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Title: SPERT PROJECT QUARTERLY TECHNICAL REPORT, APRIL-JUNE 1962

Abstract

Static measurements of various nuclear core parameters were completed for the highly enriched plate-type Al-clad core to be used for the Spert I integral core destructive test program. Self-limiting power excursion tests were performed with initial asymptotic reactor periods in the range of 934 to 4.6 msec to establish the transient response of the core and to obtain data for extrapolation to shorter-period tests in which violent destructive effects are expected. For tests with periods shorter than about 7 msec, fuel plate deformations were produced as a result of thermal stresses in the plates. Melting of fuel plates was obtained in two tests with periods of 5 and 4.6 msec. For tests with periods in the range of 9 to 4.6 msec, power burst shape changes were observed which result in an increase in the ratio of the energy release in the total burst to that at the time of the power peak, as the period is shortened. Maximum transient pressures never exceeded 10 psi for tests thus far performed. A series of self-limiting power excursion tests was initiated in Spert II to determine the effects of the initial system temperature on the kinetic response of the D/sub 2/Omoderated expandedmore » core loading. The data indicate that as the initial system temperature is increased to near the saturation temperature, boiling becomes a more predominant shutdown mechanism with a consequent reduction in the peak power, burst energy, and fuel-plate surfacetemperature rise. The increased dependence on steam formation for shutdown as subcooling is decreased leads to relatively larger amplitudes for power oscillations following the initial burst. The larger unstable void volumes which are produced is the apparent reason for this occurrence. (auth)« less

Authors:
Publication Date:
Research Org.:
Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
OSTI Identifier:
4759250
Report Number(s):
IDO-16806
NSA Number:
NSA-17-002617
DOE Contract Number:  
AT(10-1)-205
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-63
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ALUMINUM; BOILING; DEFORMATION; ENERGY; ENRICHMENT; EXCURSIONS; FUEL CANS; FUEL ELEMENTS; HEAVY WATER MODERATOR; LOSSES; MEASURED VALUES; MELTING; OSCILLATIONS; PLATES; PRESSURE; PRODUCTION; QUANTITATIVE ANALYSIS; REACTIVITY; REACTOR CORE; REACTOR KINETICS; REACTOR PERIOD; REACTOR SAFETY; RESEARCH REACTORS; SHUTDOWN; SPERT-1; SPERT-2; STEAM; SURFACES; TEMPERATURE; TESTING; THERMAL STRESSES; TRANSIENTS; ZONES

Citation Formats

Schroeder, F. ed. SPERT PROJECT QUARTERLY TECHNICAL REPORT, APRIL-JUNE 1962. United States: N. p., 1962. Web. doi:10.2172/4759250.
Schroeder, F. ed. SPERT PROJECT QUARTERLY TECHNICAL REPORT, APRIL-JUNE 1962. United States. https://doi.org/10.2172/4759250
Schroeder, F. ed. 1962. "SPERT PROJECT QUARTERLY TECHNICAL REPORT, APRIL-JUNE 1962". United States. https://doi.org/10.2172/4759250. https://www.osti.gov/servlets/purl/4759250.
@article{osti_4759250,
title = {SPERT PROJECT QUARTERLY TECHNICAL REPORT, APRIL-JUNE 1962},
author = {Schroeder, F. ed.},
abstractNote = {Static measurements of various nuclear core parameters were completed for the highly enriched plate-type Al-clad core to be used for the Spert I integral core destructive test program. Self-limiting power excursion tests were performed with initial asymptotic reactor periods in the range of 934 to 4.6 msec to establish the transient response of the core and to obtain data for extrapolation to shorter-period tests in which violent destructive effects are expected. For tests with periods shorter than about 7 msec, fuel plate deformations were produced as a result of thermal stresses in the plates. Melting of fuel plates was obtained in two tests with periods of 5 and 4.6 msec. For tests with periods in the range of 9 to 4.6 msec, power burst shape changes were observed which result in an increase in the ratio of the energy release in the total burst to that at the time of the power peak, as the period is shortened. Maximum transient pressures never exceeded 10 psi for tests thus far performed. A series of self-limiting power excursion tests was initiated in Spert II to determine the effects of the initial system temperature on the kinetic response of the D/sub 2/Omoderated expanded core loading. The data indicate that as the initial system temperature is increased to near the saturation temperature, boiling becomes a more predominant shutdown mechanism with a consequent reduction in the peak power, burst energy, and fuel-plate surfacetemperature rise. The increased dependence on steam formation for shutdown as subcooling is decreased leads to relatively larger amplitudes for power oscillations following the initial burst. The larger unstable void volumes which are produced is the apparent reason for this occurrence. (auth)},
doi = {10.2172/4759250},
url = {https://www.osti.gov/biblio/4759250}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Sep 21 00:00:00 EDT 1962},
month = {Fri Sep 21 00:00:00 EDT 1962}
}