Misplaced Pages

#203796

82-824: NLO may refer to: Fernald Feed Materials Production Center Naval Live Oaks Reservation , Florida, United States New London Orchestra , London, England Next to Leading Order, in the scientific context; see Leading-order term § Next-to-leading order NLO (magazine) , Russian print issue Nonlinear optics material Norman Lockyer Observatory , Sidmouth, Devon, England Nuffield Laboratory of Ophthalmology , Oxford, England See also [ edit ] [REDACTED] Search for "nlo" , "n-lo" , "nl-o" , or "n-l-o" on Misplaced Pages. All pages with titles beginning with NLO All pages with titles containing NLO NIO (disambiguation) N10 (disambiguation) Topics referred to by

164-409: A 2 + 5 ⁄ 8 " RB-6 Acme-Gridley machine and were centerless ground before the drilling operation. The oversize slug blank was then loaded into a magazine loader on a 1 + 5 ⁄ 8 " Acme and thence through a four-step drilling operation making a hole halfway through the blank. The blank was then reversed and again placed in the magazine loader. After a four-step drilling sequence produces

246-442: A graphite electrode modified with microscopic particles of the uranium oxide has been investigated. This experiment has also been done for U 3 O 8 . This is an example of electrochemistry of a solid modified electrode , the experiment which used for uranium trioxide is related to a carbon paste electrode experiment. It is also possible to reduce uranium trioxide with sodium metal to form sodium uranium oxides. It has been

328-432: A Li 2 CO 3 -K 2 CO 3 molten salt to be heated to 1,150–1,200 °F before being discharged singly to the mill table. The ingot was passed back and forth through the blooming mill until it was reduced to an oval billet approximately 2" to 2 + 1 ⁄ 2 ". The ends of the billet were then cut off by a cropping shear before it was pushed into an equalizing furnace. The billet was reheated to 1,150–1,200 °F in

410-490: A Medart Straightener. Rods to be beta heat treated by-pass the cooling bed and were lifted into the beta heat treating furnace by means of a hoist, to be held at 1,320–1,365 °F for 11–20 minutes and then quenched in cold water. After quenching, these rods were conveyed to the Medart straightener for straightening. The rods were located in 2 + 5 ⁄ 8 -inch Acme-Gridley automatic screw machines where slugs were cut from

492-519: A T-shaped structure ( point group C 2v ) for the molecule. This is in contrast to the commonly encountered D 3h molecular symmetry exhibited by most trioxides. From the force constants the authors deduct the U-O bond lengths to be between 1.76 and 1.79 Å (176 to 179 pm ). Calculations predict that the point group of molecular UO 3 is C 2v , with an axial bond length of 1.75 Å, an equatorial bond length of 1.83 Å and an angle of 161° between

574-497: A capacity of 3.6 metric tons or 55 gallon drums. This pneumatic transfer of the product was known as Gulping. The Green Salt Plant , the common name for Plant 4 , produced "green salt" ( uranium tetrafluoride ) from UO 3 . Green salt was the key intermediate compound in the overall process of producing uranium metal. This plant contains 12 banks of furnaces for the conversion of uranium trioxide to uranium tetrafluoride. Each bank consists of four furnaces in series. The first furnace

656-467: A charge of derbies and solid recycle scrap. The loaded crucibles were then mechanically positioned in induction melting and casting furnaces that were designed to give a maximum of flexibility and a minimum of human exposure to radioactivity. The uranium metal was melted under high vacuum to minimize contamination of the melt with atmospheric gases and to permit purification of the metal by distillation of volatile contaminants. At approximately 2,550 °F,

738-402: A condition known as a "boilover" results. The reaction generates so much gas that it becomes a foam and boils over the sides of the vat. Many workers were told to not step in any puddles on the floor as they were probably nitric acid left from one of these "boilover" incidents. The site employed their own cobblers just to repair work boots that had been exposed to too much acid. Another hazard was

820-747: A contractor for the Department of Energy . These Fernald Settlement Funds are administered by a US Federal Court, which maintains oversight of the Fernald Medical Monitoring Programs. The Fernald (Residents) Medical Monitoring Program (FMMP) is a voluntary ongoing medical surveillance program for community residents living within five miles of the perimeter of the Fernald site, and the Fernald Workers Medical Monitoring Program (FWMMP)

