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in publisher: "General Atomic Company"

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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

The multipulse Thomson scattering diagnostic on the DIII-D tokamak

This paper describes the design and operation of a 40-spatial channel Thomson scattering system that uses multiple 20 Hz Nd:YAG lasers to measure the electron temperature and density profiles periodically throughout an entire plasma discharge. Interference filter polychromators disperse the scattered light which is detected by silicon avalanche photodiodes. The measurable temperature range from 10 eV to 20 keV and the minimum detectable density is about 2 {times} 10{sup 18} m{sup {minus}3}. Las… more

Date: September 1, 1991

Creator: Carlstrom, T. N.; Campbell, G. L.; DeBoo, J. C.; Evanko, R. G.; Evans, J.; Greenfield, C. M. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

850/sup 0/C VHTR plant technical description

This report describes the conceptual design of an 842-MW(t) process heat very high temperature reactor (VHTR) plant having a core outlet temperature of 850/sup 0/C (1562/sup 0/F). The reactor is a variation of the high-temperature gas-cooled reactor (HTGR) power plant concept. The report includes a description of the nuclear heat source (NHS) and of the balance of reactor plant (BORP) requirements. The design of the associated chemical process plant is not covered in this report. The reactor de… more

Date: June 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Non-linear instability of DIII-D to error fields

Otherwise stable DIII-D discharges can become nonlinearly unstable to locked modes and disrupt when subjected to resonant m = 2, n = 1 error field caused by irregular poloidal field coils, i.e. intrinsic field errors. Instability is observed in DIII-D when the magnitude of the radial component of the m = 2, n = 1 error field with respect to the toroidal field is B{sub r21}/B{sub T} of about 1.7 {times} 10{sup {minus}4}. The locked modes triggered by an external error field are aligned with the … more

Date: October 1, 1991

Creator: La Haye, R. J. & Scoville, J. T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Gas-cooled fast breeder reactor. Quarterly progress report, February 1-April 30, 1980

Information is presented concerning the reactor vessel; reactivity control mechanisms and instrumentation; reactor internals; primary coolant circuits;core auxiliary cooling system; reactor core; systems engineering; and reactor safety and reliability;

Date: May 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Progress report on the development of the General Atomic thermochemical water-splitting process

The major accomplishments of the DOE funded part of the GA thermochemical water-splitting program are reported. They include: completion of installation of all bench-scale equipment; operation and preliminary data acquisition for bench-scale subunits I and II; design, installation and operation of a system for iodine removal from the low phase; review and modification of Section III of the engineering flowsheet resulting in an increase in process efficiency and decrease in capital cost; and com… more

Date: August 1, 1980

Creator: Besenbruch, G.E.; Allen, C.L.; Brown, L.C.; McCorkle, K.; Rode, J.S.; Norman, J.H. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

HTGR safety philosophy

The accident at the Three Mile Island has focused public attention on reactor safety. Many public figures advocate a safer method of generating nuclear electricity for the second nuclear era in the US. The paper discusses the safety philosophy of a concept deemed suitable for this second nuclear era. The HTGR, in the course of its evolution, included safety as a significant determinant in design philosophy. This is particularly evident in the design features which provide inherent safety. Inher… more

Date: August 1, 1980

Creator: Joskimovic, V. & Fisher, C.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Analysis of fission product behavior in the Saclay Spitfire Loop Test SSL-1. [HTGR]

The behavior of the fission metal cesium and the fission gases krypton and xenon in the Saclay Spitfire Loop SSL-1 test has been compared to that predicted using General Atomic reference data and computer code models. This is the first in a series of analyses planned in order to provide quantitative validation of HTGR fission product design methods. In this analysis, the first attempt to rigorously verify fission product design methods, the FIPERQ code was used to model the diffusion of cesium … more

Date: February 1, 1978

Creator: Jensen, D. D.; Haire, M. J. & Ballagny, A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Design configuration of GCFR core assemblies

The current design configurations of the core assemblies for the gas-cooled fast reactor (GCFR) demonstration plant reactor core conceptual design are described. Primary emphasis is placed upon the design innovations that have been incorporated in the design of the core assemblies since the establishment of the initial design of an upflow GCFR core. A major feature of the design configurations is that they are prototypical of core assemblies for use in commercial plants; a larger number of the … more

Date: May 1, 1980

Creator: LaBar, M.P.; Lee, G.E. & Meyer, R.J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

HTGR-GT closed-cycle gas turbine: a plant concept with inherent cogeneration (power plus heat production) capability

The high-grade sensible heat rejection characteristic of the high-temperature gas-cooled reactor-gas turbine (HTGR-GT) plant is ideally suited to cogeneration. Cogeneration in this nuclear closed-cycle plant could include (1) bottoming Rankine cycle, (2) hot water or process steam production, (3) desalination, and (4) urban and industrial district heating. This paper discusses the HTGR-GT plant thermodynamic cycles, design features, and potential applications for the cogeneration operation mode… more

Date: April 1, 1980

Creator: McDonald, C. F.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Radiochemical analysis of the first plateout probe from the Fort St. Vrain high-temperature gas-cooled reactor

This report presents the analysis of radioactive elements on the first plateout probe from the Fort St. Vrain high-temperature gas-cooled reactor. The plateout probe is a device which samples the primary coolant for condensible fission products. Circuit inventories of individual radionuclides are estimated from the probe analysis. The analysis shows that the radioactive contamination in the primary circuit is remarkable low, with activation product concentrations much greater than that of fissi… more

Date: June 1, 1982

Creator: Burnette, R. D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

HTGR fuel recycle program. Quarterly progress report for the period ending November 30, 1977

