Core Parameter Study for a 300-Mw Sodium Graphite Reactor

Thumbnail image of item number 1 in: 'Core Parameter Study for a 300-Mw Sodium Graphite Reactor'.
Thumbnail image of item number 2 in: 'Core Parameter Study for a 300-Mw Sodium Graphite Reactor'.
Thumbnail image of item number 3 in: 'Core Parameter Study for a 300-Mw Sodium Graphite Reactor'.
Thumbnail image of item number 4 in: 'Core Parameter Study for a 300-Mw Sodium Graphite Reactor'.
Showing 1-4 of 69 pages in this report.

PDF Version Also Available for Download.

Description

A core parameter study of the operating costs was performed for a 300- Mwe sodium graphite reactor, a scale-up of the Hallam Power Reactor. The results of the study indicate that the core design is nsar optimum and that core modifications would reduce the power costs by less than 5%. The lattice spacing, fuel rod diameter, and sodium flow can be varied within a rather broad range without significant changes in power generation costs. The effect of the fuel cladning thickness is more significant; fuel cycle costs can be reduced if stainless steel canning is replaced with zirconium canning. Use … continued below

Physical Description

70 pages

Creation Information

Corcoran, W.P. October 22, 1959.

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.

Author

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

A core parameter study of the operating costs was performed for a 300- Mwe sodium graphite reactor, a scale-up of the Hallam Power Reactor. The results of the study indicate that the core design is nsar optimum and that core modifications would reduce the power costs by less than 5%. The lattice spacing, fuel rod diameter, and sodium flow can be varied within a rather broad range without significant changes in power generation costs. The effect of the fuel cladning thickness is more significant; fuel cycle costs can be reduced if stainless steel canning is replaced with zirconium canning. Use of UC in place of uraniummolybdenum fuel would also permit cost reductions. (D.L.C.)

Physical Description

70 pages

Source

  • Other Information: Orig. Receipt Date: 31-DEC-61

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

  • October 22, 1959

Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

Description Last Updated

  • March 4, 2021, 1:15 a.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 9
More Statistics

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

Thumbnail image of item number 1 in: 'Core Parameter Study for a 300-Mw Sodium Graphite Reactor'.
Thumbnail image of item number 2 in: 'Core Parameter Study for a 300-Mw Sodium Graphite Reactor'.
Thumbnail image of item number 3 in: 'Core Parameter Study for a 300-Mw Sodium Graphite Reactor'.
Thumbnail image of item number 4 in: 'Core Parameter Study for a 300-Mw Sodium Graphite Reactor'.

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

Corcoran, W.P. Core Parameter Study for a 300-Mw Sodium Graphite Reactor, report, October 22, 1959; Canoga Park, California. (https://digital.library.unt.edu/ark:/67531/metadc864868/: accessed October 3, 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