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Title: MATERIALS TESTING REACTOR-ENGINEERING TEST REACTOR TECHNICAL BRANCHES QUARTERLY REPORT, OCTOBER 1-DECEMBER 31, 1960

Abstract

Experimental and calcuiated results show that flux flattening is accomplished by moving the boron burnable poison in ETR fuel elements from the fuel region to the sideplates. MTR shim rod calibrations were made for Cycle 146- B by distributed poison techniques. Excess reactivities calculated from these calibrations by three definitions give maximum values of from approximately 13.5 to 15.5%. The Advanced Reactivity Measurement Facility (ARMF) is now supplementing the Reactivity Measurement Facility (RMF) in making reactor physics measurements on small samples. The design aim of the ARMF is to achieve the maximum sensitivity and reproducibility possible with more stable operation and better control than in the RMF. Heat transfer calculations are being made on a thorium slug in the form of a thick-walled tube, which it is proposed to irrddiate, instead of the present solid slug, for U/sup 2//sup 3//sup 3/ production in the MTR high flux. Experimenthl techniques are being developed for measuring the l/E component of neutron flux in several experimental positions of the RMF. Irradiation of a highly enriched 54 wt.% UO/sub 2/--Al fuel plate sample to 56% U/sup 2//sup 3//sup 5/ burnup produced a reaction (flssion damage) zone around the UO/sup 2/ particles. Hydraulic tests mademore » on roughened fuel plates indicated roughening as a possible means of increasing the heat transfer rate during forced convection cooling. Analyses of the total cross sections for Pu/sup 2//sup 4//sup 1/ and Pa/sup 2//sup 3//sup 1/ were ess entially completed, and a final report for Pu/sup 2//sup 4//sup 1/ was submitted for publication. Measurements of U/sup 2//sup 3/ eta values using the Mn bath technique with the monochromatic crystal spectrometer neutrons were continued. Experimental results to date are primarily concerned with measurements of the corrections required. Scattering measurements for samples of U/sup 2//sup 3//sup 3/ were undertsken on the fast chopper. Various integral cross sections in reactor spectra were undertaken. The 27,000 b capture cross section of Pm/sup 1//sup 4//sup 8/ (T/sub 1//sub ///sub 2/ = 40.6 d) is of considerable reactor interest as a material produced from fission products at high fuel burnup. Neutron inelastic scattering measurements from methane were completed and compared with theoretical predictions based upon gas models. These measurements served to demonstrate the reliability of the experimental procedures and provided insight and valuable checks upon the theory as applied to a simple case. A previously unreported 3.14 hr isometric level was found in Y/sup 9//sup 0/ at 0.685 Mev. A program undertsken to determine the spin of the 512 kev level of decay of 2.3 d Np/sup 2// sup 3//sup 9/ by use of directional correlation measurements resulted in a preliminary level scheme. Continuing studies on gamma rays from the decay of both Pu/sup 2//sup 3//sup 9/ and Pu/sup 2//sup 4//sup 0/ resulted in gamma ray energy measurements not previously reported. A new end-window proportional counter was developed with improved geometry that minimizes the positive slope of the voltage plateau. An all-electronic scanning switch was developed to replace an existing 10 pole 100 position motor-driven rotary switch used to translate scaler data into a form usable by computer equipment. A number of new programs and computing techniques for the IBM-650 (and one for the IBM-704) were developed. These include a least squares program for use in calibrating the ARMF reguiating rod, a gamma spectrum interpolation scheme for use in generating analyzer response curves, an IBM-704 code for hot channel analysis in SPERT III, a nonlinear least squares program for the IBM-650, a program for use on the IBM-650 to edit input dath for the IBM-704 code PDQ, and a comprehensive MTR-ETR pricing and recordkeeping program for the irradiations in these reactors. (auth)« less

Publication Date:
Research Org.:
Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
Sponsoring Org.:
US Atomic Energy Commission (AEC)
OSTI Identifier:
4073659
Report Number(s):
IDO-16665
NSA Number:
NSA-15-020463
DOE Contract Number:  
AT(10-1)-205
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; BORON; BUCKLING; CONTROL; CONTROL ELEMENTS; EQUATIONS; FUEL ELEMENTS; HEAT TRANSFER; MATERIALS TESTING; MEASURED VALUES; MTR; NEUTRON FLUX; OPERATION; POISONING; REACTIVITY; REACTOR CORE; REACTORS; RODS; STABILITY; THORIUM; TUBES; URANIUM 233; VARIATIONS

