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Title: MTR-ETR TECHNICAL BRANCHES QUARTERLY REPORT FOR PERIOD ENDING SEPTEMBER 30, 1959

Abstract

In the reactor technical assistance program, it has been shown that the fuel content of the ETR control rods can be increased by 75% to give a generated power increase (in a control rod) of 50% and a typical increase in excess reactivity of 0.55%, without exceeding heat transfer limitations. A metal fabrication facility was completed for developing and fabricating sample fuel plates for local research programs. Hydraulic tests on experimental thin-plate narrowchannel fuel elements showed flow distribution improved over that of conventional MTR fuel elements. In the search for stronger alloys to make possible elements having thinner plates, comparative strength tests were made on plates of 6061 and 1100 aluminum alloys (in the fully-annealed condition); results are reported. Oxidation rates for an aluminum-uranium sample exposed to water vapor have been shown to follow a linear rate law within close limits. A method has been developed for use of the RMF to determine effective cross sections in terms of neutron density, cadmium ratio, and characteristic neutron temperature. This method makes it possible to determine for a sample. by a reactivity measurement, parameters which can be used to express effective cross sections for the sample in other reactor spectra, provided theirmore » neutron temperature and 1/v cadmium ratio are known. Dow energy (<5ev) measurements on the total and fission cross sections of U/sup 233/ and the total cross section of Pa-231 have been completed. Eta measurements of U/sup 233/ are continuing on the crystal spectrometer with modified long-counter and MnSO/sub 4/ fast neutron detection. The shielded sample changer for radioactive samples was installed on the fast chopper and the background-reducing characteristics of quartz filters have been studied. The results of the fission mass yield study of Pa/sup 239/ as a function of neutron energy are reported. In the inelastic scattering program additional measurements have been made on water and on a Ge single crystal. Studies on the decays of Dy/sup 165/ and Eu/sup 156/ have led to proposed preliminary decay schemes. A 4 pi beta-gamma coincidence counting system with a resolving time of 3.90 mu sec and a unit efficiency of 99.9% has been placed in operation. Also operating is the 144-channel memory for the pulse height analyzer, with completion of the readout operation and controlling functions. Progress has been made in using the IBM-650 for Monte Carlo calculations. Inclusion of secondary collisions may change the conclusions reached when this process was neglected. (For preceding period see 1DO-16561.) (auth)« less

Publication Date:
Research Org.:
Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
OSTI Identifier:
4207963
Report Number(s):
IDO-16580
NSA Number:
NSA-14-010176
DOE Contract Number:  
AT(10-1)-205
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ALUMINUM ALLOYS- CONTROL ELEMENTS- FABRICATION- FLUID FLOW- FUEL ELEMENTS- FUELS- HEAT TRANSFER- MATERIALS TESTING- OXIDATION- QUANTITY RATIO- REACTIVITY- REACTORS- TESTING- URANIUM- VAPORS- VARIATIONS- WATER; BACKGROUND- CHOPPERS- FILTERS- NEUTRON SPECTROMETERS- PULSE GENERATORS- QUARTZ; BETA DETECTION- COINCIDENCE METHODS- COUNTERS- EFFICIENCY- - FOUR-PI COUNTERS- GAMMA DETECTION- RESOLUTION; CADMIUM- CROSS SECTIONS- MATERIALS TESTING- MEASURED VALUES- NEUTRON FLUX- NEUTRONS- REACTIVITY- REACTORS- SPECTRA- TEMPERATURE; CROSS SECTIONS- FAST NEUTRONS- FISSION- MANGANESE SULFATES- MEASURED VALUES- NEUTRO

Citation Formats

None. MTR-ETR TECHNICAL BRANCHES QUARTERLY REPORT FOR PERIOD ENDING SEPTEMBER 30, 1959. United States: N. p., 1960. Web. doi:10.2172/4207963.
None. MTR-ETR TECHNICAL BRANCHES QUARTERLY REPORT FOR PERIOD ENDING SEPTEMBER 30, 1959. United States. doi:10.2172/4207963.
None. Tue . "MTR-ETR TECHNICAL BRANCHES QUARTERLY REPORT FOR PERIOD ENDING SEPTEMBER 30, 1959". United States. doi:10.2172/4207963. https://www.osti.gov/servlets/purl/4207963.
@article{osti_4207963,
title = {MTR-ETR TECHNICAL BRANCHES QUARTERLY REPORT FOR PERIOD ENDING SEPTEMBER 30, 1959},
author = {None},
abstractNote = {In the reactor technical assistance program, it has been shown that the fuel content of the ETR control rods can be increased by 75% to give a generated power increase (in a control rod) of 50% and a typical increase in excess reactivity of 0.55%, without exceeding heat transfer limitations. A metal fabrication facility was completed for developing and fabricating sample fuel plates for local research programs. Hydraulic tests on experimental thin-plate narrowchannel fuel elements showed flow distribution improved over that of conventional MTR fuel elements. In the search for stronger alloys to make possible elements having thinner plates, comparative strength tests were made on plates of 6061 and 1100 aluminum alloys (in the fully-annealed condition); results are reported. Oxidation rates for an aluminum-uranium sample exposed to water vapor have been shown to follow a linear rate law within close limits. A method has been developed for use of the RMF to determine effective cross sections in terms of neutron density, cadmium ratio, and characteristic neutron temperature. This method makes it possible to determine for a sample. by a reactivity measurement, parameters which can be used to express effective cross sections for the sample in other reactor spectra, provided their neutron temperature and 1/v cadmium ratio are known. Dow energy (<5ev) measurements on the total and fission cross sections of U/sup 233/ and the total cross section of Pa-231 have been completed. Eta measurements of U/sup 233/ are continuing on the crystal spectrometer with modified long-counter and MnSO/sub 4/ fast neutron detection. The shielded sample changer for radioactive samples was installed on the fast chopper and the background-reducing characteristics of quartz filters have been studied. The results of the fission mass yield study of Pa/sup 239/ as a function of neutron energy are reported. In the inelastic scattering program additional measurements have been made on water and on a Ge single crystal. Studies on the decays of Dy/sup 165/ and Eu/sup 156/ have led to proposed preliminary decay schemes. A 4 pi beta-gamma coincidence counting system with a resolving time of 3.90 mu sec and a unit efficiency of 99.9% has been placed in operation. Also operating is the 144-channel memory for the pulse height analyzer, with completion of the readout operation and controlling functions. Progress has been made in using the IBM-650 for Monte Carlo calculations. Inclusion of secondary collisions may change the conclusions reached when this process was neglected. (For preceding period see 1DO-16561.) (auth)},
doi = {10.2172/4207963},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {1}
}