Startup and Initial Testing of SM-1 Core II With Special Components (open access)

Startup and Initial Testing of SM-1 Core II With Special Components

The loading operation for SM-1 Core II is described. Results of startup physics measurements (Test A-300 (Series) and fission product iodine monitoring in the primary coolant are given. The SM-1 Core II initial loading progressed satisfactorily, fulfilling the predictions of the zero power experiment performed at the Alco Criticality Facility. The initial cold clean five rod bank position was 6.53 in.; the initial hot, no xenon, five rod bank position was 9.62 in.; the initial hot, equilibrium xenon, five rod bank position was 11.41 in.; and the initial hot, peak xenon, five rod bank position was 12.14 in. Rods A and B were 19.00 in. in all four measurements. Stuck rod measurements indicated that an adequate shutdown margin was available with 20% of the rods fully withdrawn. All rod calibrations indicated a distinct shift and broadening of the peaks when compared with similar Core I calibrations. The temperature coefficient for Core II was 3.5 cents/ deg F at 440 deg F. Equilibrium xenon was worth approximately - 00 while peak xenon was worth - 43, both relative to the hot, no xenon core condition. During the period June 2, 1961 through September 30, 1961, the reactor operated at a total …
Date: February 28, 1962
Creator: Moote, F. G. & Schrader, E. W.
Object Type: Report
System: The UNT Digital Library
Potential for efficient frequency conversion at high average power using solid state nonlinear optical materials (open access)

Potential for efficient frequency conversion at high average power using solid state nonlinear optical materials

High-average-power frequency conversion using solid state nonlinear materials is discussed. Recent laboratory experience and new developments in design concepts show that current technology, a few tens of watts, may be extended by several orders of magnitude. For example, using KD*P, efficient doubling (>70%) of Nd:YAG at average powers approaching 100 KW is possible; and for doubling to the blue or ultraviolet regions, the average power may approach 1 MW. Configurations using segmented apertures permit essentially unlimited scaling of average power. High average power is achieved by configuring the nonlinear material as a set of thin plates with a large ratio of surface area to volume and by cooling the exposed surfaces with a flowing gas. The design and material fabrication of such a harmonic generator are well within current technology.
Date: October 28, 1985
Creator: Eimerl, D.
Object Type: Report
System: The UNT Digital Library
Inspection of the Heber binary-cycle geothermal project (open access)

Inspection of the Heber binary-cycle geothermal project

We concluded that DOE had effective management control procedures to monitor project costs and the design, construction and demonstration activities. Lessons learned from previous DOE geothermal projects were applied and technical information generated from the Heber plant will be transferred to the public and private sectors by the project participants. We also identified the following issues that concerned us: Revenue Sharing: under existing revenue sharing provisions in the Cooperative Agreement, we estimate that reimbursable revenues to DOE will range between $30.5 million and $51.6 million. DOE and the public should be reimbursed for the total contribution of $61 million because the plant, if commercialized, will primarily benefit ratepayers and stockholders of San Diego Gas and Electric Company (SDG and E); Project Office Support Contracts: Our analyses of a number of project office support contracts suggest that some of this work should be cost shared with SDG and E; in other cases, the value of the work is questionable and appears to be an unnecessary expenditure of DOE funds; and Questionable Contractor Procurement: the noncompetitive procurement of a private firm to develop an economic study of a second Heber plant appears to be unjustified and duplicates work already planned by project …
Date: March 28, 1984
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Preliminary assessment of tree mortality near F- and H-area seepage basins (open access)

Preliminary assessment of tree mortality near F- and H-area seepage basins

A preliminary assessment was conducted to evaluate factors that may have been responsible for the vegetation damage that has occurred in groundwater seeps downslope from the F- and H-area seepage basins. The factors that were considered included altered hydrology, toxicity from hazardous chemical constituents associated with seepage basin operation, and toxicity from non-hazardous constituents associated with basin operation. It was concluded that the observed damage was not likely to have resulted from altered hydrologic conditions or hazardous constituents associated with basin operation. Insufficient information is currently available to determine definitively which of the non-hazardous constituents, alone or in concert, were responsible for the observed vegetation damage. The most likely explanation, however, is that elevated Na, pH, and conductivity is outcropping seep water are responsible for tree mortality. All three of these factors will return to ambient levels over a period of several years when basin operation ceases. Faster remediation can be achieved using lime at the seep line.
Date: January 28, 1988
Creator: Loehle, C & Gladden, J
Object Type: Report
System: The UNT Digital Library
A PROGRAM OF RESEARCH AND CALCULATIONS OF RESONANCE ABSORPTION. Final Report (open access)

