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Scoping Analysis of Source Term and Functional Containment Attenuation Factors

Description: In order to meet future regulatory requirements, the Next Generation Nuclear Plant (NGNP) Project must fully establish and validate the mechanistic modular high temperature gas-cooled reactor (HTGR) source term. This is not possible at this stage in the project, as significant uncertainties in the final design remain unresolved. In the interim, however, there is a need to establish an approximate characterization of the source term. The NGNP team developed a simplified parametric model to estab… more
Date: January 1, 2012
Creator: Lowry, Pete
Partner: UNT Libraries Government Documents Department
open access

On the benefits of an integrated nuclear complex for Nevada

Description: An integrated nuclear complex is proposed for location at the Nevada Test Site. In addition to solving the nuclear waste disposal problem, this complex would tremendously enhance the southern Nevada economy, and it would provide low cost electricity to each resident and business in the affected counties. Nuclear industry and the national economy would benefit because the complex would demonstrate the new generation of safer nuclear power plants and revitalize the industry. Many spin-offs of the… more
Date: January 1, 1994
Creator: Blink, James A. & Halsey, William G.
Partner: UNT Libraries Government Documents Department
open access

Comparison of options for plutonium disposal reactors. Revision 1

Description: The end of the Cold War has resulted in an excess of plutonium in the weapons stockpiles of the United States and other nations. A number of mostly reactor-based systems have been proposed to denature this plutonium, as opposed to storing and guarding it indefinitely. A Department of Energy task force has been set up to consider this problem, and the National Academy of Sciences is evaluating it as well. In this report, three major reactor types -- the Advanced Light Water Reactor (ALWR), the A… more
Date: January 1, 1993
Creator: Buckner, M.; Radder, J. A. & Inhaber, H.
Partner: UNT Libraries Government Documents Department
open access

Current Abstracts Nuclear Reactors and Technology

Description: This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past m… more
Date: January 1, 1993
Creator: Bales, J. D. & Hicks, S. C.
Partner: UNT Libraries Government Documents Department
open access

Assessment of engineering plant analyzer with Peach Bottom 2 stability tests

Description: Engineering Plant Analyzer (EPA) has been developed to simulate plant transients for Boiling Water Reactor (BWR). Recently, this code has been used to simulate LaSalle-2 instability event which was initiated by a failure in the feed water heater. The simulation was performed for the scram conditions and for the postulated failure in the scram. In order to assess the capability of the EPA to simulate oscillatory flows as observed in the LaSalle event, EPA has been benchmarked with the available … more
Date: January 1, 1992
Creator: Rohatgi, U.S.; Mallen, A.N.; Cheng, H.S. & Wulff, W.
Partner: UNT Libraries Government Documents Department
open access

Innovative safety features of the modular HTGR

Description: The Modular High Temperature Gas-Cooled Reactor (MHTGR) is an advanced reactor concept under development through a cooperative program involving the US Government, the nuclear industry, and the utilities. Near-term development is focused on electricity generation. The top-level safety requirement is that the plant's operation not disturb the normal day-to-day activities of the public. Quantitatively, this requires that the design meet the US Environmental Protection Agency's Protective Action G… more
Date: January 1, 1992
Creator: Silady, F.A. & Simon, W.A.
Partner: UNT Libraries Government Documents Department
open access

Innovative safety features of the modular HTGR

Description: The Modular High Temperature Gas-Cooled Reactor (MHTGR) is an advanced reactor concept under development through a cooperative program involving the US Government, the nuclear industry, and the utilities. Near-term development is focused on electricity generation. The top-level safety requirement is that the plant`s operation not disturb the normal day-to-day activities of the public. Quantitatively, this requires that the design meet the US Environmental Protection Agency`s Protective Action G… more
Date: January 1, 1992
Creator: Silady, F. A. & Simon, W. A.
Partner: UNT Libraries Government Documents Department
open access

Non-isotropic thermal behavior of an MHTGR fuel block: Impact upon reactivity feedback

Description: This report discusses lumped parameter and detailed multi-dimensional thermal analyses of a New Production Modular High Temperature Gas Cooled Reactor (NP-MHTGR) fuel block were conducted that indicated that during a power transient, the target temperature would rise significantly later than the fuel temperature. This behavior, which is due to radiative, convective and conductive heat transport phenomena within the fuel block coupled with the significantly different thermal physical properties … more
Date: January 1, 1992
Creator: Delpech, M. (CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France)); Singer, R. M. & Finck, P. J. (Argonne National Lab., IL (United States))
Partner: UNT Libraries Government Documents Department
open access

