Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954

Thumbnail image of item number 1 in: 'Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954'.
Thumbnail image of item number 2 in: 'Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954'.
Thumbnail image of item number 3 in: 'Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954'.
Thumbnail image of item number 4 in: 'Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954'.
Showing 1-4 of 102 pages in this report.

PDF Version Also Available for Download.

Description

Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the application of steadystate plutonium feedback techniques to the use of diffusion plant tails for reactor fuel feed material. The performance and design of a twin core SGR power plant are given. Thermal neutron flux distribution measurements are reported for a six-rod fuel cluster and for a hollow uranium rod. A power cost calculation was made for a 1000-Mw SGR Th-U/sup 233/ breeder reactor which starts up on Th--U/sup 235/ alloy. Calculations were made on neutron leakage through the SRE shield. Research on reactor fuel elements and reactor … continued below

Physical Description

101 pages

Creation Information

Siegel, S. & Inman, G.M. eds. December 1, 1954.

Context

This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. More information about this report can be viewed below.

Who

People and organizations associated with either the creation of this report or its content.

Authors

Sponsor

Publisher

Provided By

UNT Libraries Government Documents Department

Serving as both a federal and a state depository library, the UNT Libraries Government Documents Department maintains millions of items in a variety of formats. The department is a member of the FDLP Content Partnerships Program and an Affiliated Archive of the National Archives.

About | Browse this Partner

Contact Us

Corrections Questions

What

Descriptive information to help identify this report. Follow the links below to find similar items on the Digital Library.

Description

Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the application of steadystate plutonium feedback techniques to the use of diffusion plant tails for reactor fuel feed material. The performance and design of a twin core SGR power plant are given. Thermal neutron flux distribution measurements are reported for a six-rod fuel cluster and for a hollow uranium rod. A power cost calculation was made for a 1000-Mw SGR Th-U/sup 233/ breeder reactor which starts up on Th--U/sup 235/ alloy. Calculations were made on neutron leakage through the SRE shield. Research on reactor fuel elements and reactor materials are described. Corrosion and irradiation damage data at 5 x 10/sup 7/ r dose (150 deg F) on toluene as the SRE shield coolant indicate that the radioinduced corrosion of Fe, Al, and Cu in the SRE shield should be negligible. Preliminary results are summarized for l-Mev electron ir radiation studies of terphenyls at 400 to 450 deg C. Sodium Reactor Experiment. Progress is reported for various portions of the SRE project: reactor design and evaluation, fuel elements, moderator, reflector, structure, reactor cooling and heat transfer, instrumentation and control, shielding, and reactor services. (D.L.C.)

Physical Description

101 pages

Source

  • Other Information: Orig. Receipt Date: 31-DEC-62

Language

Item Type

Identifier

Unique identifying numbers for this report in the Digital Library or other systems.

Collections

This report is part of the following collection of related materials.

Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

About | Browse this Collection

What responsibilities do I have when using this report?

Digital Files

When

Dates and time periods associated with this report.

Creation Date

  • December 1, 1954

Added to The UNT Digital Library

  • Jan. 22, 2018, 7:23 a.m.

Description Last Updated

  • March 15, 2021, 9 p.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 4
More Statistics

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

Thumbnail image of item number 1 in: 'Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954'.
Thumbnail image of item number 2 in: 'Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954'.
Thumbnail image of item number 3 in: 'Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954'.
Thumbnail image of item number 4 in: 'Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954'.

PDF Version Also Available for Download.

Citations, Rights, Re-Use

International Image Interoperability Framework

IIF Logo

We support the IIIF Presentation API

Links for Robots

Helpful links in machine-readable formats.

Archival Resource Key (ARK)

International Image Interoperability Framework (IIIF)

Metadata Formats

Images

URLs

Stats

Siegel, S. & Inman, G.M. eds. Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954, report, December 1, 1954; United States. (https://digital.library.unt.edu/ark:/67531/metadc1062014/: accessed June 11, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

Back to Top of Screen