Between October 1952 and February 1957, National Lead of Ohio (NLO), a primary contractor for the Atomic Energy Commission (AEC), subcontracted certain uranium machining operations to Alba Craft Laboratory, Incorporated, located at 10-14 West Rose Avenue, Oxford, Ohio. In 1992, personnel from Oak Ridge National Laboratory (ORNL) confirmed the presence of residual radioactive materials from the AEC-related operations in and around the facility in amounts exceeding the applicable Department of Energy (DOE) guidelines. Above-guideline radiation levels were also found both indoors and outdoors at 525 S. Main Street, a private residential property in the immediate vicinity of the Alba Craft site. This document reports the findings at this private residence. Although the amount of uranium found on the properties posed little health hazard if left undisturbed, the levels were sufficient to require remediation to bring radiological conditions into compliance with current guidelines, thus ensuring that the public and the environment are protected. A team from ORNL conducted a radiological verification survey of the property at 525 S. Main Street, between November 1993 and December 1994. The survey was conducted at the request of DOE and included directly measured radiation levels, the collection and analysis of soil samples to determine concentrations of uranium and certain other radionuclides, and comparison of these data to the guidelines.
The former Associate Aircraft Tool and Manufacturing Company site is located at 3550 Dixie Highway, Fairfield, Ohio. Associate Aircraft Tool and Manufacturing Company produced hollow uranium slugs in a machine shop at the site in 1956. The work was performed for National Lead of Ohio in a contract with the Atomic Energy Commission to augment the capacity of the Feed Materials Production Center at Fernald in the development of nuclear energy for defense-related projects. The current occupant of the building, Force Control, operates a multipurpose machine shop. At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at the former Associate Aircraft Tool and Manufacturing Company Site, Fairfield, Ohio. The survey was performed from February to May of 1995. The purpose of the survey was to verify that radioactivity from residues of {sup 238}U was remediated to a level below acceptable DOE guidelines levels.
At the request of the USDOE, a team from ORNL conducted an independent radiological verification survey at the former Bridgeport Brass Company Facility, Seymour, Connecticut, from September 1992 to March 1993. Purpose of the survey was to determine whether residual levels of radioactivity inside the Ruffert Building and selected adjacent areas were rmediated to levels below DOE guidelines for FUSRAP sites. The property was contaminated with radioactive residues of {sup 238}U from uranium processing experiments conducted by Reactive Metals, Inc., from 1962 to 1964 for the Atomic Energy Commission. A previous radiological survey did not characterize the entire floor space because equipment which could not be moved at the time made it inaccessible for radiological surveys. During the remediation process, additional areas of elevated radioactivity were discovered under stationary equipment, which required additional remediation and further verification. Results of the independent radiological verification survey confirm that, with the exception of the drain system inside the building, residual uranium contamination has been remediated to levels below DOE guidelines for unrestricted release of property at FUSRAP sites inside and outside the Ruffert Building. However, certain sections of the drain system retain uranium contamination above DOE surface guideline levels. These sections of pipe are addressed in separate, referenced documentation.
We report neutron diffraction studies on a series of La[sub 2]NiO[sub 4+[delta]] single crystals with 0.05[approx lt][delta][approx lt]0.11. At 300 K, all of the crystals have an average tetragonal structure (space group [ital I]4/[ital mmm]). On cooling below 290 K, one or more orthorhombic phases appear, characterized by incommensurate superlattice peaks at (0,[ital k],[ital l][plus minus][Delta]) with [ital k] odd, [ital l] even, and 1/4[lt][Delta][le]1/2. The positions, widths, and intensities of the superlattice peaks are quite sensitive to the cooling rate. We show that the incommensurate peaks are evidence of intercalated layers of oxygen spaced periodically along the [ital c] axis, with a one-dimensional ordering similar to the staging of intercalates in graphite. The structure of the La[sub 2]NiO[sub 4] lattice between the interstitial layers is of the [ital Bmab]-type; the superlattice peaks result from the ordered antiphase domain boundaries induced by the interstitial oxygens, which sit at (1/4,[ital 1] / 4 , 1/4)-type positions. Observed orderings involve interstitial layers separated by two to four Ni-O layers. Peak shapes and positions are modelled quantitatively using the formulas of Hendricks and Teller for one-dimensional disorder in a layer lattice. Besides the one-dimensional ordering of the intercalant layers, temperature-dependent phase separations aremore » observed. Because of the slow ordering kinetics, phase separation can be suppressed by rapid cooling.« less
