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

Title: APDA reactor components test

Abstract

A comprehensive description of the test operation and nonnuclear performance of the APDA Reactor Components Test is given. These activities were carried out in a facility consisting of the reactor, associated fuel handling mechanisms, and one primary sodium loop with pump and heat exchanger. A detailed description is included of the systems and components of the facility, and of the relation of the facility to the total plant. Unusual methods that were used in planning and erection of the facility and which contributed significantly to minimizing the cost and time of erection and testing are outlined. All the test operations conducted are reported, including discussion of the results obtained, unusual methods and tools employed, the few deficiencies discovered, and the modifications and improvements made to ready the test components for nuclear service.

Authors:
 [1];  [1];  [1];  [1];  [1];  [1];  [1]
+ Show Author Affiliations
  1. Atomic Power Development Associates, Inc., Detroit, MI (United States)
Publication Date:
Research Org.:
Atomic Power Development Associates, Inc., Detroit, MI (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
4684919
Report Number(s):
APDA-147
NSA Number:
NSA-17-042339
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-63
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; APDA; COOLANT LOOPS; ECONOMICS; FUELS; HEAT EXCHANGERS; LIQUID METAL COOLANT; PERFORMANCE; POWER PLANTS; REMOTE HANDLING; SERVOMECHANISMS; SODIUM; TESTING

Citation Formats

Costello, R. H., Fiedler, M. M., Flis, J. J., Jones, R. H., Lempges, T. E., Matte, III, J., and Vanmassenhove, G. APDA reactor components test. United States: N. p., 1962. Web. doi:10.2172/4684919.
Copy to clipboard
Costello, R. H., Fiedler, M. M., Flis, J. J., Jones, R. H., Lempges, T. E., Matte, III, J., & Vanmassenhove, G. APDA reactor components test. United States. doi:10.2172/4684919.
Copy to clipboard
Costello, R. H., Fiedler, M. M., Flis, J. J., Jones, R. H., Lempges, T. E., Matte, III, J., and Vanmassenhove, G. Thu . "APDA reactor components test". United States. doi:10.2172/4684919. https://www.osti.gov/servlets/purl/4684919.
Copy to clipboard
@article{osti_4684919,
title = {APDA reactor components test},
author = {Costello, R. H. and Fiedler, M. M. and Flis, J. J. and Jones, R. H. and Lempges, T. E. and Matte, III, J. and Vanmassenhove, G.},
abstractNote = {A comprehensive description of the test operation and nonnuclear performance of the APDA Reactor Components Test is given. These activities were carried out in a facility consisting of the reactor, associated fuel handling mechanisms, and one primary sodium loop with pump and heat exchanger. A detailed description is included of the systems and components of the facility, and of the relation of the facility to the total plant. Unusual methods that were used in planning and erection of the facility and which contributed significantly to minimizing the cost and time of erection and testing are outlined. All the test operations conducted are reported, including discussion of the results obtained, unusual methods and tools employed, the few deficiencies discovered, and the modifications and improvements made to ready the test components for nuclear service.},
doi = {10.2172/4684919},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Nov 01 00:00:00 EST 1962},
month = {Thu Nov 01 00:00:00 EST 1962}
}
Copy to clipboard
Technical Report:
View Technical Report (30.75 MB)
DOI:  10.2172/4684919
Save / Share:
Export Metadata
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.

  • ;
    The investigation undertaken to determine the effect of thermal cycling in sodium of various fuel pins has been concluded. Nine fuel pins, with various heat treatments, different end caps, and made by different manufacturers, were submitted for this test. The test consisted of the following thermal cycle: heating to 1375 plus or minus 25 d F, holding, cooling to 250 plus or minus 25 d F. The temperature of the test specimens exceeded 1200 d F for at least 1 hour for each cycle. At the conclusion of the tests, the pins were examined visually to determine whether any physicalmore » damage was evident, and what dimensional and metallurgical changes had occurred. The nine fuel pins that were thermally cycled all reacted similarly. The three variables that were thought to influence pin failure, namely fuel pin fabricator, type of heat treatment, and surface preparation were found to be inconsequential in this test. (W.L.H.)« less

  • ; ;
    BS>An investigation to determine the effect of thermal cycling in sodium of a fuel pin is reported. The pin submitted for the test was composed of uranium--2 wt.% zirconium sheathed in zirconium. The test consisted of the following thermal cycle: heating to 125O deg F, holding 5 min. then cooiing to 25O deg F and holding at 25O deg F to prevent the freezing of the sodium. The duration of the test was 25 cycles. At the completion of the thermal cycling, the pin was examined visually to determine whether any- physical damage was evident, and what dimensional and metallurgicalmore » changes had occurred. (auth)« less

  • ;
    An investigation was undertaken to determine the effect of thermal cycling in sodium of various fuel pins. The pin submitted for this test was a depleted uranium--10 wt.% molybdenum fuel pin sheathed with sponge zirconium, commercial grade. The pin was not end capped. The test consisted of the following thermal cycle: heating to 1575 plus or minus 25 deg F, holding, cooling to 250 plus or minus 25 deg F. The temperature of the test specimen exceeded 12OO deg F for at least 30 min. for each cycle. At the conclusion of 25 cycles, the pin was examined visually tomore » determine whether any physical damage was evident, and what dimensional and metallurgical changes had occurred. (auth)« less

  • ;
    The APDA irradiation test program from june 1954 to june 1957 for fuel materials included binary alloys of U-Cr, U-Zr, and U-Mo. It was shown that the U-5 wt.% chromium eutectic alloy does not have radiation stability. Irradiation of U-Zr alloy specimens containing 2, 2.2, 3, 5, 10, and 15% by weight of zirconium indicates that the radiation stability is inferior to the U-Mo alloys containing 3 1/2, 5, 7, and 10% by weight of molybdenum. The U-10 wt.% Mo alloy was selected as the reference fuel alloy for the Enrico Fermi Reactor, and tests to cover high burn-ups ofmore » this material under several conditions were completed. Post-irradiation meaasurements of density, dimensions, electrical reactivity, fission gas, and thermal conductivity were conducted on specimens irradiated from 0.36 to 1.4 total atom% burn-up. The results of the irradiations indicate that the retained gamma structare of the U-10 wt. % Mo alloy is more stable than the partially transformed or the transformed alpha-plus-epsilon stnuctures. However, none of the irradiated specimens of U-10 wt.% Mo showed severe dimensional changes. The average decrease in density of test specimens with retained gamma, partially transfermed, and transformed alpha-plus-epsilon stnuctures was determined to be 2.4, 3.3, and 3.9% per total atom% burn-up, respectively. (auth)« less