Nuclear Reactors and Technology

Description: This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past m… more
Date: January 1, 1992
Creator: Cason, D. L. & Hicks, S. C.
Partner: UNT Libraries Government Documents Department
open access

Safety aspects of forced flow cooldown transients in modular high temperature gas-cooled reactors

Description: During some of the design basis accidents in Modular High Temperature Gas Cooled Reactors (MHTGRs) the main Heat Transport System (HTS) and the Shutdown Cooling System (SCS), are assumed to have failed. Decay heat is then removed by the passive Reactor Cavity Cooling System (RCCS) only. If either forced flow cooling system becomes available during such a transient, its restart could significantly reduce the down-time. This paper uses the THATCH code to examine whether such restart, during a per… more
Date: January 1, 1992
Creator: Kroeger, P. G.
Partner: UNT Libraries Government Documents Department
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Accident simulation and consequence analysis in support of MHTGR safety evaluations

Description: This paper summarizes research performed at Oak Ridge National Laboratory (ORNL) to assist the Nuclear Regulatory Commission (NRC) in preliminary determinations of licensability of the US Department of Energy (DOE) reference design of a standard modular high-temperature gas-cooled reactor (MHTGR). The work described includes independent analyses of core heatup and steam ingress accidents, and the reviews and analyses of fuel performance and fission product transport technology.
Date: January 1, 1991
Creator: Ball, S. J.; Wichner, R. P.; Smith, O. L.; Conklin, J. C. (Oak Ridge National Lab., TN (United States)) & Barthold, W. P. (Barthold Associates, Inc., Knoxville, TN (United States))
Partner: UNT Libraries Government Documents Department
open access

Analysis of capsule HFR-B1 graphite-corrosion data

Description: The recently completed irradiation of capsule HFR-B1 in the high-flux reactor at the Pitten Establishment in The Netherlands provided some excellent data for fission-product release. The data were obtained under irradiation and temperature conditions close to those expected during normal operation of the Modular High-Temperature Gas-cooled Reactor (MHTGR). Some of the tests at Petten were designed to measure release of fission gases during hydrolysis of failed fuel. Hydrolysis was initiated by … more
Date: January 1, 1991
Creator: Richards, M.B. & Gillespie, A.G.
Partner: UNT Libraries Government Documents Department
open access

Analysis of depressurized loss-of-forced cooling transients by HERA

Description: The Modular High-Temperature Gas-Cooled Reactor (MHTGR) is one of the next generation reactors, which has passive safety features. Among these safety features is the ability to withstand a depressurized, loss-of-forced cooling of the reactor without release of fission products from the primary containment. In order to assess the capability of the MHTGR to withstand this type of accident condition, the thermal behavior of the reactor core must be well understood. To accomplish this, we have empl… more
Date: January 1, 1991
Creator: Rider, W. J. & Cappiello, M. W.
Partner: UNT Libraries Government Documents Department
open access

The effect of volume on the tensile strength of several nuclear-grade graphites

Description: This report will present the results of a study on the effects of stress volume on the tensile strength of two nuclear-grade graphites. The materials selected were H-451, an extruded near-isotropic graphite manufactured by Great Lakes Carbon Corporation, and IG-110, a fine-grained isotropic molded graphite manufactured by Toyo Tanso Company, Ltd. The tensile properties of H-451 were examined extensively in the past in order to characterize the variability of strength within billets, between bil… more
Date: January 1, 1991
Creator: Strizak, J.P.
Partner: UNT Libraries Government Documents Department
open access

The effect of water vapor in the reactor cavity in a MHTGR (Modular High Temperature Gas Cooled Reactor) on the radiation heat transfer

Description: Analyses have been completed to determine the effect of the presence of water vapor in the reactor cavity in a modular high temperature gas cooled reactor on the predicted radiation heat transfer from the vessel wall to the reactor cavity cooling system. The analysis involves the radiation heat transfer between two parallel plates with an absorbing and emitting medium present. Because the absorption in the water vapor is spectrally dependent, the solution is difficult even for simple geometries… more
Date: January 1, 1991
Creator: Cappiello, M.W.
Partner: UNT Libraries Government Documents Department
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The effects of specimen geometry and size on the fracture toughness of nuclear graphites

Description: In a joint Oak Ridge National Laboratory (ORNL)/Japan Atomic Energy Research Institute (JAERI) study, various fracture toughness techniques were applied to Toyo Tanso grade IG-110 graphite to establish if specimen geometry influences on fracture toughness. The test geometries investigated were: compact tension (CT), disc compact tension (DCT), short rod (SR), chevron-notched short-red (CNSR), cylindrical bend specimen (BS), and centrally slotted disc (CSD). Specimen geometries which allow slow … more
Date: January 1, 1991
Creator: Romanoski, G.R. & Burchell, T.D.
Partner: UNT Libraries Government Documents Department
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A microstructurally based fracture model for nuclear graphite