902-550: A degreasing tank, pickling tank, two rinse tanks and a hot air dryer before depositing the slug basket in the Inspection Department. The slugs were inspected for seams, striations, dimensions and handling defects with the good slugs being packed for shipment. In addition to the solid slugs produced in Plant 6, hollow fuel element production was started about January 1, 1956. Hollow slug blanks were produced oversize on

SECTION 10

#1732800969204

984-498: A diameter and distance between pipes making a criticality incident nigh impossible. Plant 2/3 was known as the Ore Refinery & Denitration Plant . It was called Plant 2/3 because two separate functions occur in the same building. Here uranium values were recovered from feed materials (i.e., ores, concentrates and residues) and were converted to concentrated uranium trioxide , also called orange salt. In addition to uranium,

1066-667: A high in 1960 of 10,000 metric tons to a low in 1975 of 1,230 metric tons. Refining uranium metal was a process requiring a series of chemical and metallurgical conversions that occurred in nine specialized plants at the site. Workers at the site were represented by the Fernald Atomic Trades and Labor Council. Releases from the Fernald site to the surrounding area resulted in exposure to community residents included ionizing radiation, soluble and insoluble forms of uranium, and various other hazardous chemicals. The Centers for Disease Control and Prevention (CDC) has conducted

1148-523: A historical exposure characterization and developed dose estimation models through the Fernald Dose Reconstruction Project, with an endpoint of developing an algorithm to estimate doses to individual persons who lived within the exposure assessment domain (the area within a ten kilometer radius from the center of the plant site). In addition to radioactive materials, many other non-radiological toxic substances were present in

1230-501: A hole all the way through the blank, a reamer was passed through this hole in the final position. The oversize Outer Diameter was turned concentric with the finished Inner Diameter on an automatic Sundstrand lathe. Subsequent operations were the same as those for the solid slug. Plant 7 was known as the 6 to 4 Plant because UF 6 was converted to UF 4 here. It was basically a high-temperature gas-to-solid reactor system that only operated for two years: 1954–1956. To produce UF 4 ,

1312-604: A lithium ion enters the lattice of this oxide electrode. Uranium oxide is amphoteric and reacts as acid and as a base , depending on the conditions. Dissolving uranium oxide in a strong base like sodium hydroxide forms the doubly negatively charged uranate anion ( UO 4 ). Uranates tend to concatenate, forming diuranate , U 2 O 7 , or other poly-uranates. Important diuranates include ammonium diuranate ((NH 4 ) 2 U 2 O 7 ), sodium diuranate (Na 2 U 2 O 7 ) and magnesium diuranate (MgU 2 O 7 ), which forms part of some yellowcakes . It

1394-541: A production facility for various processes. In the early years, derbies were produced there, in the manner described in Plant 5. Another process operated on a production scale was the direct conversion of uranium hexafluoride to green salt. This production process was operated with UF 6 that contained as much as 2.5% U235. A two-step procedure was used. First was the vaporization of UF 6 : solid UF 6 in large 10 or 14 ton cylinders were heated in autoclaves at approximately 110 °C to produce gaseous UF 6 . The next step

1476-532: A pure metal. However, improvement in production techniques permitted the eventual development of an oxalate precipitation process capable of producing pure thorium metal. Interest in this item declined during the 1956–1957 period and the plant operations evolved to the casting of enriched uranium ingots larger than those being processed in the Metals Production and Metals Fabrication Plants. Ingots were cast up to 13-inch diameter, 38-inch length and having

1558-600: A separate processing route for putting the uranium into solution. Uranium oxides are dissolved in 6000 gallon vats of pure nitric acid in the Oxide Digester (also known as the west metal dissolver), miscellaneous residues that required filtration were dissolved in the Slag Leach Digester, and metals were dissolved in the Metal Dissolver. If the ore was poured too rapidly into the nitric acid vats

1640-401: A system of conveyors, which conveys the material to a surge hopper that feeds the ring roll mill. The particle size output from the mill was controlled to about 100 mesh by an air classifier mounted directly on the mill. The undersized material was blown to a cyclone separator that was mounted directly above the first Gallagher sampler. The three Gallagher samplers in series each took a 10% cut of

