Pressurized Water Reactor Program Technical Progress Report for the Period September 9 to October 20, 1955

PDF Version Also Available for Download.

Description

Progress in the design, development, and construction of PWR power plant systems and components and PWR core and auxiliaries is summarized. The blanket assembly design is described and illustrated. Results of MTR evaluation of fuel element failure instrumentation are reported. Development of fabrication and testing tochaiques for clad fuel elements, fuel rods, plates, and assemblies is described. Investigations of fuel and cladding alloys include crystal structure and thermal stability determinations on U--Mo alloys, studies on the nature of the hydride phase formed during corrosion of gamma -phase alloys in high- temperature water, and specific heat, resistivity, and phase diagram studies ... continued below

Physical Description

Medium: P; Size: Pages: 95

Creation Information

Creator: Unknown. October 31, 1958.

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. More information about this report can be viewed below.

Who

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

Creator

  • We've been unable to identify the creator(s) of this report.

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

Progress in the design, development, and construction of PWR power plant systems and components and PWR core and auxiliaries is summarized. The blanket assembly design is described and illustrated. Results of MTR evaluation of fuel element failure instrumentation are reported. Development of fabrication and testing tochaiques for clad fuel elements, fuel rods, plates, and assemblies is described. Investigations of fuel and cladding alloys include crystal structure and thermal stability determinations on U--Mo alloys, studies on the nature of the hydride phase formed during corrosion of gamma -phase alloys in high- temperature water, and specific heat, resistivity, and phase diagram studies of U- -Mo and U--Nb alloys. The equilibrium and kinetics in the system UO/sub 2/--O/ sub 2/ are being studied to gain information on the structure and stability of UO/ sub 2/ under various conditions. Results of irradiation tests on UO/sub 2/ samples and of thermal cycling tests of Zircaloy-2 clad UO/sub 2/ rods are reported. Corrosion test resuIts are summarized for unclad and Zircaloy-2 clad U- - Mo and U--Nb samples. The radiation induced volume change of prototype fuel reds has been investigated. Studies of the fabrication cladding, tensile properties, and corrosion of U-- Si systems are described. Corrosion tests are continuing on Zircaloy-2 clad U-- Zr fuel elements and on various experimental Al alloys for cladding applications. Work was continued on the preparation, corrosion and sinterability of pure UO/sub 2/ and UO/sub 2/ containing additives. Operation and chemical analysis of in-pile loop experiments are described. Results are reported from studies of the erosion of UO/sub 2/ in high-velocity coolant, decontamination of water by ion exchange resins, sorption of radioisotopes on stainless steel, and decontamination of corrosion loops. Work in reactor physics has included PWR control calculations using a 2-dimensional UNIVAC code, calculation of fission product activity in the primary coolant, and criticaiity studies on the Flexibie Critical Experiment and on a lattice of UO/ sub 2/ fuel reds in the TRX. Current PWR plant parameters are recapitulated. (D.E.B.)

Physical Description

Medium: P; Size: Pages: 95

Source

  • Other Information: Decl. Mar. 16, 1957. Orig. Receipt Date: 31-DEC-58

Language

Item Type

Identifier

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

  • Report No.: WAPD-MRP-57(Rev.)
  • Grant Number: AT-11-1-GEN-14
  • DOI: 10.2172/4327739 | External Link
  • Office of Scientific & Technical Information Report Number: 4327739
  • Archival Resource Key: ark:/67531/metadc1023760

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

  • October 31, 1958

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

Description Last Updated

  • Jan. 17, 2018, 2:23 p.m.

Usage Statistics

When was this report last used?

Congratulations! It looks like you are the first person to view this item online.

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

Pressurized Water Reactor Program Technical Progress Report for the Period September 9 to October 20, 1955, report, October 31, 1958; Pittsburgh, Pennsylvania. (digital.library.unt.edu/ark:/67531/metadc1023760/: accessed September 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.