The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel, the design and development of an integrated pilot line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials, and design work in support of Hot Engineering Tests (HET). Work is also described on trade-off studies concerning the required design of facilities and equipment for the large-scale recycle of HTGR fuels in order to … more

Date: December 1, 1977

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Negative ion-based neutral injection on DIII-D

High energy negative ion-based neutral beam injection is a strong candidate for heating and non-inductive current drive in tokamaks. Many of the questions related to the physics and engineering of this technique remain unanswered. In this paper, we consider the possibility of negative ion-based neutral beam injection on DIII-D. We establish the desired parameter space by examining physics trades. This is combined with potential design constraints and a survey of component technology options to … more

Date: January 1, 1990

Creator: Stewart, L. D.; Bhadra, D. K.; Colleraine, A. P. & Kim, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

GCFR core thermal-hydralic design

The approach for developing the thermal-hydraulic core assembly designs for the gas-cooled fast reactor (GCFR) is reviewed, and key considerations for improving the core performance at all power and flow conditions are discussed. It is shown how the thermal-hydraulic core assembly designs evolve from evaluations of plant size, material limitations, safety criteria, and structural performance considerations.

Date: May 1, 1980

Creator: Schleuter, G.; Baxi, C.B. & Bennett, F.O.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Probabilistic risk assessment of HTGRs

Probabilistic Risk Assessment methods have been applied to gas-cooled reactors for more than a decade and to HTGRs for more than six years in the programs sponsored by the US Department of Energy. Significant advancements to the development of PRA methodology in these programs are summarized as are the specific applications of the methods to HTGRs. Emphasis here is on PRA as a tool for evaluating HTGR design options. Current work and future directions are also discussed.

Date: August 1980

Creator: Fleming, K. N.; Houghton, W. J.; Hannaman, G. W. & Joksimovic, V.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

End of life fission product distributions in F-1 experiment fuel rods

Fission product migration and end-of-life distributions were examined in the F-1 (X094) series of sealed, mixed-oxide fuel rods irradiated in the fast flux of EBR-II. Cesium, rubidium, iodine, and strontium data obtained from axial gamma scanning, mass spectrometry, and radiochemical analyses are presented. The results show significant migration of cesium, probably as both a volatile species and as the noble gas precursor. Cesium metal species leaving the fuel region accumulate predominately at… more

Date: May 1, 1980

Creator: Goodin, D. T.; Langer, S. & Bell, W. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

US GCFR demonstration plant design

A general description of the US GCFR demonstration plant conceptual design is given to provide a context for more detailed papers to follow. The parameters selected for use in the design are presented and the basis for parameter selection is discussed. Nuclear steam supply system (NSSS) and balance of plant (BOP) component arrangements and systems are briefly discussed.

Date: May 1, 1980

Creator: Hunt, P. S. & Snyder, H. J.

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

Gas-cooled fast breeder reactor. Quarterly progress report, November 1, 1979 through January 31, 1980

Information is presented concerning the nuclear steam supply system; reactor core; systems engineering; safety and reliability; and circulator test facility.

Date: February 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Design and analysis of PCRV core cavity closure

Design requirements and considerations for a core cavity closure which led to the choice of a concrete closure with a toggle hold-down as the design for the Gas-Cooled Fast Breeder Reactor (GCFR) plant are discussed. A procedure for preliminary stress analysis of the closure by means of a three-dimensional finite element method is described. A limited parametric study using this procedure indicates the adequacy of the present closure design and the significance of radial compression developed a… more

Date: May 1, 1980

Creator: Lee, T.T.; Schwartz, A.A. & Koopman, D.C.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Licensing topical report: application of probabilistic risk assessment in the selection of design basis accidents. [HTGR]

A probabilistic risk assessment (PRA) approach is proposed to be used to scrutinize selection of accident sequences. A technique is described in this Licensing Topical Report to identify candidates for Design Basis Accidents (DBAs) utilizing the risk assessment results. As a part of this technique, it is proposed that events with frequencies below a specified limit would not be candidates. The use of the methodology described is supplementary to the traditional, deterministic approach and may r… more

Date: June 1, 1980

Creator: Houghton, W.J.

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

Review of fission product plateout investigations at General Atomic. [HTGR]

The status of fission product plateout studies at General Atomic is reviewed and suggestions are offered for future work. The deposition, or plateout, of condensible radionuclides in the primary circuits of gas-cooled reactors affects shielding requirements, maintenance procedures, and plant availability as well as representing a significant radiological source and/or sink for certain hypothetical accidents. Physical models and computer codes used to describe these plateout phenomena for reacto… more

Date: December 1, 1977

Creator: Hanson, D. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

A formula for efficiency of fast wave current drive in fusion devices

Fast wave current drive (FWCD) is a principal candidate for non- inductive current drive schemes in reactors. Major experiments are in progress or planned on DIII-D, JET, and Tore-Supra. A theory for FWCD was presented by two of the authors and collaborators. To minimize computations required in transport simulations, and for analytical understanding, it is very useful to have a concise analytical efficiency formula. Fisch and Karney, and Ehst and Karney have obtained empirical formulae that fi… more

Date: June 1, 1992

Creator: Chiu, S. C.; Harvey, R. W. (General Atomics, San Diego, CA (United States)); Karney, C. F. F. (Princeton Univ., NJ (United States). Plasma Physics Lab.) & Mau, T. K. (California Univ., Los Angeles, CA (United States). School of Engineering and Applied Science)

Item Type: Article

Partner: UNT Libraries Government Documents Department