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A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor

Description: From abstract: A conceptual design study has been performed for a sodium cooled, graphite moderated, thermal power-breeder reactor utilizing the Thorium-Uranium 233 breeding cycle. Several aspects of the design of the system are considered but no attempt has been made to supply all the details. It appears that the design presented is feasible and will allow the production of economic power as well as full utilization of thorium resources.
Date: February 1, 1954
Creator: Henrie, J. O. & Weisner, E. F.
Partner: UNT Libraries Government Documents Department

Comparison of Two Sodium-Cooled, 1000 MegaWatt Fast Reactor Concepts: Task 1 Report of 1000 MegaWatt Liquid Metal Fast Breeder Reactor Follow-On Work

Description: From introduction: "The development of one or more nuclear steam supply system concepts, with certain trade-off studies to aid in the definition of these concepts. The selection of a reference concept for further study."
Date: June 1968
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department

Methods, System Optimization, and Safety Studies for a 1000 MegaWatt Sodium-Cooled Fast Reactor: Task 3 and 5 report of 1000 MegaWatt Liquid Metal Fast Breeder Reactor Follow-On Work

Description: From introduction: "Evaluation of trade-off and optimization studies in which numerous design parameters and economic ground-rules are varied to determine the effect on the economics of the reference concept. Selected safety studies."
Date: February 1969
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department

An Evaluation of Mercury Cooled Breeder Reactors

Description: Abstract: The technical feasibility and economic potential of fast breeder power reactor systems cooled with boiling mercury have been investigated by American-Standard under the United States Atomic Energy Commission's New Reactor Concepts Evaluation Program.
Date: October 13, 1959
Creator: Advanced Technology Laboratories
Partner: UNT Libraries Government Documents Department

U-233 Power-Breeder Reactor: Reactor Design and Feasibility Problem

Description: Report containing information regarding several designs of breeder reactors that utilizes the circulation of solid particles consisting of a fuel-moderator mixture, from the core to a separate heat exchanger vessel from which the solids flow freely to and through the core by gravity" (p. 13). Appendix begins on page 117.
Date: January 1954
Creator: Halik, R. R.; Beckberger, L. H.; Haibeck, J. M.; Mealia, J. E.; Northrop, W. A.; Rees, D. R. et al.
Partner: UNT Libraries Government Documents Department

Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor

Description: Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.
Date: December 9, 1963
Creator: Aase, D. T.; Fox, J. C.; Hennig, R. J.; Peterson, R. E.; Stewart, S. L. & Toyoda, K. G.
Partner: UNT Libraries Government Documents Department

Investigation of Reactivity Anomalies in EBR-II

Description: A data-collection and advisory team was formed to investigate observations of power reactivity decrement (PRD) and reactivity loss rate (RLR) obtained during EBR-II reactor run 74, because both the PRD and RLR were judged to be high during that run. This report describes the efforts to develop a realistic model explaining the reactivity observations for run 74 and presents recommendations for additional diagnostic information in the event of a recurrence of off-normal behavior of reactivity.
Date: June 1976
Creator: Walters, L. C.; Cutforth, D. S.; Forehand, H. M.; Hudman, G. D.; Larson, H. A.; MacFarlane, H. F. et al.
Partner: UNT Libraries Government Documents Department

1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1

Description: From introduction: "The objective of this study is to provide information that will assist the Atomic Energy Commission in furthering the National Liquid Metal Fast Breeder Reactor (LMFBR) Program. We plan to accomplish this end, in part, by extending the original studies to include system and component design and parametric evaluations of the nuclear steam supply system and its related systems and subsystems based on a n estimation of the state of technology in 1980."
Date: June 1967
Creator: Goulding, B. J.
Partner: UNT Libraries Government Documents Department

1000-MWe LMFBR Follow-On Study, Task I Report: Volume 3, Concept IV System Description

Description: From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept II description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On-Study Program."
Date: June 1967
Creator: Goulding, B. J.
Partner: UNT Libraries Government Documents Department

1000-MWe LMFBR Follow-On Study, Task I Report: Volume 2, Concept I System Description

Description: From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept I description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On Study Program."
Date: April 1967
Creator: Boyer, R. L.
Partner: UNT Libraries Government Documents Department

Investigations of Materials Compatibility Relevant to the EBR-2 System : FY 1978

Description: This report is the ninth in a series of yearly reports on investigations of components of the EBR-II reactor plant and out-of-reactor experiments in which materials or techniques are tested before being used in the EBR-II reactor systems. Wide ranges of materials, circumstances, and evaluation techniques are involved. Therefore, each investigation is reported separately.
Date: January 1979
Creator: Longua, K. J.; Shields, J. A.; Ruther, W. E. & Olson, W. H.
Partner: UNT Libraries Government Documents Department

EBR-2 Fisson-Product-Source Test No. 1

Description: A fission-product source (FPS) was irradiated in EBR-II to provide data for calibrating the facility's fuel-element rupture detector (FERD), which is a delayed-neutron monitor, and germanium-lithium argon-scanning system (GLASS), a fission-gas-activity monitor. A metal alloy source, Ni-3.2 wt.% uranium, provided quantitative recoil release of the fission-product nuclides. The source alloy, in tubular form, was irradiated as core-region segments of 18 capsules in the FPS subassembly. The irradiation showed that the response of the FERD was linear with increasing reactor power. The magnitude of the FERD signal was dependent on local fission rate for the FPS and the flow path of the sodium carrying the delayed-neutron emitters. The relatively high fission-gas activity released by the FPS allowed accurate calibration of the GLASS under several modes of operation and provided data for verifying a gas-release model for the reactor.
Date: August 1978
Creator: Strain, R. V.; Fogle, G. L.; Thresh, H. R.; Heinrich, R. R.; Freyer, R. M.; So, B. Y. C. et al.
Partner: UNT Libraries Government Documents Department