A radiological characterization survey of the interior of the Building 7819 Decontamination Facility at Oak Ridge National Laboratory (ORNL) was conducted during July 1993. The interior of Building 7819 is grossly contaminated, and the contamination is highly transferable. Levels of alpha and beta contamination inside the building exceed ORNL guidelines for zoning as a Contamination Area. Gamma whole-body exposure rates generally ranged from 0.1 to 20 mR/h. Total beta-gamma surface contamination ranged from 1,000 to 520,000 dpm/100 cm{sup 2}, and transferable beta-gamma contamination ranged from 200 to 174,000 dpm/100 cm{sup 2}. A pump and a metal table near the pit exhibited beta dose rates of 3 rad/h and 300 mrad/h, respectively, and gamma exposure rates of 250 mR/h and 25 mR/h at contact, respectively. Total alpha contamination levels ranged from 100 to 110,000 dpm/100 cm{sup 2}, and transferable contamination ranged from 21 to 440 dpm/100 cm{sup 2}. The ledge at the north end of the pit above the sink demonstrated alpha contamination of approximately 100,000 dpm/100 cm{sup 2}. Radionuclide analysis of 11 smear samples showed the primary beta emitters to be {sup 90}Sr and {sup 137}Cs with trace amounts of {sup 60}Co. The Building 7819 Decontamination Facility was zoned as a Contamination Area and Radiation Area at the time of this survey, and the zoning is justified by the results of the survey. The building will also be zoned as an Airborne Radioactivity Area, based on the results of air sampling. Recommendations for corrective actions are included.
This report presents information on (1) a new improved synthesis of carrier-free rhenium-188-labeled Re(V) dimercaptosuccinic acid (DMSA) complex as a potential therapeutic agent for treatment of thyroid medullary carcinoma; and (2) the synthesis and evaluation of a series of iodine-125-labeled analogues of altanserine for imaging of serotonin receptors.
We describe the synthesis of the cis- and trans-iodovinyl isomers of the new ORNL cholinergic-muscarinicreceptorligand, 1 -azabicyclo[2.2-2]oct-3-yl{alpha}-hydroxy-{alpha}-(1-iodo-l-propen-3-yl)-{alpha}-phenylacetate (``IQNP``). This agent is prepared in high radiochemical yield, and the racemic mixture shows high specificity and selectivity for the cerebral and myocardial receptors. Since two chiral centers are present in this molecule, it is important to evaluate the importance of the absolute configuration of the two centers on receptor specificity. The tributyltin substrates were carefully separated by column chromatography, converted to the iodine-125 analogues by iododestannylation, and evaluated in rats in vivo. While the ``E`` (trans) isomer cleared rapidly from the receptor-rich areas of rat brain, the ``Z`` (cis) isomer showed high uptake in these areas but also high concentration in the cerebellum. In contrast, the E,Z-isomeric mixture showed good uptake and retention in the receptor rich areas. Also described in this report is a description of neutron flux measurements in the hydraulic tube position at the ORNL High Flux Isotope Reactor (HFIR). Also during this period, samples of [l-125]- and [l-131]-labeled racemic ``IQNP`` were supplied through a collaborative program with the Brookhaven National Laboratory for high resolution autoradiographic studies in rat tissues.
Rat tissue distribution properties of IQNP,'' a new radioiodinated cholinergic-muscarinic receptor antagonist, are described. IQNP is the acronym for 1-azabicyclo(2.2.2)oct-3-yl {alpha}-hydroxy-{alpha}-phenyl-{alpha}(1-iodo-1-propen-3-yl) acetate, which is an analogue of the QNB muscarinic antagonist in which the p-iodophenyl moiety has been replaced with the 1-iodo-1-propen-3-yl moiety. The radioiodinated IQNP analogue is easier to prepare in much higher yields than QNB and is thus a candidate for the evaluation of muscarinic receptors by external imaging techniques. Studies in rats demonstrated that IQNP shows high uptake in those cerebral regions rich in muscarinic receptors QNB-treatment of rats either 1 h before (pre) or 2 h after (post) administration of radioiodinated IQNP resulted in significant displacement or blocking of cerebral specific IQNP uptake (% dose/gm) in the cortex and striatum. These studies demonstrate that IQNP has specificity for the cholinergic-muscarinic receptor and is a good candidate for further studies. Also during this period, several agents developed in the ORNL Nuclear Medicine Program were supplied to Medical Cooperative Programs for collaborative studies including the iodine-125-labeled BMIPP and DMIPP fatty acid analogues and the IPM antibody labeling agent. Tin-117m and gold-199 were produced in the ORNL High Flux Isotope Reactor (HFIR) and supplied to the OHER-supported program in the Medical Department at Brookhaven National Laboratory to aid in their research until the re-start of the High Flux Brookhaven Reactor.
