294 {+-} 25 C. Two silicon carbide (SiC) temperature monitors irradiated in the Advanced Test Reactor (ATR) were evaluate… more
Date: December 1, 2011
Creator: Davis, K. L.; Rempe, J. L.; Knudson, D. L.; Chase, B. M. & Unruh, T. C.
Partner: UNT Libraries Government Documents Department
open access

OECD MCCI project enhancing instrumentation for reactor materials experiments, Rev. 0 September 3, 2002.

Description: Reactor safety experiments for studying the reactions of a molten core (corium) with water and/or concrete involve materials at extremely high temperature. Such high temperature severely restricts the types of sensors that can be employed to measure characteristics of the corium itself. Yet there is great interest in improving instrumentation so that the state of the melt can be established with more precision. In particular, it would be beneficial to increase both the upper range limit and acc… more
Date: May 23, 2011
Creator: Lomperski, S. & Basu, S.
Partner: UNT Libraries Government Documents Department
open access

ASSESSMENT OF THE ABILITY OF STANDARD SLURRY PUMPS TO MIX SOLIDS WITH LIQUIDS IN TANK 50H

Description: Tank 50H is the feed tank for the Saltstone Production Facility (SPF). In the summer of 2011, Tank 50H contained two standard slurry pumps and two quad volute slurry pumps. Current requirements for mixing operation is to run three pumps for one hour prior to initiating a feed transfer to SPF. Savannah River Site (SRS) Liquid Waste moved both of the Quad Volute pumps from Tank 50H to Tank 51H to replace pumps in Tank 51H that were failing. In addition, one of the standard pumps in Tank 50H exhib… more
Date: November 11, 2011
Creator: Poirier, M.
Partner: UNT Libraries Government Documents Department
open access

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
Partner: UNT Libraries Government Documents Department
open access

Ongoing Space Nuclear Systems Development in the United States

Description: Reliable, long-life power systems are required for ambitious space exploration missions. Nuclear power and propulsion options can enable a bold, new set of missions and introduce propulsion capabilities to achieve access to science destinations that are not possible with more conventional systems. Space nuclear power options can be divided into three main categories: radioisotope power for heating or low power applications; fission power systems for non-terrestrial surface application or for sp… more
Date: October 1, 2011
Creator: Bragg-Sitton, S.; Werner, J.; Johnson, S.; Houts, Michael G.; Palac, Donald T.; Mason, Lee S. et al.
Partner: UNT Libraries Government Documents Department
open access

Summary of Planned Implementation for the HTGR Lessons Learned Applicable to the NGNP

Description: This document presents a reconciliation of the lessons learned during a 2010 comprehensive evaluation of pertinent lessons learned from past and present high temperature gas-cooled reactors that apply to the Next Generation Nuclear Plant Project along with current and planned activities. The data used are from the latest Idaho National Laboratory research and development plans, the conceptual design report from General Atomics, and the pebble bed reactor technology readiness study from AREVA. O… more
Date: September 1, 2011
Creator: Mckirdy, Ian
Partner: UNT Libraries Government Documents Department
open access

PROJECT-SPECIFIC TYPE A VERIFICATION FOR THE BROOKHAVEN GRAPHITE RESEARCH REACTOR ENGINEERED CAP, BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK DCN 5098-SR-07-0

Description: The Oak Ridge Institute for Science and Education (ORISE) has reviewed the project documentation and data for the Brookhaven Graphite Research Reactor (BGRR) Engineered Cap at Brookhaven National Laboratory (BNL) in Upton, New York. The Brookhaven Science Associates (BSA) have completed removal of affected soils and performed as-left surveys by BSA associated with the BGRR Engineered Cap. Sample results have been submitted, as required, to demonstrate that remediation efforts comply with the cl… more
Date: July 15, 2011
Creator: Harpenau, Evan
Partner: UNT Libraries Government Documents Department
open access

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.
Partner: UNT Libraries Government Documents Department
open access

Integration of High Temperature Gas-cooled Reactor Technology with Oil Sands Processes

Description: This paper summarizes an evaluation of siting an HTGR plant in a remote area supplying steam, electricity and high temperature gas for recovery and upgrading of unconventional crude oil from oil sands. The area selected for this evaluation is the Alberta Canada oil sands. This is a very fertile and active area for bitumen recovery and upgrading with significant quantities piped to refineries in Canada and the U.S Additionally data on the energy consumption and other factors that are required to… more
Date: October 1, 2011
Creator: Demick, L. E.
Partner: UNT Libraries Government Documents Department
open access

THE FINAL DEMISE OF EAST TENNESSEE TECHNOLOGY PARK BUILDING K-33 Health Physics Society Annual Meeting West Palm Beach, Florida June 27, 2011

Description: Building K-33 was constructed in 1954 as the final section of the five-stage uranium enrichment cascade at the Oak Ridge Gaseous Diffusion Plant (ORGDP). The two original building (K-25 and K-27) were used to produce weapons grade highly enriched uranium (HEU). Building K-29, K-31, and K-33 were added to produce low enriched uranium (LEU) for nuclear power plant fuel. During ORGDP operations K-33 produced a peak enrichment of 2.5%. Thousands of tons of reactor tails fed into gaseous diffusion p… more
Date: June 27, 2011
Creator: King, David A.
Partner: UNT Libraries Government Documents Department
open access

Independent Confirmatory Survey Report for the University of Arizona Nuclear Reactor Laboratory, Tucson, Arizona

Description: The University of Arizona (University) research reactor is a TRIGA swimming pool type reactor designed by General Atomics and constructed at the University in 1958. The reactor first went into operation in December of 1958 under U.S. Nuclear Regulatory Commission (NRC) license R-52 until final shut down on May 18, 2010. Initial site characterization activities were conducted in February 2009 during ongoing reactor operations to assess the radiological status of the Nuclear Reactor Laboratory (N… more
Date: November 11, 2011
Creator: Altic, Nick A.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen