Status of Prestressed Concrete Reactor Vessel (PCRV) experimental and analytical programs in the United States. [HTGR] Page: 4 of 33
This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided to UNT Digital Library by the UNT Libraries Government Documents Department.
Extracted Text
The following text was automatically extracted from the image on this page using optical character recognition software:
4
PCRV model tests have been conducted to demonstrate capability to predict
structural behavior using analysis methods in conjunction with small specimen
materials test data, to demonstrate adequacy of particular configurations or
designs and to demonstrate specific structural features. In the case of the
latter, we are testing a series of relatively simple beam structures to demon-
strate advantages of grouted prestressing systems. Examples of the other types
of our more recent structural model tests are described in the following sections.
4. MODEL STUDIES
4.1 Thermal Cylinder Model
The ORNL thermal cylinder model was a 1/6-scale representation of a portion
of the barrel section of a single cavity PCRV as shown in Fig. 3. Tl.e ring sec-
tion was posttensioned circumferentially and vertically, and subjected to tem-
peratures of 338.7 K on the inside and 295.4 K on the outside.
The top and bottom of the model were insulated and the vertical prestress
designed to simulate the presence of the complete vessel. The model was instru-
mented extensively using the various types of concrete embedment instrumentation
shown in Fig. 4. In addition to various types of embedment strain gages a series
of disk-shaped experimental stress cells some of which are shown in the figure
were included in the model. The completed structure is shown in Fig. 5. It was
subjected to an internal pressure of 483 MPa using a pressurization annulus that
was attached to the inside surface of the concrete ring.
The chronology of the various loading conditions to which the model was
subjected is indicated at the top of Fig. 6. These loadings represent what is
to be expected during the operating lifetime of a PCRV. The figure also shows
a comparison of typical experimental and calculated results, the latter of which
was obtained using the SAFE-CRACK finite element computer code. These results
Upcoming Pages
Here’s what’s next.
Search Inside
This article can be searched. Note: Results may vary based on the legibility of text within the document.
Tools / Downloads
Get a copy of this page or view the extracted text.
Citing and Sharing
Basic information for referencing this web page. We also provide extended guidance on usage rights, references, copying or embedding.
Reference the current page of this Article.
Callahan, J P & Dodge, W G. Status of Prestressed Concrete Reactor Vessel (PCRV) experimental and analytical programs in the United States. [HTGR], article, January 1, 1977; Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc1074659/m1/4/: accessed April 24, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.