1722-416: A weight approaching 2,000 pounds. As such the processes and equipment used were almost identical to those of Plants 5 and 6. The Pilot Plant consists of small size equipment for piloting refinery operations, hexafluoride reduction, derby pickling, ingot casting, and other equipment for special purposes. This plant was used for numerous process testing and experimental operations as well as being employed as

SECTION 20

#1732800969204

1804-746: Is UO 3 , of which several polymorphs are known. Solid UO 3 loses O 2 on heating to give green-colored U 3 O 8 : reports of the decomposition temperature in air vary from 200 to 650 °C. Heating at 700 °C under H 2 gives dark brown uranium dioxide (UO 2 ), which is used in MOX nuclear fuel rods. There is a high-pressure solid form with U 2 O 2 and U 3 O 3 rings in it. Several hydrates of uranium trioxide are known, e.g., UO 3 ·6H 2 O, which are commonly known as "uranic acid" in older literature due to their similarity in formula to various metal oxyacids , although they are not in fact particularly acidic. While uranium trioxide

1886-444: Is a case of a hard perhalogenated freon which is normally considered to be inert being converted chemically at a moderate temperature. Uranium trioxide can be dissolved in a mixture of tributyl phosphate and thenoyltrifluoroacetone in supercritical carbon dioxide , ultrasound was employed during the dissolution. The reversible insertion of magnesium cations into the lattice of uranium trioxide by cyclic voltammetry using

1968-631: Is a program for former workers who were employed when National Lead of Ohio was the contractor. Activities of the medical monitoring programs include both periodic medical examinations and diagnostic testing and yearly questionnaire data collection. In January 2007, there were 9,764 persons enrolled in the FMMP and 2716 former workers enrolled in the FWMMP. The FMMP has an extensive computer database available for research studies. Samples of whole blood, serum, plasma and urine were obtained from all FMMP participants at

2050-672: Is different from Wikidata All article disambiguation pages All disambiguation pages Fernald Feed Materials Production Center The Fernald Feed Materials Production Center (commonly referred to simply as Fernald or later NLO ) is a Superfund site located within Crosby Township in Hamilton County, Ohio , as well as Ross Township in Butler County, Ohio , in the United States . It

2132-873: Is encountered as a polymeric solid under ambient conditions, some work has been done on the molecular form in the gas phase, in matrix isolations studies, and computationally. At elevated temperatures gaseous UO 3 is in equilibrium with solid U 3 O 8 and molecular oxygen . With increasing temperature the equilibrium is shifted to the right. This system has been studied at temperatures between 900 °C and 2500 °C. The vapor pressure of monomeric UO 3 in equilibrium with air and solid U 3 O 8 at ambient pressure, about 10  mbar (1 mPa) at 980 °C, rising to 0.1 mbar (10 Pa) at 1400 °C, 0.34 mbar (34 Pa) at 2100 °C, 1.9 mbar (193 Pa) at 2300 °C, and 8.1 mbar (809 Pa) at 2500 °C. Infrared spectroscopy of molecular UO 3 isolated in an argon matrix indicates

2214-485: Is formed in the first week and then after four months studtite (UO 2 )O 2 ·4(H 2 O) was produced. This alteration of uranium oxide also leads to the formation of metastudtite , a more stable uranyl peroxide, often found in the surface of spent nuclear fuel exposed to water. Reports on the corrosion of uranium metal have been published by the Royal Society . Like all hexavalent uranium compounds, UO 3

2296-474: Is hazardous by inhalation, ingestion, and through skin contact. It is a poisonous, slightly radioactive substance, which may cause shortness of breath, coughing, acute arterial lesions, and changes in the chromosomes of white blood cells and gonads leading to congenital malformations if inhaled. However, once ingested, uranium is mainly toxic for the kidneys and may severely affect their function. The only well characterized binary trioxide of any actinide

2378-590: Is located at (000) and oxygens at (View the MathML source), (View the MathML source), and (View the MathML source) with some anion vacancies. The compound is isostructural with ReO 3 . The U-O bond distance of 2·073 Å agrees with that predicted by Zachariasen for a bond strength S = 1. Uranium trioxide reacts at 400 °C with freon-12 to form chlorine , phosgene , carbon dioxide and uranium tetrafluoride . The freon-12 can be replaced with freon-11 which forms carbon tetrachloride instead of carbon dioxide. This

