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in subjects: %22Natural gas%22

open access

Examples of the use of PRA in the design process and to support modifications

Many, if not most, of the world`s commercial nuclear power plants have been the subject of plant-specific probabilistic safety assessments (PSAs). A growing number of other nuclear facilities as well as other types of industrial installations have been the focus of plant-specific PSAs. Such studies have provided valuable information concerning the nature of the fisk of the individual facility and have been utilized to identify opportunities to manage that risk. This paper explores the risk mana… more

Date: September 7, 1993

Creator: Johnson, D. H.; Bley, D. C.; Lin, J. C.; Schueller, J.; van Otterloo, R. W.; Ramsey, C. T. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Post-Closure Monitoring Report for Corrective Action Unit 329: Area 22 Desert Rock Airstrip Fuel Spill, Nevada Test Site, Nevada (Rev. No.: 0, June 2002)

There was an increase in total petroleum hydrocarbons (TPH) concentrations at all three depths within Borehole DRA-0. The oxygen concentration at 40 ft below ground surface (bgs) decreased. There was also an increase in carbon dioxide concentration at that depth. The decrease in oxygen concentrations and the increase in carbon dioxide concentration at the 40 ft bgs level could be possible indicators of natural attenuation. It is not possible to determine trends or biodegradation rates with the … more

Date: June 6, 2002

Creator: United States. National Nuclear Security Administration. Nevada Operations Office.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Sister Lab Program Prospective Partner Nuclear Profile: Malaysia

The Malaysian Deputy Prime Minister Tun Dr Ismail Abdul Rahman suggested in the early 1970s that Malaysia should have a role in the development of nuclear science and technology for peaceful purposes. Accordingly, the Center for the Application of Nuclear Energy (CRANE) was established, with a focus on the development of a scientific and technical pool critical to a national nuclear power program. The Malaysian Cabinet next established the Tun Ismail Atomic Research Center (TIARC) under the Min… more

Date: December 14, 2006

Creator: Bissani, M & Tyson, S

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

THE INTEGRATION OF PROCESS HEAT APPLICATIONS TO HIGH TEMPERATURE GAS REACTORS

A high temperature gas reactor, HTGR, can produce industrial process steam, high-temperature heat-transfer gases, and/or electricity. In conventional industrial processes, these products are generated by the combustion of fossil fuels such as coal and natural gas, resulting in significant emissions of greenhouse gases such as carbon dioxide. Heat or electricity produced in an HTGR could be used to supply process heat or electricity to conventional processes without generating any greenhouse gas… more

Date: November 1, 2011

Creator: McKellar, Michael G.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

A Strategy for Nuclear Energy Research and Development

The United States is facing unprecedented challenges in climate change and energy security. President-elect Obama has called for a reduction of CO2 emissions to 1990 levels by 2020, with a further 80% reduction by 2050. Meeting these aggressive goals while gradually increasing the overall energy supply requires that all non-emitting technologies must be advanced. The development and deployment of nuclear energy can, in fact, help the United States meet several key challenges: 1) Increase the el… more

Date: December 1, 2008

Creator: Bennett, Ralph G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Computational Fluid Dynamics Analyses on Very High Temperature Reactor Air Ingress

A preliminary computational fluid dynamics (CFD) analysis was performed to understand density-gradient-induced stratified flow in a Very High Temperature Reactor (VHTR) air-ingress accident. Various parameters were taken into consideration, including turbulence model, core temperature, initial air mole-fraction, and flow resistance in the core. The gas turbine modular helium reactor (GT-MHR) 600 MWt was selected as the reference reactor and it was simplified to be 2-D geometry in modeling. The … more

Date: July 1, 2009

Creator: Oh, Chang H; Kim, Eung S.; Schultz, Richard; Petti, David & Kang, Hyung S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Scaled Experimental Modeling of VHTR Plenum Flows

Abstract The Very High Temperature Reactor (VHTR) is the leading candidate for the Next Generation Nuclear Power (NGNP) Project in the U.S. which has the goal of demonstrating the production of emissions free electricity and hydrogen by 2015. Various scaled heated gas and water flow facilities were investigated for modeling VHTR upper and lower plenum flows during the decay heat portion of a pressurized conduction-cooldown scenario and for modeling thermal mixing and stratification (“thermal st… more

Date: April 1, 2007

Creator: 15, ICONE

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Integrating Nuclear Energy to Oilfield Operations – Two Case Studies