Description: This paper reports the physical basis of, and assumptions behind, a fracture model for nuclear graphites. Microstructurally related inputs, such as filler particle size, filler particle fracture toughness (K{sub Ic}), density, pore size distribution, number of pores and specimen geometry (size and volume), are utilized in the model. The model has been applied to two graphites, Great Lakes Carbon Corporation grade H-451 and Toyo Tanso grade IG-110. For each graphite, the predicted tensile failur… more
Date: January 1, 1991
Creator: Burchell, T.D.
Partner: UNT Libraries Government Documents Department
open access

Nuclear Reactors and Technology; (USA)

Description: Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also … more
Date: January 1, 1991
Creator: Cason, D.L. & Hicks, S.C. (eds.)
Partner: UNT Libraries Government Documents Department
open access

Nuclear Safety. Technical Progress Journal, October--December 1991: Volume 32, No. 4

Description: This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear … more
Date: January 1, 1991
Partner: UNT Libraries Government Documents Department
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Rules for design of Alloy 617 nuclear components to very high temperatures

Description: Very-high-temperature gas-cooled reactors provide attractive options for electric power generation using a direct gas-turbine cycle and for process-heat applications. For the latter, temperatures of at least 950{degree}C (1742{degree}F) are desirable. As a first step to providing rules for the design of nuclear components operating at very high temperatures, a draft ASME Boiler and Pressure Vessel Code Case has been prepared by an ad hoc Code task force. The Case, which is patterned after the h… more
Date: January 1, 1991
Creator: Corum, J.M. & Blass, J.J.
Partner: UNT Libraries Government Documents Department
open access

Use of miniature and standard specimens to evaluate effects of irradiation temperature on pressure vessel steels

Description: The effects of neutron irradiation on the steel reactor vessel for the modular high-temperature gas-cooled reactor (MHTGR) are being investigated, primarily because the operating temperatures are low (121 to 210{degrees}C (250--410{degrees}F)) compared to those for commercial light-water reactors (LWRs) ({approximately}288{degrees}C (550{degrees}F)). The need for design data on the reference temperature shift necessitated the irradiation at different temperatures of A 533 grade B class 1 plate.… more
Date: January 1, 1991
Creator: Haggag, F.M.; Nanstad, R.K. (Oak Ridge National Lab., TN (United States)) & Byrne, S.T. (ABB/Combustion Engineering, Inc., Windsor, CT (United States))
Partner: UNT Libraries Government Documents Department
open access

Bounding core temperature transients for severe and rapid water ingress scenarios in modular high temperature gas-cooled reactors

Description: A rapid water ingress transient, resulting from steam generator tube or tube-sheet failures, could lead to a reactivity insertion and core heatup in the Modular High Temperature Gas-Cooled Reactors. This paper considers the effect of hypothetical rapid and severe water ingress scenarios of extremely low probability, and assesses the effect of such transients on potentially excessive fuel temperatures and subsequent fuel failures. The results indicate that for the worst postulated scenarios the … more
Date: January 1, 1990
Creator: Kroeger, P. G.
Partner: UNT Libraries Government Documents Department
open access

Development of a detailed core flow analysis code for prismatic fuel reactors

Description: The development of a computer code for the analysis of the detailed flow of helium in prismatic fuel reactors is reported. The code, called BYPASS, solves, a finite difference control volume formulation of the compressible, steady state fluid flow in highly cross-connected flow paths typical of the Modular High-Temperature Gas Cooled Reactor (MHTGR). The discretization of the flow in a core region typically considers the main coolant flow paths, the bypass gap flow paths, and the crossflow conn… more
Date: January 1, 1990
Creator: Bennett, R.G.
Partner: UNT Libraries Government Documents Department
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Diffusion modeling of fission product release during depressurized core conduction cooldown conditions

Description: A simple model for diffusion through the silicon carbide layer of TRISO particles is applied to the data for accident condition testing of fuel spheres for the High-Temperature Reactor program of the Federal Republic of Germany (FRG). Categorization of sphere release of {sup 137}Cs based on fast neutron fluence permits predictions of release with an accuracy comparable to that of the US/FRG accident condition fuel performance model. Calculations are also performed for {sup 85}Kr, {sup 90}Sr, an… more
Date: January 1, 1990
Creator: Martin, R. C.
Partner: UNT Libraries Government Documents Department
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