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in subjects: "Turbomachinery 210300* -- Power Reactors, Nonbreeding, Graphite Moderated"

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Hot helium flow test facility summary report

This report summarizes the results of a study conducted to assess the feasibility and cost of modifying an existing circulator test facility (CTF) at General Atomic Company (GA). The CTF originally was built to test the Delmarva Power and Light Co. steam-driven circulator. This circulator, as modified, could provide a source of hot, pressurized helium for high-temperature gas-cooled reactor (HTGR) and gas-cooled fast breeder reactor (GCFR) component testing. To achieve this purpose, a high-temp… more

Date: June 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Heat exchanger design considerations for high temperature gas-cooled reactor (HTGR) plants

Various aspects of the high-temperature heat exchanger conceptual designs for the gas turbine (HTGR-GT) and process heat (HTGR-PH) plants are discussed. Topics include technology background, heat exchanger types, surface geometry, thermal sizing, performance, material selection, mechanical design, fabrication, and the systems-related impact of installation and integration of the units in the prestressed concrete reactor vessel. The impact of future technology developments, such as the utilizati… more

Date: February 1980

Creator: McDonald, C. F.; Vrable, D. L.; Van Hagan, T. H.; King, J. H. & Spring, A. H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

HTGR gas-turbine program. Semiannual progress report for period ending March 31, 1980

This report describes the conceptual design and analysis performed by General Atomic Company and its subcontractors for the US Department of Energy on the direct cycle gas turbine high-temperature gas-cooled reactor. The primary accomplishments for this period were cost reduction studies, turbomachinery failure analysis, and alternate plant concept evaluation.

Date: January 1, 1982

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Nuclear closed-cycle gas turbine (HTGR-GT): dry cooled commercial power plant studies

Combining the modern and proven power conversion system of the closed-cycle gas turbine (CCGT) with an advanced high-temperature gas-cooled reactor (HTGR) results in a power plant well suited to projected utility needs into the 21st century. The gas turbine HTGR (HTGR-GT) power plant benefits are consistent with national energy goals, and the high power conversion efficiency potential satisfies increasingly important resource conservation demands. Established technology bases for the HTGR-GT ar… more

Date: November 1, 1979

Creator: McDonald, C. F. & Boland, C. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

3000 MW(t) HTGR - gas turbine non-intercoolel. Technical evaluation report

This report summarizes all the technical work performed on the 3000-MW(t) 3-loop High-Temperature Gas-Cooled Reactor Gas Turbine design as of June 1979. Although the plant configuration has changed to a 2000-MW(t) 2-loop plant, most of the technical assessments described in this report are still applicable to the 2000-MW(t) plant. The report covers the criteria under which the plant was designed, the technical feasibility problems associated with the plant and their potential solutions, and oth… more

Date: December 1, 1979

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Turbomachinery design considerations for the nuclear HTGR-GT power plant

For several years, design studies have been under way in the USA on a nuclear closed-cycle gas turbine plant (HTGR-GT). Design aspects of the helium turbomachine portion of these studies are presented. Gas dynamic and mechanical design considerations are presented for helium turbomachines in the 400-MW(e) (non-intercooled) and 600-MW(e) (intercooled) power range. Design of the turbomachine is a key element in the overall power plant program effort, which is currently directed toward the selecti… more

Date: November 1, 1979

Creator: McDonald, C. F. & Smith, M. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Thermal and flow design of helium-cooled reactors

This book continues the American Nuclear Society's series of monographs on nuclear science and technology. Chapters of the book include information on the first-generation gas-cooled reactors; HTGR reactor developments; reactor core heat transfer; mechanical problems related to the primary coolant circuit; HTGR design bases; core thermal design; gas turbines; process heat HTGR reactors; GCFR reactor thermal hydraulics; and gas cooling of fusion reactors.