Fossil fuel resources that require large energy inputs for extraction, such as the Canadian oil sands and the Green River oil shale resource in the western USA, could benefit from the use of nuclear power instead of power generated by natural gas combustion. This paper discusses the technical and economic aspects of integrating nuclear energy with oil sands operations and the development of oil shale resources. A high temperature gas reactor (HTGR) that produces heat in the form of high pressur… more

Date: November 1, 2011

Creator: Robertson, Eric P.; Nelson, Lee O.; McKellar, Michael G.; Gandrik, Anastasia M. & Patterson, Mike W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Classification of alarm processing techniques and human performance issues

Human factors reviews indicate that conventional alarm systems based on the one sensor, one alarm approach, have many human engineering deficiencies, a paramount example being too many alarms during major disturbances. As an effort to resolve these deficiencies, various alarm processing systems have been developed using different techniques. To ensure their contribution to operational safety, the impacts of those systems on operating crew performance should be carefully evaluated. This paper br… more

Date: May 1, 1993

Creator: Kim, I. S. & O'Hara, J. M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Classification of alarm processing techniques and human performance issues

Date: January 1, 1993

Creator: Kim, I. S. & O'Hara, J. M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Use of DRACS to Enhance HTGRs Passive Safety and Economy

This paper discusses the use of DRACS to Enhance HTGRs Passive Safety and Economy. One of the important requirements for Gen. IV High Temperature Gas Cooled Reactors (HTGR) is passive safety. Currently all the HTGR designs use Reactor Vessel Auxiliary Cooling System (RVACS) for passive decay heat removal. [1] The decay heat first is transferred to core barrel by conduction and radiation, and then to reactor vessel by thermal radiation and convection; finally the decay heat is transferred to nat… more

Date: June 1, 2011

Creator: Zhao, Haihua; Zhang, Hongbin & Zou, Ling

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Atoms for Peace After 50 Years: The New Challenges and Opportunities

This report draws on a series of international workshops held to mark the fiftieth anniversary of President Dwight D. Eisenhower's Atoms for Peace address before the United Nations General Assembly. A half-century after President Eisenhower's landmark speech, the world is vastly different, but mankind still faces the challenge he identified--gaining the benefits of nuclear technology in a way that limits the risks to security. Fifty years after Eisenhower declared that the people of the world s… more

Date: November 12, 2003

Creator: Schock, R N

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Relative risks of energy sources

This paper compares the risks associated with various energy sources in an attempt to demonstrate the relative safety of nuclear energy. (JEF)

Date: January 1, 1990

Creator: Haire, M.J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Sodemme: natural circulation thermal-hydraulics code for HTGR transient analysis

The SODEMME code provides a Solution to the One Dimensional Energy, Mass and Momentum Equations for a system of ''volumes'' and ''segments'' that comprise a circulating system containing a gaseous coolant. Input consists of a description of the system's geometry, the user's choice of some control variables, specification of the initial and time-dependent boundary conditions and setting various options for items such as pumping head, heat transfe… more

Date: July 1, 1977

Creator: Epel, L.G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Thermal response of core and central-cavity components of a high-temperature gas-cooled reactor in the absence of forced convection coolant flow. [NATCON code]

A means of determining the thermal responses of the core and the components of a high-temperature gas-cooled reactor after loss of forced coolant flow is discussed. A computer program, using a finite-difference technique, is presented together with a solution of the confined natural convection. The results obtained are reasonable and demonstrate that the computer program adequately represents the confined natural convection.

Date: September 1, 1976

Creator: Whaley, R. L. & Sanders, J. P.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Gas-Cooled Fast Breeder Reactor Preliminary Safety Information Document, Amendment 10. GCFR residual heat removal system criteria, design, and performance

This report presents a comprehensive set of safety design bases to support the conceptual design of the gas-cooled fast breeder reactor (GCFR) residual heat removal (RHR) systems. The report is structured to enable the Nuclear Regulatory Commission (NRC) to review and comment in the licensability of these design bases. This report also presents information concerning a specific plant design and its performance as an auxiliary part to assist the NRC in evaluating the safety design bases.