A PROGRAM OF RESEARCH AND CALCULATIONS OF RESONANCE ABSORPTION. Final Report

A direct numerical integration of the integral equation for the average collision density in the absorber was previously suggested in a discussion of resonance absorption. The implementation of this program is considered. The method of calculation, comparison with experimental data, and the computer code developed are described. The method of integration, computation of cross sections, selection of mesh size, integration interval, outside correction, the Dancoff correction, and unresolved resonances are discussed. Resonance integrals for U/sup 235/ and Th2/sup >/s3>s/sup 2/ were calculated and compared with experiment. (M.C.G.)
Date: August 28, 1961
Creator: Nordheim, L.W.
Object Type: Report
System: The UNT Digital Library
Office of Waste Isolation progress report, January 1978 (open access)

Office of Waste Isolation progress report, January 1978

This document, prepared to report progress on the National Waste Terminal Storage (NWTS) program, consists of project reports on work performed by organizations under subcontract to OWI, by DOE contractors, by OWI consultants, and by other federal agencies participating in the NWTS program. The project reports are made under the headings technical projects, facility projects, planning and analysis, and regulatory affairs. (DLC)
Date: February 28, 1978
Creator: Zerby, C.D.
Object Type: Report
System: The UNT Digital Library
High resolution positron Q-value measurements and nuclear structure studies far from the stability line. Progress report (open access)

High resolution positron Q-value measurements and nuclear structure studies far from the stability line. Progress report

Research progress in briefly described, and details are presented in the attached preprints and reprints: (1) precision mass differences in light rubidium and krypton isotopes utilizing beta endpoint measurements; (2) precision mass measurements utilizing beta endpoints; (3) Monte Carlo calculations predicting the response of intrinsic GE detectors to electrons and positrons; and (4) reactor antineutrino spectra and nuclear spectroscopy of isotopes far from beta stability. (WHK)
Date: February 28, 1982
Creator: Avignone, F. T. III
Object Type: Report
System: The UNT Digital Library
Combustible radioactive waste treatment by incineration and chemical digestion (open access)

Combustible radioactive waste treatment by incineration and chemical digestion

A review is given of present and planned combustible radioactive waste treatment systems in the US. Advantages and disadvantages of various systems are considered. Design waste streams are discussed in relation to waste composition, radioactive contaminants by amount and type, and special operating problems caused by the waste.
Date: May 28, 1980
Creator: Stretz, L. A.; Crippen, M. D. & Allen, C. R.
Object Type: Article
System: The UNT Digital Library
AN INVESTIGATION OF THE HIGH-TEMPERATURE PROPERTIES OF THE AISI TYPE 502 STEEL (open access)

AN INVESTIGATION OF THE HIGH-TEMPERATURE PROPERTIES OF THE AISI TYPE 502 STEEL

None
Date: November 28, 1961
Creator: Martin, W. R. & McCoy Jr., H. E.
Object Type: Report
System: The UNT Digital Library
Tertiary Blast Effects: The Effects of Impact on Mice, Rats, Guinea Pigs and Rabbits. Technical Progress Report (open access)

Tertiary Blast Effects: The Effects of Impact on Mice, Rats, Guinea Pigs and Rabbits. Technical Progress Report

A total of 455 mlce, rats, gulnea plgs, and rabbits was subjected to lmpact at velocitles ranglng between 25 ft/sec and 51 ft/sec. The deslred velocities were generated by allowlng the anlmals to free-fall from various helghts to a flat concrete pad. The ventral surface of each anlmal was the area of impact. Problt analyses of the 24-hr mortallty data ylelded LD/sub 50/ lmpact veloclties with 95% confldence limits as follows: mouse, 39.4 (37.4 to 42.0) ft/ sec; rat, ft/sec; and rabbit, 31.7 (30.2 to 33.3) ft/sec. The LD/sub 50/ figures for the mouse and rat were slgnificantly higher, statlstically, than those for the gulnea plg and rabblt. The small spread ln the LD/sub 50/ values suggested little variation ln the tolerance of blologlcal systems to impact. Further, the steepness of the mortallty curves lndicated a narrow survlval range to lmpact. Extrapolatlon of the experimental data to the 70 kg anlmal yielded a predicted LD/ sub 50/ impact velocity of 26 ft/sec (18 mph). Literature relevant to the human case was revlewed and the tentative appllcabllity of the predlcted flgures to adult man ls discussed. (auth)
Date: February 28, 1961
Creator: Richmond, D. R.; Bowen, I. G. & White, C. S.
Object Type: Report
System: The UNT Digital Library
REMOTELY CONTROLLED SHEARING OF PIPE AND STRUCTURAL MEMBERS (open access)

