Scoping systems analysis of a 350 MWt modular liquid metal cooled reactor

PDF Version Also Available for Download.

Description

The systems analysis code SASSYS was used to explore the sensitivity of the system response to various inherent reactivity feedback mechanisms and design features for a small, liquid-metal-cooled reactor during the first 1000 s following the initiation of an unprotected loss-of-flow and/or loss-of-primary-heat-removal transient. The results show that to maximize the inherent safety of small, liquid-metal-cooled reactors, inherent feedback mechanisms should be accounted for in establishing design features such as the flow coastdown time constant and the control rod suspension system. The results also indicate insensitivity of the system response to the operation or non-operation of heat removal systems during … continued below

Physical Description

7 pages

Creation Information

Morris, E. E.; Rhow, S. K. & Switick, D. M. January 1, 1985.

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 27 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.

Publishers

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.

Contact Us

What

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

Description

The systems analysis code SASSYS was used to explore the sensitivity of the system response to various inherent reactivity feedback mechanisms and design features for a small, liquid-metal-cooled reactor during the first 1000 s following the initiation of an unprotected loss-of-flow and/or loss-of-primary-heat-removal transient. The results show that to maximize the inherent safety of small, liquid-metal-cooled reactors, inherent feedback mechanisms should be accounted for in establishing design features such as the flow coastdown time constant and the control rod suspension system. The results also indicate insensitivity of the system response to the operation or non-operation of heat removal systems during the early part of an unprotected loss-of-flow transient.

Physical Description

7 pages

Notes

NTIS, PC A02/MF A01.

Source

  • ANS/ENS fast reactor safety meeting, Knoxville, TN, USA, 21 Apr 1985

Language

Item Type

Identifier

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

  • Other: DE85012117
  • Report No.: CONF-850410-45
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 5341915
  • Archival Resource Key: ark:/67531/metadc1071083

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.

What responsibilities do I have when using this article?

When

Dates and time periods associated with this article.

Creation Date

  • January 1, 1985

Added to The UNT Digital Library

  • Feb. 4, 2018, 10:51 a.m.

Description Last Updated

  • April 23, 2020, 2:27 a.m.

Usage Statistics

When was this article last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 27

Interact With This Article

Here are some suggestions for what to do next.

Start Reading

PDF Version Also Available for Download.

International Image Interoperability Framework

IIF Logo

We support the IIIF Presentation API

Morris, E. E.; Rhow, S. K. & Switick, D. M. Scoping systems analysis of a 350 MWt modular liquid metal cooled reactor, article, January 1, 1985; Illinois. (https://digital.library.unt.edu/ark:/67531/metadc1071083/: 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