Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness

Thumbnail image of item number 1 in: 'Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness'.
Thumbnail image of item number 2 in: 'Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness'.
Thumbnail image of item number 3 in: 'Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness'.
Thumbnail image of item number 4 in: 'Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness'.
Showing 1-4 of 11 pages in this article.

PDF Version Also Available for Download.

Description

A blanket/shield assembly for a fusion reactor has been designed through extensive optimization studies. The design was optimized under the following constraints: (a) minimum overall thickness, (b) tritium breeding ratio of 1.10, (c) thermal energy recovery of 90%, (d) acceptably flat temperature distribution, and (e) excluding all ''exotic'' or problematic materials. The optimized blanket/shield has an overall thickness of 36 cm and conforms with all the above requirements. All tritium breeding is accomplished in a 24-cm-thick breeding zone using stagnant enriched lithium-6, and lead as a neutron multiplier. The energy recovery in this breeding zone is 71% which, together with … continued below

Physical Description

11 pages

Creation Information

Gerstl, S.A.W. January 1, 1978.

Context

This article 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. It has been viewed 41 times. More information about this article can be viewed below.

Who

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

Author

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 article. Follow the links below to find similar items on the Digital Library.

Description

A blanket/shield assembly for a fusion reactor has been designed through extensive optimization studies. The design was optimized under the following constraints: (a) minimum overall thickness, (b) tritium breeding ratio of 1.10, (c) thermal energy recovery of 90%, (d) acceptably flat temperature distribution, and (e) excluding all ''exotic'' or problematic materials. The optimized blanket/shield has an overall thickness of 36 cm and conforms with all the above requirements. All tritium breeding is accomplished in a 24-cm-thick breeding zone using stagnant enriched lithium-6, and lead as a neutron multiplier. The energy recovery in this breeding zone is 71% which, together with an additional energy extraction of 19% in a 12-cm-thick laminated stainless steel/boron carbide shield zone, results in the desired overall thermal efficiency of 0.90 which is considered adequate if normal-conducting magnets are used for plasma confinement.

Physical Description

11 pages

Notes

Dep. NTIS, PC A02/MF A01.

Source

  • 3. meeting on the technology of controlled thermonuclear fusion, Santa Fe, NM, USA, 9 May 1978

Language

Item Type

Identifier

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

  • Report No.: LA-UR-78-1198
  • Report No.: CONF-780508-3
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 7080183
  • Archival Resource Key: ark:/67531/metadc1192655

Collections

This article 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 article?

Digital Files

When

Dates and time periods associated with this article.

Creation Date

  • January 1, 1978

Added to The UNT Digital Library

  • July 2, 2018, 10:52 p.m.

Description Last Updated

  • June 21, 2019, 12:07 p.m.

Usage Statistics

When was this article last used?

Yesterday: 0
Past 30 days: 1
Total Uses: 41
More Statistics

Interact With This Article

Here are some suggestions for what to do next.

Start Reading

Thumbnail image of item number 1 in: 'Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness'.
Thumbnail image of item number 2 in: 'Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness'.
Thumbnail image of item number 3 in: 'Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness'.
Thumbnail image of item number 4 in: 'Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness'.

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

Gerstl, S.A.W. Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness, article, January 1, 1978; New Mexico. (https://digital.library.unt.edu/ark:/67531/metadc1192655/: accessed July 16, 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