2460-413: Is the hexavalent oxide of uranium . The solid may be obtained by heating uranyl nitrate to 400 °C. Its most commonly encountered polymorph is amorphous UO 3 . There are three methods to generate uranium trioxide. As noted below, two are used industrially in the reprocessing of nuclear fuel and uranium enrichment. [REDACTED] Uranium trioxide is shipped between processing facilities in

2542-439: Is used to separate uranium from other elements in nuclear reprocessing , which begins with the dissolution of nuclear fuel rods in nitric acid to form this salt. The uranyl nitrate is then converted to uranium trioxide by heating. From nitric acid one obtains uranyl nitrate , trans -UO 2 (NO 3 ) 2 ·2H 2 O, consisting of eight-coordinated uranium with two bidentate nitrato ligands and two water ligands as well as

NLO - Misplaced Pages Continue

2624-529: Is worth noting that uranates of the form M 2 UO 4 do not contain UO 4 ions, but rather flattened UO 6 octahedra, containing a uranyl group and bridging oxygens. Dissolving uranium oxide in a strong acid like sulfuric or nitric acid forms the double positive charged uranyl cation . The uranyl nitrate formed (UO 2 (NO 3 ) 2 ·6H 2 O) is soluble in ethers , alcohols , ketones and esters ; for example, tributylphosphate . This solubility

2706-428: The nitrogen dioxide fumes coming off the nitric acid vats. There were so many fumes that on high humidity days during the summer there appeared to be an orange cloud encasing this building and anyone just walking past would experience a sensation as if he had wandered into a swarm of bees. The resulting "UNH" ( uranium nitrate hexahydrate ) material pumped out of the vats was then processed through extraction to purify

2788-410: The uranium hexafluoride was first heated to form a gaseous compound and was then reduced to UF 4 . The reduction occurs in a reaction with hydrogen. UF 6 vapor and hydrogen will be mixed at the top of each reactor by means of a cyclonic type mixer. The bulk of the reduction reaction will occur at the top of the reactor. The UF 4 formed will be a powdery solid that falls like snow to the bottom of

2870-468: The Refinery was capable of extracting and purifying a number of different materials. The Ore Refinery consists of three major process areas designated digestion (Plant 2), extraction and denitration (Plant 3). Support areas include nitric acid recovery, raffinate treatment and refinery sump. The digestion, extraction, and raffinate areas included 'hot' and 'cold' sides. To provide radiation protection from

2952-427: The axial oxygens. The more symmetrical D 3h species is a saddle point, 49 kJ/mol above the C 2v minimum. The authors invoke a second-order Jahn–Teller effect as explanation. The crystal structure of a uranium trioxide phase of composition UO 2·82 has been determined by X-ray powder diffraction techniques using a Guinier-type focusing camera. The unit cell is cubic with a = 4·138 ± 0·005 kX. A uranium atom

3034-412: The breakout station was conveyed to the slag recycling plant, where it was stored awaiting processing for reuse as refractory liner. The slag recovery process consists of crushing, pulverizing, and classifying the slag, which was then transferred back to the reduction area for use. The next step in the plant consists of melting massive uranium metal and casting an ingot. Graphite crucibles were loaded with

3116-399: The breakout station. The yields expected from this operation were about 95%. There are many documented explosions of these furnaces due to improperly packed refractory lining or a magnesium flare. Whatever the cause, the building would fill with radioactive smoke along with a real probability that molten uranium metal would come pouring out of the bottom of the furnace. The MgF 2 slag from

3198-415: The case that it is possible to insert lithium into the uranium trioxide lattice by electrochemical means, this is similar to the way that some rechargeable lithium ion batteries work. In these rechargeable cells one of the electrodes is a metal oxide which contains a metal such as cobalt which can be reduced, to maintain the electroneutrality for each electron which is added to the electrode material

3280-399: The chemical reactor. The off-gases from the reduction reactors were passed to a hydrogen burner where the excess hydrogen was burned and then passed through a dust collector to remove any entrained uranium dioxide that might have been present. The UO 2 in the reduction furnace passed through a seal hopper and a feed screw to the first of the three hydrofluorination furnaces. The bed of UO 2

