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

Title: Heavy Water Power Reactor Program Monthly Progress Report, October 1963

Abstract

Research and development progress is reported on the AEC-AECL cooperative program, CANDU Reactor development, creep-rupture properties of SAP, heat transfer and fluid flow studies, zirconium technology, metallurgy, Savannah River Componente Test Reactor operation, reactor fuel elements development, Carolinas-Virginia Tube Reactor development and operation, and power reactor technology.

Publication Date:
Research Org.:
Savannah River Operations Office, Aiken, SC
Sponsoring Org.:
US Atomic Energy Commission
OSTI Identifier:
4133982
Report Number(s):
SRO-95
A80046060
NSA Number:
NSA-18-003190
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-64
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ALUMINUM; CANDU; CREEP; CVTR; FAILURES; FLUID FLOW; FUEL ELEMENTS; HEAT TRANSFER; HEAVY WATER MODERATOR; METALLURGY; OPERATION; PLANNING; POWER PLANTS; REACTORS; SINTERED MATERIALS; ZIRCONIUM

Citation Formats

None. Heavy Water Power Reactor Program Monthly Progress Report, October 1963. United States: N. p., 1964. Web. doi:10.2172/4133982.
Copy to clipboard
None. Heavy Water Power Reactor Program Monthly Progress Report, October 1963. United States. doi:10.2172/4133982.
Copy to clipboard
None. Sat . "Heavy Water Power Reactor Program Monthly Progress Report, October 1963". United States. doi:10.2172/4133982. https://www.osti.gov/servlets/purl/4133982.
Copy to clipboard
@article{osti_4133982,
title = {Heavy Water Power Reactor Program Monthly Progress Report, October 1963},
author = {None},
abstractNote = {Research and development progress is reported on the AEC-AECL cooperative program, CANDU Reactor development, creep-rupture properties of SAP, heat transfer and fluid flow studies, zirconium technology, metallurgy, Savannah River Componente Test Reactor operation, reactor fuel elements development, Carolinas-Virginia Tube Reactor development and operation, and power reactor technology.},
doi = {10.2172/4133982},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Oct 31 00:00:00 EST 1964},
month = {Sat Oct 31 00:00:00 EST 1964}
}
Copy to clipboard
Technical Report:
View Technical Report (1.06 MB)
DOI:  10.2172/4133982
Save / Share:
Export Metadata
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.

  • Progress made in the development and operation of heavy water reactors is reported. lnformation is included on the fabrication and testing of the on- power refueling machine for the CANDU reactor, creep-rupture testing of SAP, nondestructive testing of fuel cladding, operation of HWCTR, development and operation of CVTR, development of DDCR, heat transfer and fluid dynamics of reactor fuel elements and rod bundles, development of fogcooled reactors, zirconium technology, fuel irradiation programs, and reactor physics. (N.W.R.)

  • Progress made in the development and operation of heavy water reactors is reported. Information is included on the fabrication and testing of the on- power refueling machine for the Candu Reactor, testing of Candu boiler, creep- rupture testing of SAP, nondestructive testing of fuel cladding, header and feeder piping fluid dynamics, testing of dome-type pressure tube closure seal, zirconium technology, heat transfer at low flux, Candu fuel radioactivity monitoring, Euratom cooperative program, operation of HWCTR, and development of CarolinasVirginia Tube Reactor. (N.W.R.)

  • ABS>Research and development progress is reported on the AEC-AECL cooperative program, the CANDU boiler section test, SAP testing, nondestructive tests, header and feeder piping fluid dynamics, zirconium technology, and metallurgy. Operation of the Heavy Water Components Test Reactor is summarized. Low-power physics and systems tests on the Carolinas-Virginia Tube Reactor are described. (M.C.G.)

  • A refueling machine and boiler for CANDU are described, along with the testing of these components. The operations and testing of CVTR and HWCTR are outlined. The feasibility of a Th-- U/sup 233/-fueled, D/sub 2/O-moderated power reactor is discussed. Mechanical properties and radiation testing of alloys (e.g., Inconel, Monel, Zircaloy-2, SAP, Zr--2.5% Nb--0.5% Cu) are reviewed. (T.F.H.)

  • Progress is reported on various reactor development programs. Topics included are: Candu Reactor development on on-power refueling machine, boiler testing, fuel assembly testing, and radioactivity monitoring system; creep- rupture testing of SAP alloys, nondestructlve testing of fuel cladding; header and feeder piping fluid dynamics; zirconium technology; heat transfer at low heat flux; capacity of heavy water reactors; hydraulic ball control system; material development; HWCTR operation; and Carolinas-Virginia Tube Reactor development and operation. (N.W.R.)