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Title: ML-1-1A Core studies with the GCRE critical assembly

Abstract

Critical assembly studies were conducted tc provide physics and engineering data to aid in developing the Mobile Low-Power Reactor (ML-1). The ML-1-lA core was critical with 59 elements containing 17,906.71 g of U 235 and had an excess reactivity of 0.381 x 10 -2 DELTA k/k at a moderator temperature of 24.91 deg C. The ratio of maximum element power to core-averaged power was approximately 1.09. The ratio of maximum to core-averaged thermal flux was approximately 1.10. At an 18-deg separation, the shutdown worth of the cadmium-covered control-blade mock-up was 1.14 x 10 -2 DELTA k/k for a 69 element core. Radial and upper axial reflector-moderator void coefficients were - 0.59 plus or minus 0.07 and -0.36S plus or minus 0.015 x 10 -2 DELTA k/ k.per in., respectively. Two lA production fuel elements were evaluated in the critical assembly core. The results predict that the production elements tested contained roughly the same fuel as the critical assembly element and an additional 772 g of stainless steel equivalent on the average. Radial power and neutron flux distributions were measured in a 19-pin lB fuel element. Fairly uniform distributions were observed. Data to evaluate the thermal utilization of this element weremore » obtained.« less

Authors:
; ; ;
Publication Date:
Research Org.:
Battelle Memorial Inst., Columbus, Ohio
OSTI Identifier:
4206668
Report Number(s):
BMI-1396
NSA Number:
NSA-14-006031
DOE Contract Number:  
W-7405-ENG-92
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 42 ENGINEERING; CADMIUM; CONTROL ELEMENTS; CRITICAL ASSEMBLIES; DISTRIBUTION; FUEL ELEMENTS; ML-1; MOCKUP; MODERATORS; NEUTRON FLUX; POWER; POWER PLANTS; REACTIVITY; REACTOR CORE; REACTORS; REFLECTORS; SHUTDOWN; STAINLESS STEELS; TEMPERATURE; THERMAL NEUTRONS; THERMAL UTILIZATION; URANIUM 235; ZONES

Citation Formats

Egen, R. A., Hogan, W. S., Dingee, D. A., and Chastain, J. W. ML-1-1A Core studies with the GCRE critical assembly. United States: N. p., 1959. Web. doi:10.2172/4206668.
Egen, R. A., Hogan, W. S., Dingee, D. A., & Chastain, J. W. ML-1-1A Core studies with the GCRE critical assembly. United States. https://doi.org/10.2172/4206668
Egen, R. A., Hogan, W. S., Dingee, D. A., and Chastain, J. W. Fri . "ML-1-1A Core studies with the GCRE critical assembly". United States. https://doi.org/10.2172/4206668. https://www.osti.gov/servlets/purl/4206668.
@article{osti_4206668,
title = {ML-1-1A Core studies with the GCRE critical assembly},
author = {Egen, R. A. and Hogan, W. S. and Dingee, D. A. and Chastain, J. W.},
abstractNote = {Critical assembly studies were conducted tc provide physics and engineering data to aid in developing the Mobile Low-Power Reactor (ML-1). The ML-1-lA core was critical with 59 elements containing 17,906.71 g of U235 and had an excess reactivity of 0.381 x 10-2 DELTA k/k at a moderator temperature of 24.91 deg C. The ratio of maximum element power to core-averaged power was approximately 1.09. The ratio of maximum to core-averaged thermal flux was approximately 1.10. At an 18-deg separation, the shutdown worth of the cadmium-covered control-blade mock-up was 1.14 x 10-2 DELTA k/k for a 69 element core. Radial and upper axial reflector-moderator void coefficients were - 0.59 plus or minus 0.07 and -0.36S plus or minus 0.015 x 10-2 DELTA k/ k.per in., respectively. Two lA production fuel elements were evaluated in the critical assembly core. The results predict that the production elements tested contained roughly the same fuel as the critical assembly element and an additional 772 g of stainless steel equivalent on the average. Radial power and neutron flux distributions were measured in a 19-pin lB fuel element. Fairly uniform distributions were observed. Data to evaluate the thermal utilization of this element were obtained.},
doi = {10.2172/4206668},
url = {https://www.osti.gov/biblio/4206668}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {11}
}