REMOTELY CONTROLLED SHEARING OF PIPE AND STRUCTURAL MEMBERS

A shearing tool was developed for remotely controlled severing of pipes or structural members. The shear is rotated about its axis in a wrist motion by the pumped hydraulic fluid that also powers the shear blade. It can be used in a stationary mounting or suspended from a crane. A C-shaped support for the shear was designed to pass through a small top opening of a shielded cell. The controls for manipulating the shear pass through or along the Cframe. The shear jaw opens to 5 in. in height and 7 in. in width, and the total weight of the tool is only 575 lb. It was used to cut metal sections 4 3/4 in. thick and 4-in. sched.-40 stainless steel pipe. (auth)
Date: December 28, 1961
Creator: Abbatiello, A. A.
Object Type: Report
System: The UNT Digital Library
GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JUNE 30, 1961 (open access)

GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JUNE 30, 1961

Activities are discussed for research in design investigations, and materials development and testing conducted in connection with the development of the EGCR. The discussions are given in terms of: reactor physics; reactor design studies; heat transfer and fluid now investigations; materials development; in- pile and out-of-pile testing of components and materials; and development of test loops and components. (B.O.G.)
Date: August 28, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Enhanced durability and reactivity for zinc ferrite desulfurization sorbent (open access)

Enhanced durability and reactivity for zinc ferrite desulfurization sorbent

AMAX Research Development Center (AMAX R D) has been investigating methods for enhancing the reactivity and durability of the zinc ferrite desulfurization sorbent. Zinc ferrite sorbents are intended for use in desulfurization of hot coal gas in integrated gasification combined cycle (IGCC) or molten carbonate fuel cell (MCFC) applications. For the present program, the reactivity of the sorbent may be defined as its sulfur sorption capacity at the breakthrough point and at saturation in a bench-scale, fixed-bed reactor. Durability may be defined as the ability of the sorbent to maintain important physical characteristics such As size, strength, and specific surface area during 10 cycles of sulfidation and oxidation.
Date: August 28, 1987
Creator: Jha, Mahesh C.; Baltich, Linda K. & Berggren, Mark H.
Object Type: Report
System: The UNT Digital Library
Reactor Controls Reliability and Maintenance at the ORR (open access)

Reactor Controls Reliability and Maintenance at the ORR

Early evaluation and study of the various criteria for the ORR clearly established the requirements for the fundarnental safety and control instrumentation, and the instrumentation was well integrated into the design and construction of the plant. However, it was not designed for the optimum of maintenance convenience and minimum reactor down time in the event of instrument failure. The revisions and additions that have been made in the physical plant and maintenance which have resulted in a definite reduction of reactor down time resulting from instrument failure in the reactor and in the experiments are described. (auth)
Date: August 28, 1962
Creator: West, K.W.
Object Type: Report
System: The UNT Digital Library
Comparison of Gaseous Waste Handling Systems for PL-3 (open access)

Comparison of Gaseous Waste Handling Systems for PL-3

Gaseous waste handling systems are compared for direct and indirect boiling water and pressurized water reactors for PL-3 application. Areas that are common to the various concepts are not discussed since they do not enter into a comparison study. The major differences present are in the handling of active gases released to or held in the primary system coolant. These gases which could be present, their possibIe release from the system, and the necessary processing requirements are discussed in detail. Sufficient information is presented to enable one to analyze the methcds required to remove gaseous activity present in other size and type pressurized and boiIing water reactors. (auth)
Date: February 28, 1962
Creator: Noble, J. H. & Duke, E. E.
Object Type: Report
System: The UNT Digital Library
Broadband diffractive lens (open access)

Broadband diffractive lens

Significant progress has been made toward solving the century-old problem of chromatic aberrations in diffractive optics. Our approach exploits modern materials and microfabrication technology and is very different from the purely diffractive strategy,'' which is commonly employed and which results in multiple diffractive elements separated by a finite distance. We have developed a Fresnel zone plate lens comprised of a serial stack of patterned minus-filters which allows broadband radiation to be focused (or imaged) without longitudinal or transverse chromatic aberrations. 7 refs., 4 figs.
Date: May 28, 1991
Creator: Ceglio, N. M.; Hawryluk, A. M.; London, R. A.; Seppala, L. G. (Lawrence Livermore National Lab., CA (USA)) & Gaines, D. P. (Brigham Young Univ., Provo, UT (USA))
Object Type: Article
System: The UNT Digital Library
Instrumentation for two-phase geothermal flow (open access)

Instrumentation for two-phase geothermal flow

None
Date: May 28, 1975
Creator: Calder, C. A.
Object Type: Report
System: The UNT Digital Library
Toxic vapor hazard of heated mock high explosive. [200 to 700/sup 0/C] (open access)

Toxic vapor hazard of heated mock high explosive. [200 to 700/sup 0/C]

None
Date: April 28, 1975
Creator: Distler, T. M. & Kwok, Y. M.
Object Type: Report
System: The UNT Digital Library
Flexible Monte Carlo Programs FMC-N and FMC-G (open access)