Citation Formats

None. MATERIALS TESTING REACTOR-ENGINEERING TEST REACTOR TECHNICAL BRANCHES QUARTERLY REPORT, OCTOBER 1-DECEMBER 31, 1960. United States: N. p., 1961. Web. doi:10.2172/4073659.
None. MATERIALS TESTING REACTOR-ENGINEERING TEST REACTOR TECHNICAL BRANCHES QUARTERLY REPORT, OCTOBER 1-DECEMBER 31, 1960. United States. doi:10.2172/4073659.
None. Sat . "MATERIALS TESTING REACTOR-ENGINEERING TEST REACTOR TECHNICAL BRANCHES QUARTERLY REPORT, OCTOBER 1-DECEMBER 31, 1960". United States. doi:10.2172/4073659. https://www.osti.gov/servlets/purl/4073659.
@article{osti_4073659,
title = {MATERIALS TESTING REACTOR-ENGINEERING TEST REACTOR TECHNICAL BRANCHES QUARTERLY REPORT, OCTOBER 1-DECEMBER 31, 1960},
author = {None},
abstractNote = {Experimental and calcuiated results show that flux flattening is accomplished by moving the boron burnable poison in ETR fuel elements from the fuel region to the sideplates. MTR shim rod calibrations were made for Cycle 146- B by distributed poison techniques. Excess reactivities calculated from these calibrations by three definitions give maximum values of from approximately 13.5 to 15.5%. The Advanced Reactivity Measurement Facility (ARMF) is now supplementing the Reactivity Measurement Facility (RMF) in making reactor physics measurements on small samples. The design aim of the ARMF is to achieve the maximum sensitivity and reproducibility possible with more stable operation and better control than in the RMF. Heat transfer calculations are being made on a thorium slug in the form of a thick-walled tube, which it is proposed to irrddiate, instead of the present solid slug, for U/sup 2//sup 3//sup 3/ production in the MTR high flux. Experimenthl techniques are being developed for measuring the l/E component of neutron flux in several experimental positions of the RMF. Irradiation of a highly enriched 54 wt.% UO/sub 2/--Al fuel plate sample to 56% U/sup 2//sup 3//sup 5/ burnup produced a reaction (flssion damage) zone around the UO/sup 2/ particles. Hydraulic tests made on roughened fuel plates indicated roughening as a possible means of increasing the heat transfer rate during forced convection cooling. Analyses of the total cross sections for Pu/sup 2//sup 4//sup 1/ and Pa/sup 2//sup 3//sup 1/ were ess entially completed, and a final report for Pu/sup 2//sup 4//sup 1/ was submitted for publication. Measurements of U/sup 2//sup 3/ eta values using the Mn bath technique with the monochromatic crystal spectrometer neutrons were continued. Experimental results to date are primarily concerned with measurements of the corrections required. Scattering measurements for samples of U/sup 2//sup 3//sup 3/ were undertsken on the fast chopper. Various integral cross sections in reactor spectra were undertaken. The 27,000 b capture cross section of Pm/sup 1//sup 4//sup 8/ (T/sub 1//sub ///sub 2/ = 40.6 d) is of considerable reactor interest as a material produced from fission products at high fuel burnup. Neutron inelastic scattering measurements from methane were completed and compared with theoretical predictions based upon gas models. These measurements served to demonstrate the reliability of the experimental procedures and provided insight and valuable checks upon the theory as applied to a simple case. A previously unreported 3.14 hr isometric level was found in Y/sup 9//sup 0/ at 0.685 Mev. A program undertsken to determine the spin of the 512 kev level of decay of 2.3 d Np/sup 2// sup 3//sup 9/ by use of directional correlation measurements resulted in a preliminary level scheme. Continuing studies on gamma rays from the decay of both Pu/sup 2//sup 3//sup 9/ and Pu/sup 2//sup 4//sup 0/ resulted in gamma ray energy measurements not previously reported. A new end-window proportional counter was developed with improved geometry that minimizes the positive slope of the voltage plateau. An all-electronic scanning switch was developed to replace an existing 10 pole 100 position motor-driven rotary switch used to translate scaler data into a form usable by computer equipment. A number of new programs and computing techniques for the IBM-650 (and one for the IBM-704) were developed. These include a least squares program for use in calibrating the ARMF reguiating rod, a gamma spectrum interpolation scheme for use in generating analyzer response curves, an IBM-704 code for hot channel analysis in SPERT III, a nonlinear least squares program for the IBM-650, a program for use on the IBM-650 to edit input dath for the IBM-704 code PDQ, and a comprehensive MTR-ETR pricing and recordkeeping program for the irradiations in these reactors. (auth)},
doi = {10.2172/4073659},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {4}
}