WorldCat Identities

U.S. Atomic Energy Commission Idaho Operations Office

Overview
Works: 451 works in 768 publications in 1 language and 2,681 library holdings
Genres: Periodicals  History  Handbooks and manuals 
Roles: Researcher
Classifications: QE75,
Publication Timeline
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Most widely held works by U.S. Atomic Energy Commission
Hydrologic conditions at the Idaho National Engineering Laboratory, Idaho : 1979-1981 update by Barney D Lewis( Book )

1 edition published in 1984 in English and held by 35 WorldCat member libraries worldwide

Chemical processing technology quarterly progress report( )

in English and held by 26 WorldCat member libraries worldwide

Materials testing reactor-engineering test reactor technical branches quarterly report : April 1-June 30, 1962 by J. R Huffman( Book )

21 editions published between 1960 and 1964 in English and held by 21 WorldCat member libraries worldwide

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)
Final report of SL-1 recovery operation by General Electric Company( Book )

2 editions published in 1962 in English and held by 7 WorldCat member libraries worldwide

In May, 1961, it waa determined no renewed nuclear reaction in the SL-1 pressure vessel was possible as long as water was excluded. It was therefore possible to proceed with the final phase of the SL-1 recovery. This work consisted of moving the pressure vessel and core to the Hot Shop at the north end of the National Reactor Testing Station, dissecting and analyzing the reactor and its components, cutting up and burying the reactor building, and decontaminating the rest of the SL-1 area. These things were accomplished by the General Electric Company between May 1961 and July 1962. It was determined that the central control rod was bound in its shroud at a position corresponding to 20- inch withdrawal. Analysis of the pertinent data showed that the amount of reactivity associated with this rod position, inserted at a rate compatihie with manual withdrawal of the rod, can explain the significant evidence which was coliected. No other means of withdrawing the rod was found to be in accordance with the evidence. It was found that the relatively low yield (130 Mw-sec) nuclear excursion produced a water hammer with pressures up to 10,000 psi, which, in turn, caused the pressure vessel to rise some 9 feet in the air. (auth)
Measurement error : identification and estimation by Fred H Tingey( Book )

3 editions published in 1960 in English and held by 6 WorldCat member libraries worldwide

Nuclear incident at the Idaho Chemical Processing Plant on October 16, 1959 : report of the investigating committee( Book )

2 editions published in 1960 in English and held by 6 WorldCat member libraries worldwide

Detector efficiency of continuous air monitor having the filter coaxial with the detector by E. A King( Book )

2 editions published in 1964 in English and held by 6 WorldCat member libraries worldwide

Engineering test reactor critical facility control system manual by F. A Meichle( Book )

4 editions published in 1961 in English and held by 6 WorldCat member libraries worldwide

Effectiveness of various solutions for decontaminating stainless steel, lead and glass by John B Huff( Book )

2 editions published in 1956 in English and held by 5 WorldCat member libraries worldwide

A method of estimating the kinetic effects of scram rods by K. V Moore( Book )

2 editions published in 1962 in English and held by 5 WorldCat member libraries worldwide

Economically optimum sweepdown criterion for chemical processing by Fred H Tingey( Book )

2 editions published in 1959 in English and held by 5 WorldCat member libraries worldwide

Fuel rod experience during the Spert I destructive test series with a stainless steel clad, rod-type core by J Dugone( Book )

2 editions published in 1965 in English and held by 5 WorldCat member libraries worldwide

Slow neutron inelastic scattering from aluminum powder by Robert M Brugger( Book )

2 editions published in 1965 in English and held by 5 WorldCat member libraries worldwide

Heat transfer in the ETR by V. A Walker( Book )

2 editions published in 1958 in English and held by 5 WorldCat member libraries worldwide

The adsorption of ruthenium from nitric acid-air mixtures by D. A Hanson( Book )

2 editions published in 1959 in English and held by 5 WorldCat member libraries worldwide

A summary report on ML-1 fuel element development in-pile test history by George L Vivian( Book )

2 editions published in 1964 in English and held by 5 WorldCat member libraries worldwide

A summary of the 1962 fuel element fission break in the MTR by J. W Dykes( Book )

2 editions published in 1965 in English and held by 5 WorldCat member libraries worldwide

A machine program for calculating slow neutron scattering cross sections with exact averaging over molecular orientation by L. J Gannon( Book )

2 editions published in 1965 in English and held by 5 WorldCat member libraries worldwide

Corrosion of alloys in various ICPP decontamination solutions by T. L Hoffman( Book )

2 editions published in 1961 in English and held by 4 WorldCat member libraries worldwide

Corrosion studies were conducted on stainless steel types 347 and Carpenter-20, Monel, titanium 55A, and tsntalum in decontamination solutions. These solutions are: 10% nitric acid, 10% citric acid, 10% sodium hydroxide--2.5% tartaric acid, 10% oxalic acid, 0.003M periodic acid in 0.05M nitric acid, 3% sodium fluoride --20% nitric acid, Turco 4501 and Turco 4502, and 0.25M phosphoric acid. Boron stainless steel type 304L was studied in 10% sodium hydroxide--2.5% tartaric acid, 10 and 60% nitric acids, Turco 4501 and Turco 4502. The two austenitic stainless steels were found to be acceptable construction materials for handling each of the decontamination solutions except 3% sodium fluoride--20% nitric acid. Special limitations are defined for Monel, titanium 55A, and tantalum when exposed to decontamination reagents. (auth)
Continuous dissolver theory by E. E Erickson( Book )

3 editions published in 1959 in English and held by 4 WorldCat member libraries worldwide

General relationships are developed for the performance of continuous flooded dissolvers based on complete mixing, such as tank flow, uniform packing characteristics of metal, and a first-order rate law. The form of the final equation is the same as that derived for the nonmixing or tube-flow case discussed in earlier reports of this series, with differences appearing only in the term that expresses the concentrations of metal and dissolvent in the liquid phase. The relationships are applied to available pilot plant data on the mercury-catalyzed dissolution of four shapes of 2S aluminum elements. The data cover a range of catalyst concentrations from 1.5 x 10⁻⁶ to 3.75 x 10/sup - 4/ molar Hg/sup 2+/ and metal bed heights from 1 to 10 feet in a 2-inch pyrex column. The average initial dissolvent concentration was 5.6M nitric acid. Round rods, flat plates, tubes, and flattened tubes are compared. The data for the round rods are utilized to determine the effective reaction velocity constants at the various catalyst concentrations. The general dissolver equation is used to predict the effect on dissolution rate of the shape of metal elements, liquid phase flow rate, and height of the bed of elements. Calculated rates follow the trends in the data, but not quite so well as calculated rates for the nonmixing or tube-flow case. The mathematical representation of the model is generally consistent with the pilot plant data. (See also IDO-14450 and IDO- 14451.) (auth)
 
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Audience Level
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Audience level: 0.76 (from 0.52 for Hydrologic ... to 0.96 for MTR techni ...)

Alternative Names

controlled identityUnited States. Energy Research and Development Administration. Idaho Operations Office

United States. Atomic Energy Commission. Idaho Operations Office

Languages
English (88)