HAZARDS SUMMARY REPORT FOR THE VMR CRITICAL-ASSEMBLY EXPERIMENTS

PDF Version Also Available for Download.

Description

Moderator Reactor (VMR), a reactor concept under investigation by American-Standard for the AEC. The VMR is light-water moderated and cooled and is fueled with slightly enriched uranium dioxide pellets loaded into aluminum tubes. The core consists of 37 hexagonal fuel cans each loaded with 61 fuel pins. The cooling water, which flows upward around the pins inside the fuel can, boils in passing through the core. Reactor control in the prototype will be achieved by varying the moderator height. The site, laboratory, and the critical assembly, including control and safety mechanisms, are described in detuil. Special characteristics of the assembly ... continued below

Physical Description

Pages: 78

Creation Information

Egen, R.A.; Hogan, W.S.; Dingee, D.A. & Chastain, J.W. June 10, 1960.

Context

This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 12 times . More information about this report can be viewed below.

Who

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

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.

Contact Us

What

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

Description

Moderator Reactor (VMR), a reactor concept under investigation by American-Standard for the AEC. The VMR is light-water moderated and cooled and is fueled with slightly enriched uranium dioxide pellets loaded into aluminum tubes. The core consists of 37 hexagonal fuel cans each loaded with 61 fuel pins. The cooling water, which flows upward around the pins inside the fuel can, boils in passing through the core. Reactor control in the prototype will be achieved by varying the moderator height. The site, laboratory, and the critical assembly, including control and safety mechanisms, are described in detuil. Special characteristics of the assembly pentinent to safety were calculated. The nuclesr energy released and the average and maximum fuel temperatures resulting from step reactivity increases up to 2% DELTA k/k are presented graphically for two cases. In the first case, fuel-temperature effects are considered to be the oniy shutdown mechanism; in the second radiolytic gas is considered to contribute to shutdown, in addition to fuel-temperature effects. The accident considered to be the maximum credible accident causes a step addition in reactivity of 1.5% DELTA k/k. The nuclear-energy release is between 160 and 310 megawatt-sec depending on the assumed shutdown mechanisms. This accident does not cause any fuel to be vapcrized (and probably none to be melted) and, hence, there does not appear to be a hazard from fission-product activity. It appears that this criticalassembly program can be conducted with reasonable assurance of safe operation and that no public persons will be jeopardized by its operation. (auth)

Physical Description

Pages: 78

Notes

NTIS

Source

  • Other Information: Orig. Receipt Date: 31-DEC-60

Language

Item Type

Identifier

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

  • Report No.: BMI-1445
  • Grant Number: W-7405-ENG-92
  • DOI: 10.2172/4143836 | External Link
  • Office of Scientific & Technical Information Report Number: 4143836
  • Archival Resource Key: ark:/67531/metadc871222

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.

What responsibilities do I have when using this report?

When

Dates and time periods associated with this report.

Creation Date

  • June 10, 1960

Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

Description Last Updated

  • Nov. 18, 2016, 7:20 p.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 12

Interact With This Report

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

Egen, R.A.; Hogan, W.S.; Dingee, D.A. & Chastain, J.W. HAZARDS SUMMARY REPORT FOR THE VMR CRITICAL-ASSEMBLY EXPERIMENTS, report, June 10, 1960; Columbus, Ohio. (digital.library.unt.edu/ark:/67531/metadc871222/: accessed September 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.