skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Shield dome end plenum spacing

Authors:
Publication Date:
Research Org.:
Westinghouse Electric Corp., Pittsburgh, Pa. (USA). Astronuclear Lab.
OSTI Identifier:
4214060
Report Number(s):
WANL-TMI-519
NSA Number:
NSA-32-002571
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-75
Country of Publication:
United States
Language:
English
Subject:
N77800* -Reactors-Space, Mobile, Propulsion, Transportation & Package Reactors; *NERVA REACTOR- SHIELDING; *SHIELDING- RADIATION HEATING; NESDPS Office of Nuclear Energy Space and Defense Power Systems

Citation Formats

Rieke, K.L. Shield dome end plenum spacing. United States: N. p., 1962. Web. doi:10.2172/4214060.
Copy to clipboard
Rieke, K.L. Shield dome end plenum spacing. United States. doi:10.2172/4214060.
Copy to clipboard
Rieke, K.L. Tue . "Shield dome end plenum spacing". United States. doi:10.2172/4214060. https://www.osti.gov/servlets/purl/4214060.
Copy to clipboard
@article{osti_4214060,
title = {Shield dome end plenum spacing},
author = {Rieke, K.L.},
abstractNote = {},
doi = {10.2172/4214060},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Sep 25 00:00:00 EDT 1962},
month = {Tue Sep 25 00:00:00 EDT 1962}
}
Copy to clipboard
Technical Report:
View Technical Report (0.05 MB)
DOI:  10.2172/4214060
Save / Share:
Export Metadata
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.

  • ; ;
    This report describes the integral flux, energy spectra, and dose rate measurements made for the Exit Shield Experiment at the Oak Ridge National Laboratory Tower Shielding Facility as part of the Gas Cooled Fast Breeder Reactor program. The source was the same mockup of fuel pins used in the previous Grid Plate Shield Experiment. Two mockups of the upper axial shield were studied: one with seven subassemblies prototypic of that portion of the Exit Shield without a control rod, and another that was representative of the shield region with a control rod. The experiment was performed to provide verification of:more » the shield design methods, the shield effectiveness of a prototypic mockup, the analytical ability to calculate streaming effects in the presence of a control rod, and the source term bias factors for the upper plenum.« less

  • ; ;
    This report presents measurements of neutron fluxes made in the Shield Heterogeneity Study of at the Tower Shielding Facility (TSF) for the Gas Cooled Breeder Reactor (GCFR) shielding program. The study consisted of mockups of selective neutron streaming paths in the outer radial shield surrounding the 300 MW(e) reactor. The experimental configurations included four basic segments: a straight planar slit through a graphite slab; a straight planar slit through an iron spacer between graphite walls; straight planar slits through the iron spacer and between the iron and graphite; an offset slit through graphite.

  • ;
    The cooling tube spacing for cooling the biological shield in the Piqua Power Reactor was investigated. (W.L.H.)

  • ;