Date: September 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Inherent design features of the GCFR

This paper discusses several inherent design features of the GCFR that enhance its safety and presents analyses to demonstrate the degree of protection they provide. These features are a subset of a larger group of potential inherent features that form the third line of protection (LOP-3) for the GCFR. The function of LOP-3 is to demonstrate that the inherent response of the reactor system will limit core damage even if active cooling and shutdown systems in LOP-1 and LOP-2 fail. By providing t… more

Date: May 1, 1980

Creator: Medwid, W.; Breher, W.; Shenoy, A. & Elliott, R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Natural convection effects in a GCFR subassembly during loss of flow with scram conditions

Natural convection in a full length GCFR fuel assembly was investigated by experiment and analysis. Non-convecting analysis is shown to be in substantial disagreement with experiment. A new natural convection model using the SCORIA code for GCFR fuel assemblies and the COBRA-IV model for natural convection is presented. The SCORIA/COBRA analytic predictions agree much better with the experiment. The remaining differences are qualitatively explainable.

Date: October 1, 1979

Creator: Croft, M.Z.; Del Bene, J.V. & Torri, A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Personnel Radiation Exposure in HTGR Plants

Occupational radiation exposures in high-temperature gas-cooled reactor (HTGR) plants were assessed. The expected rate of dose accumulations for a large HTGR steam cycle (HTGR-SC) unit is 0.07 man-rem/MW(e)y, while the design basis is 0.17 man-rem/MW(e)y. The comparable figure for actual light water reactor (LWR) experience is 1.3 man-rem/MW(e)y. The favorable HTGR occupational exposure is supported by results from the Peach Bottom Unit No. 1 HTGR and Fort St. Vrain HTGR plants and by operating… more

Date: January 1, 1980

Creator: Su, S. & Engholm, B. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Manufacturing sector carbon dioxide emissions in nine OECD countries 1973--87: A Divisia index decomposition to changes in fuel mix, emission coefficients, industry structure, energy intensities, and international structure

In this paper the reduction in energy-related manufacturing carbon dioxide emissions for nine OECD countries in the period 1973 to 1987 is analyzed. Carbon dioxide emissions are estimated from energy use data. The emphasis is on carbon dioxide intensities, defined as emissions divided by value added. The overall manufacturing carbon dioxide intensity for the nine OECD countries was reduced by 42% in the period 1973--1987. Five fuels are specified together with six subsectors of manufacturing. C… more

Date: November 1, 1990

Creator: Torvanger, A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Energy technology impacts on agriculture with a bibliography of models for impact assessment on crop ecosystems

Possible impacts of energy technologies on agriculture are evaluated, and some of the available simulation models that can be used for predictive purposes are identified. An overview of energy technologies and impacts on the environment is presented to provide a framework for the commentary on the models. Coal combustion is shown to have major impacts on the environment and these will continue into the next century according to current Department of Energy projections. Air pollution effects wil… more

Date: September 1, 1979

Creator: Rupp, E. M.; Luxmoore, R. J. & Parzyck, D. C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Evaluation of closure alternatives for the Building 3001 Storage Canal at Oak Ridge National Laboratory, Oak Ridge, Tennessee

The Bldg. 3001 Storage Canal at ORNL is leaking approximately 400 gal of water per day. This report presents the Bechtel National Inc. (BNI) Team's evaluation of plans and presents recommendations for interim closure alternatives to stop the release of radionuclides and potential release of heavy metals into the environment. This is a conceptual evaluation and does not include detailed engineering of physical mitigation methods. The alternatives address only interim closure measures and not fin… more

Date: February 1, 1992

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

A safety assessment of the use of graphite in nuclear reactors licensed by the US NRC

This report reviews existing literature and knowledge on graphite burning and on stored energy accumulation and releases in order to assess what role, if any, a stored energy release can have in initiating or contributing to hypothetical graphite burning scenarios in research reactors. It also addresses the question of graphite ignition and self-sustained combustion in the event of a loss-of-coolant accident (LOCA). The conditions necessary to initiate and maintain graphite burning are summariz… more

Date: September 1, 1987

Creator: Schweitzer, D.G.; Gurinsky, D.H.; Kaplan, E. & Sastre, C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Chernobyl source term estimation

The Chernobyl source term available for long-range transport was estimated by integration of radiological measurements with atmospheric dispersion modeling and by reactor core radionuclide inventory estimation in conjunction with WASH-1400 release fractions associated with specific chemical groups. The model simulations revealed that the radioactive cloud became segmented during the first day, with the lower section heading toward Scandinavia and the upper part heading in a southeasterly direct… more

Date: September 1, 1990

Creator: Gudiksen, P. H.; Harvey, T. F. & Lange, R.

Item Type: Article

Partner: UNT Libraries Government Documents Department