Date: January 1, 1984

Creator: Melese, G. & Katz, R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

HTGR market assessment: interim report

The purpose of this Assessment is to establish the utility perspective on the market potential of the HTGR. The majority of issues and conclusions in this report are applicable to both the HTGR-Gas Turbine (GT) and the HTGR-Steam Cycle (SC). This phase of the HTGR Market Assessment used the HTGR-GT as the reference design as it is the present focus of the US HTGR Program. A brief system description of the HTGR-GT is included in Appendix A. This initial report provides the proposed structure for… more

Date: September 1, 1979

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

High temperature gas-cooled reactor: gas turbine application study

The high-temperature capability of the High-Temperature Gas-Cooled Reactor (HTGR) is a distinguishing characteristic which has long been recognized as significant both within the US and within foreign nuclear energy programs. This high-temperature capability of the HTGR concept leads to increased efficiency in conventional applications and, in addition, makes possible a number of unique applications in both electrical generation and industrial process heat. In particular, coupling the HTGR nucl… more

Date: December 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, October 1, 1978--December 31, 1978

Results of work performed from October 1, 1978 through December 31, 1978 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program is presented. Objectives are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposure… more

Date: March 9, 1979

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

HTGR generic technology program plan (FY 80)

Purpose of the program is to develop base technology and to perform design and development common to the HTGR Steam Cycle, Gas Turbine, and Process Heat Plants. The generic technology program breaks into the base technology, generic component, pebble-bed study, technology transfer, and fresh fuel programs. (DLC)

Date: January 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

HTGR gas turbine program. Semiannual progress report, April 1-September 30, 1978

This report describes work performed under the gas turbine HTGR (HTGR-GT) program, Department of Energy Contract DE-AT03-76-SF70046, during the period April 1, 1978 through September 30, 1978. The work reported covers the demonstration and commercial plant concept studies including plant layout, heat exchanger studies, turbomachine studies, systems analysis, and reactor core engineering.

Date: December 1, 1979

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

800-MWe HTGR-gas-turbine two-loop electric plant

The design and development of the electric plant for the HTGR-Gas Turbine (GT) present a radical departure in accommodating the electrical requirements of the nuclear heat system and the balance of plant. To address not only these requirements but also codes and standards (for power plants and safety-grade systems), the evolution of the design dictates the application of innovative and unique solutions. The complexity of the GT plant and the criteria for nuclear power stations are substantial r… more

Date: June 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program: Topical report I, selection of candidate alloys. Volume 3. Selection of surface coating/substrate systems for screening creep and structural stability studies

Considering the high temperature, low O/sub 2/, high C environment of operation in the Very High Temperature Reactor (VHTR) Systems, the utilization of coatings is envisaged to hold potential for extending component lifetimes through the formation of stable and continuous oxide films with enhanced resistance to C diffusion. A survey of the current state of technology for high temperature coatings has been performed. The usefulness of these coatings on the Mo, Ni, and Fe base alloys is discussed… more

Date: June 20, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Response of a thermal barrier system to acoustic excitation in a gas turbine nuclear reactor

A gas turbine located within a High-Temperature Gas-Cooled Reactor (HTGR) induces high acoustic sound pressure levels into the primary coolant (helium). This acoustic loading induces high cycle fatigue stresses which may control the design of the thermal barrier system. This study examines the dynamic response of a thermal barrier configuration consisting of a fibrous insulation compressed against the reactor vessel by a coverplate which is held in position by a central attachment fixture. The … more

Date: November 1, 1980

Creator: Betts, W.S. Jr. & Blevins, R.D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Dynamic computer simulation of the Fort St. Vrain steam turbines

A computer simulation is described for the dynamic response of the Fort St. Vrain nuclear reactor regenerative intermediate- and low-pressure steam turbines. The fundamental computer-modeling assumptions for the turbines and feedwater heaters are developed. A turbine heat balance specifying steam and feedwater conditions at a given generator load and the volumes of the feedwater heaters are all that are necessary as descriptive input parameters. Actual plant data for a generator load reduction … more

Date: January 1, 1983

Creator: Conklin, J. C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, September 23, 1976--December 31, 1976

This report presents the results of work performed from September 23, 1976 through December 31, 1976 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Process Heat and Direct Cycle Helium Turbine (DCHT) applications, in terms of the affect of simulated reactor primary coolant (impure Helium), high temperatures, and long time exposures, on the mechanical… more

Date: January 1, 1977

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Gas Turbine HTGR program. Quarterly progress report for the period ending December 31, 1977

The report covers the demonstration plant design studies, core and fission product studies, shielding studies, heat exchanger design, and maintenance studies, including inservice inspection (ISI).

Date: April 1, 1978

Item Type: Report

Partner: UNT Libraries Government Documents Department