Iridium-194 (t{sub {1/2}} = 19.15 h) decays by {beta}-particle emission (E{sub {beta}}{sup max} = 2.236 MeV) and is a potential candidate for radioimmunotherapy (1,2). An important characteristic is availability of carrier-free {sup 194}Ir from {beta}-decay of {sup 194}Os (t{sub {1/2}} = 6 y). The {sup 194}Os parent nuclei is produced in a fission nuclear reactor with double neutron capture on {sup 192}Os (41.0% natural abundance). We report here the preliminary nuclear data for production of {sup 194}OS and discuss the feasibility of producing sufficient quantities of {sup 194}Os required for the fabrication of the large-scale generators for further studies. In addition, we describe a novel gas- thermochromatographic method (GTC) for the one step conversion of metallic Os to OsO{sub 4} and subsequent separation and purification of OsO{sub 4}. 6 refs., 1 fig., 1 tab.
Iridium-194 (t12 = 19.15 h) decays by beta-particle emission (Emax = 2.236 MeV) and is a potential candidate for radioimmunotherapy. An important characteristic is availability of 194Ir from decay of reactor-produced 194Os (t12 = 6 y). We report the fabrication of the first 194Os/194Ir generator system using activated carbon. In addition, a novel gas thermochromatographic method was developed for the one step conversion of metallic Os to OsO4 and subsequent separation and purification of OsO4. In this manner, the reactor irradiated enriched 192Os target was converted to 194OsO4, which was then converted to the K2OsCl6 for generator loading. The yield and the elution profile of carrier-free 194Ir, and 194Os breakthrough were determined for a prototype generator which was evaluated over a 10-month period.
We have developed an efficient {sup 188}W/{sup 188}Re alumina-based generator to provide carrier-free {sup 188}Re. This {sup 188}Re will be used for direct-labeling of antibodies to be used for both radioimmunodiagnosis and radioimmunotherapy. Previous studies have involved small scale generators (< 10 mCi of {sup 188}W); the goal of the present study was to fabricate and test a clinical prototype generator (170--180 mCi {sup 188}W), an amount chosen to generate 40--75 mCi of {sup 188}Re/day. In order to investigate radiolysis in the alumina-based system, columns either remained in saline at all times ( wet'') or had saline removed by an air stream after isotope elution ( dry''). Wet columns had a 40% yield after 2--3 days in saline, while dry columns had a yield of 60-75% after 2--3 days dry, indicating radiolysis may be decreasing the yield. Dry columns gave an average elution yield of 80--95%. The {sup 188}W/{sup 188}Re system has proven to be useful in providing 100--200 mCi or higher levels of carrier-free {sup 188}Re readily and consistently for labeling antibodies or other agents for therapeutic studies. 9 refs., 2 figs. (MHB)
${\mathrm{La}}_{2}$${\mathrm{NiO}}_{4+\ensuremath{\delta}}$ (\ensuremath{\delta}=0) has a high-temperature tetragonal (HTT) phase (T>680 K), a low-temperature orthorhombic (LTO) phase, and a low-temperature tetragonal (LTT) phase (T70 K); that is, HTT\ensuremath{\rightarrow}LTO\ensuremath{\rightarrow}LTT). These phases are isomorphic to those of ${\mathrm{La}}_{2\mathrm{\ensuremath{-}}\mathit{x}}$${\mathrm{Ba}}_{\mathit{x}}$${\mathrm{CuO}}_{4}$ (x=0.12). Using Raman spectroscopy, we have measured the c-axis-polarized phonons. The $^{2}$${\mathit{A}}_{1\mathit{g}}$ modes of the HTT phase occur in all three phases at 155 and 445 ${\mathrm{cm}}^{\mathrm{\ensuremath{-}}1}$, with energies and widths only weakly dependent on temperature. The low-energy ${\mathrm{NiO}}_{6}$-octahedra tilting modes (which drive the phase transitions) have been observed and clearly show the first-order nature of the LTO\ensuremath{\rightarrow}LTT phase transition. The lowest-energy Raman mode observed (at 70 ${\mathrm{cm}}^{\mathrm{\ensuremath{-}}1}$ with ${\mathit{B}}_{1\mathit{g}}$ symmetry), allowed only in the LTT phase, involves rocking motion of the undisplaced in-plane oxygen atoms.