Flexible Monte Carlo Programs FMC-N and FMC-G

Flexible Monte Carlo programs FMC-N and FMC-G (GE-ANPD Programs 516 and 515) are digital computer programs which apply Monte Carlo methods to simulate neutron and gamma ray life histories, respectively, in a source-shield configuration. The programs were designed for flexlbility in the geometrical, material, nuclear, and source descriptions of source-shield configurations and variance reduction techniques. The programs were also designed to optimize the use of fast memory and to provide complete freedom in the dimensions of the various input quantities. The programs are coded for an IBM-704 computer with a fast memory capacity of 32,768 storage locations and eight magnetic tape units, and for an IBM7090 computer wlth a fast memory capacity of 32,768 storage locations and ten magnetic tape unlts on two date channels. No magnetic drum storage is necessary for either computer. (auth)
Date: April 28, 1961
Creator: Loechler, J. J. & MacDonald, J. E.
Object Type: Report
System: The UNT Digital Library
Small Power Reactor Projects of the United States Atomic Energy Commission (open access)

Small Power Reactor Projects of the United States Atomic Energy Commission

Information on small power reactor projects of the USAEC is summarized. General information concerning the projects as a whole is given. Specific projects discussed include: the Elk River Power Reactor, the Piqua Nuclear Power Facility, the BONUS Power Reactor, the Pathfinder Power Reactor, the small-size pressurized water power reactor, and the experimental low-power process heat reactor. (M.C.G.)
Date: September 28, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Primary Shield Optimization Survey for the PL-3 Reactor (open access)

Primary Shield Optimization Survey for the PL-3 Reactor

A detailed study of four reactor and shield configurations was made. Two basic reactor types, the boiling water and pressurized water reactors were considered. Shield materials of lead-water and iron-water were used with varying thicknesses for determining the optimum shield configuration for the PL-3 reactor. Also presented is a survey of available shielding codes. (auth)
Date: June 28, 1962
Creator: Scoles, J. F. & Crouch, A. N.
Object Type: Report
System: The UNT Digital Library
Chemical Processing Technology Quarterly Progress Report, October-December 1961 (open access)

Chemical Processing Technology Quarterly Progress Report, October-December 1961

The ICPP processed Al fuel, prtncipally of the MTR-ETR type, durtng this quarter. Newly designed and installed processing equipment exhibited excellent operating performance. This included direct-air-pulsed extraction, stripping and scrub columns, and a cascade-controlled continuous evaporator in first cycle product concentration service. Aqueous zirconium fuel processing studies continued with the objective of adapting the hydrofluoric acid process to continuous dissolution-complexing to increase the capacity of the LCPP process while using as much existing equipment as possible to minimize costs. Six variations of hydrofluoric acid flowsheets were tested in a smallscale continuous dissolvers. Dissolution rates were found to be high in all cases and dissolution was easily initiated at temperatures as low as 36 deg C. Monel and Carpenter 2O(Nb) were found to be satisfactory construction materials, from the standpoint of corroston, if oxidizing conditions were carefully controlled. Additional studies are reported on the stability of blended Zr and Al process raffinates and on the nature of the solids which result from the sodium formate headend precipitation process. Electrolytic dissolution studies, dtrected at fundamentals of current utiltzation in a series''-type dissolver, demonstrated that high current utilization is obtained when the polarization resistance is small compared with the solution resistance. Factors affecting …
Date: March 28, 1962
Creator: Bower, J. R.
Object Type: Report
System: The UNT Digital Library
THE OAK RIDGE RESEARCH REACTOR (ORR), THE LOW-INTENSITY TESTING REACTOR (LITR), AND THE OAK RIDGE GRAPHITE REACTOR (OGR) AS EXPERIMENT FACILITIES (open access)

THE OAK RIDGE RESEARCH REACTOR (ORR), THE LOW-INTENSITY TESTING REACTOR (LITR), AND THE OAK RIDGE GRAPHITE REACTOR (OGR) AS EXPERIMENT FACILITIES

>Characteristics of the ORR, LITR, and OGR that experimenters have found to be important are listed. The results of a survey conducted among experimenters on the utility of the reactors for various types of experiments are discussed, and some changes which might be made to improve the utilization are listed. A brief outline, with references, of most of the experiments currently being performed is included. (auth)
Date: August 28, 1962
Creator: George, K.D.
Object Type: Report
System: The UNT Digital Library
Resonators for heavily beam-loaded linacs (open access)

Resonators for heavily beam-loaded linacs

Capacitively loaded resonant line section accelerating structures are discussed. Prototype models were measured at low levels, and calculations were made to predict high level operation. High current composite beams of multiple-beamlets as accelerated by a MEQALAC were assumed.
Date: April 28, 1980
Creator: Sanders, R.T.
Object Type: Report
System: The UNT Digital Library