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Title: FUEL CYCLE PROGRAM, A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. THIRD QUARTERLY REPORT, JANUARY 1961-MARCH 1961

Abstract

The continuing analysis of the VBWR core resulted in refinements in the calculations for reactivity in voids, flux leakage and resonance escape probability. The Zircaloy cladding for 25 fuel assemblies was received and passed inspection. Preliminary measurements of VBWR flux oscillations, used to develop instrumentation and data interpretation techniques, showed random normally-distributed oscillations with a predominant frequency of 0.5 to 1.0 cycles/second. A model for analog computer simulation of a reactor as a feedback control system was adapted to VBWR. Equations for the hydraulics model and preliminary results from use of the model are presented. Irradiation of the Fuel Cycle stainless steel clad assemblies reached 412 MWD/T with specific powers of 28 kw/kg (average) and 52 kw/kg (peak) during January. Visual examination of the fuel after this irradiation indicated that it is in good condition. The VBWR was shut down during February and March for replacement of all in-core components made of 17-4 pH stainless steel with 304 stainless steel. The details of the first eight special fuel assemblies were determined and materials were ordered. The effects of steam quality, mass flow rate, and rod diameter on burnout heat flux are shown. The burnout heat flux varied inversely with massmore » flow rate; this result was contradictory to several previous correlations. The experimental phase of the high-pressure observational boiling experiment was completed. Reproducibility of the burnout points was good (about plus or minus 1 1/2%). High speed movies of the flow conditions at burnout are being analyzed. (auth)« less

Publication Date:
Research Org.:
General Electric Co. Atomic Power Equipment Dept. San Jose, Calif.
OSTI Identifier:
4835066
Report Number(s):
GEAP-3709
NSA Number:
NSA-15-030204
DOE Contract Number:  
AT(04-3)-189
Resource Type:
Technical Report
Resource Relation:
Other Information: Project Agreement No. 11. Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ANALOG SYSTEMS; BOILING; BURNOUT; CANNING; COMPUTERS; DISTRIBUTION; EQUATIONS; FLUID FLOW; FREQUENCY; FUEL CANS; FUEL ELEMENTS; HEATING; HYDRAULICS; INSPECTION; INSTRUMENTS; IRRADIATION; MEASURED VALUES; NEUTRON FLUX; OSCILLATIONS; PHOTOGRAPHY; PRESSURE; REACTIVITY; REACTOR CORE; REACTORS; RESONANCE ESCAPE PROBABILITY; RODS; STAINLESS STEELS; STEAM; TESTING; VARIATIONS; VBWR; WATER COOLANT; WATER MODERATOR; ZIRCALOY; ZIRCONIUM ALLOYS; ZONES

Citation Formats

None. FUEL CYCLE PROGRAM, A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. THIRD QUARTERLY REPORT, JANUARY 1961-MARCH 1961. United States: N. p., 1961. Web. doi:10.2172/4835066.
None. FUEL CYCLE PROGRAM, A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. THIRD QUARTERLY REPORT, JANUARY 1961-MARCH 1961. United States. doi:10.2172/4835066.
None. Tue . "FUEL CYCLE PROGRAM, A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. THIRD QUARTERLY REPORT, JANUARY 1961-MARCH 1961". United States. doi:10.2172/4835066. https://www.osti.gov/servlets/purl/4835066.
@article{osti_4835066,
title = {FUEL CYCLE PROGRAM, A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. THIRD QUARTERLY REPORT, JANUARY 1961-MARCH 1961},
author = {None},
abstractNote = {The continuing analysis of the VBWR core resulted in refinements in the calculations for reactivity in voids, flux leakage and resonance escape probability. The Zircaloy cladding for 25 fuel assemblies was received and passed inspection. Preliminary measurements of VBWR flux oscillations, used to develop instrumentation and data interpretation techniques, showed random normally-distributed oscillations with a predominant frequency of 0.5 to 1.0 cycles/second. A model for analog computer simulation of a reactor as a feedback control system was adapted to VBWR. Equations for the hydraulics model and preliminary results from use of the model are presented. Irradiation of the Fuel Cycle stainless steel clad assemblies reached 412 MWD/T with specific powers of 28 kw/kg (average) and 52 kw/kg (peak) during January. Visual examination of the fuel after this irradiation indicated that it is in good condition. The VBWR was shut down during February and March for replacement of all in-core components made of 17-4 pH stainless steel with 304 stainless steel. The details of the first eight special fuel assemblies were determined and materials were ordered. The effects of steam quality, mass flow rate, and rod diameter on burnout heat flux are shown. The burnout heat flux varied inversely with mass flow rate; this result was contradictory to several previous correlations. The experimental phase of the high-pressure observational boiling experiment was completed. Reproducibility of the burnout points was good (about plus or minus 1 1/2%). High speed movies of the flow conditions at burnout are being analyzed. (auth)},
doi = {10.2172/4835066},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {10}
}