We have studied the polarized infrared reflectance of a stoichiometric single crystal of ${\mathrm{La}}_{2}$${\mathrm{NiO}}_{4}$ through the Abma (${\mathit{D}}_{2\mathit{h}}^{18}$) (low-temperature orthorhombic) \ensuremath{\rightarrow}P${4}_{2}$/ncm (${\mathit{D}}_{4\mathit{h}}^{16}$) (low-temper- ature tetragonal) structural phase transition. This transition, which occurs near 70 K, involves a rigid tilt of the Ni-${\mathrm{O}}_{6}$ octahedra and produces distinct changes in the infrared-active phonons. Our observations are consistent with a first-order phase transition. This phase transition also occurs in ${\mathrm{La}}_{1.88}$${\mathrm{Ba}}_{0.12}$${\mathrm{CuO}}_{4}$, and has a profound influence on superconductivity in that material.
In this report the use of a simple colorimetric assay employing the bisthiosemicarbazone (TSC) derivative of phenylglyoxal to evaluate the specific activity of spallation-produced copper-67 (Cu-67) samples is described. Four samples from the Los Alamos National Laboratory (LANL) and one sample from the Brookhaven National Laboratory (BNL) were analyzed and the results compared in a blind study'' with specific activity values obtained by isotope coupling plasma (ICP) analysis at the production sites. A good comparison was found, and these results indicate that the TSC approach is a simple, inexpensive, and rapid technique to determine the specific activity of spallation-produced Cu-67. The synthesis, radioiodination, and evaluation of deiodination in rats in vivo of two new maleimide agents for antibody labeling is also described. 3 figs., 1 tab.
Journal of Labelled Compounds and RadiopharmaceuticalsVolume 26, Issue 1-12 p. 162-164 Symposium Abstract Neutron production of Os-191 and separation from Ir-192 for a medical Os-191/Ir-191m generator C. Brihaye, C. Brihaye University of Liege, Cyclotron Research Center B30, 4000 Liège (Belgium)Search for more papers by this authorM. Guillaume, M. Guillaume University of Liege, Cyclotron Research Center B30, 4000 Liège (Belgium)Search for more papers by this authorF.F. Knapp Jr., F.F. Knapp Jr. Nuclear Medicine Group, Oak Ridge National Laboratory, Oak Ridge, TN 37831 (USA)Search for more papers by this authorS. Dewez, S. Dewez University of Liege, Cyclotron Research Center B30, 4000 Liège (Belgium)Search for more papers by this authorD.E. Rice, D.E. Rice Nuclear Medicine Group, Oak Ridge National Laboratory, Oak Ridge, TN 37831 (USA)Search for more papers by this authorA.P. Callahan, A.P. Callahan Nuclear Medicine Group, Oak Ridge National Laboratory, Oak Ridge, TN 37831 (USA)Search for more papers by this author C. Brihaye, C. Brihaye University of Liege, Cyclotron Research Center B30, 4000 Liège (Belgium)Search for more papers by this authorM. Guillaume, M. Guillaume University of Liege, Cyclotron Research Center B30, 4000 Liège (Belgium)Search for more papers by this authorF.F. Knapp Jr., F.F. Knapp Jr. Nuclear Medicine Group, Oak Ridge National Laboratory, Oak Ridge, TN 37831 (USA)Search for more papers by this authorS. Dewez, S. Dewez University of Liege, Cyclotron Research Center B30, 4000 Liège (Belgium)Search for more papers by this authorD.E. Rice, D.E. Rice Nuclear Medicine Group, Oak Ridge National Laboratory, Oak Ridge, TN 37831 (USA)Search for more papers by this authorA.P. Callahan, A.P. Callahan Nuclear Medicine Group, Oak Ridge National Laboratory, Oak Ridge, TN 37831 (USA)Search for more papers by this author First published: January 1989 https://doi.org/10.1002/jlcr.2580260170AboutPDF ToolsRequest permissionExport citationAdd to favoritesTrack citation ShareShare Give accessShare full text accessShare full-text accessPlease review our Terms and Conditions of Use and check box below to share full-text version of article.I have read and accept the Wiley Online Library Terms and Conditions of UseShareable LinkUse the link below to share a full-text version of this article with your friends and colleagues. Learn more.Copy URL Share a linkShare onFacebookTwitterLinkedInRedditWechat Volume26, Issue1-12January 1989Pages 162-164 RelatedInformation