3362-427: The equalizing furnace and was then discharged into the finishing mill. The finishing mill consists of six stands that reduce the rod to the final diameter of 1.43" for Hanford rods, and 1.12" for Savannah River rods. The rods were cut into 22-foot lengths as they leave the last stand by means of a flying shear. The Savannah rods were air cooled to room temperature on the cooling bed and then were cold straightened in

NLO - Misplaced Pages Continue

3444-703: The facility. Fluor Fernald, part of the Fluor Corporation , was awarded the contract in 1992 for cleanup of the site. Fluor Fernald completed their portion of the cleanup in October 2006, 12 years ahead of schedule and 7.8 billion dollars below the original cost estimate. The waste was permanently buried at Waste Control Specialists . The site is permanently unfit for human habitation, according to federal scientists, and "will have to be closely monitored essentially forever". Cleanup costs were estimated at $ 1 billion over 10 years. The $ 4.4 billion cleanup of

3526-436: The familiar O=U=O core. UO 3 -based ceramics become green or black when fired in a reducing atmosphere and yellow to orange when fired with oxygen. Orange-coloured Fiestaware is a well-known example of a product with a uranium-based glaze. UO 3 -has also been used in formulations of enamel , uranium glass , and porcelain . Prior to 1960, UO 3 was used as an agent of crystallization in crystalline coloured glazes. It

3608-428: The form of a gel, most often from mines to conversion plants. Cameco Corporation , which operates at the world's largest uranium refinery at Blind River, Ontario , produces high-purity uranium trioxide. It has been reported that the corrosion of uranium in a silica rich aqueous solution forms uranium dioxide , uranium trioxide, and coffinite . In pure water, schoepite (UO 2 ) 8 O 2 (OH) 12 ·12(H 2 O)

3690-552: The hydrometallurgical recovery system. A brief description of the Winlo process follows: The primary purpose of Plant 9 , the Special Products Plant was to process slightly enriched uranium and to cast larger ingots than those produced in Plant 5. The plant contains facilities for producing derbies, ingots, slugs, and washers of various enrichments. Construction of the plant as a thorium metal production process

3772-405: The jaw crusher, rotary dryer, ring roll mill, air classifier, and cyclone separator. In addition to sampling incoming ores this plant reconditions 30 and 55 gallon drums used to transport and store radioactive materials onsite. It also contains a safe-geometry digestion system used to process enriched uranium materials assaying up to 5% U. This digester was so named because the piping was of such

3854-471: The large quantities of incoming ore concentrates. This plant was divided into two main processing lines, one for Q-11 and one for INX. Q-11 was the term used to refer to radium bearing ores primarily mined in the Belgian Congo while INX was a non-radium concentrate. The problem with handling radium bearing ores was that one of radium's daughter particles is radon : an invisible radioactive gas. Q-11

3936-1131: The molten metal was poured into a graphite mold and the ingot was allowed to cool and solidify. Additional equipment was provided for the ingot to be removed from the mold, weighed, cropped, sampled, and stored for further processing in the Metals Fabrication Plant [Plant 6]. The ingot was approximately 7" in diameter, by 45" long, and weighs about 1,200 pounds. Plant 6 was known as the Metals Fabrication Plant . "Ingots from Plant 5 and MCW Mallinckrodt Chemical Works were bloomed into billets and then rolled into rods that were straightened and machined to finished reactor slug dimensions. The finished product consists of either hollow or solid uranium slugs, designed for both internal and external cooling during pile irradiation. The product shipped from Plant 6 must pass rigid inspection for dimensional tolerances, metal quality, and surface conditions." Uranium ingots were charged into an automated ingot preheat furnace where they were lowered into

4018-491: The needs of development projects and special orders. Some of the equipment that was available for and had been used in enriched processing was as follows: The Fernald Closure Project is a program run by the United States Department of Energy to clean up the former uranium processing site Fernald Feed Materials Production Center. In 1990, Congress approved closure of the site and environmental cleanup of

4100-626: The plant area, storage of residual waste onsite, and filtering of uranium contamination from the Great Miami River aquifer. These cleanup operations, along with restrictions on establishing new wells in areas exceeding water contaminant limits, will continue for the foreseeable future. The following are links that provide additional information about the Fernald site and the health risks associated with its processes: Uranium trioxide Uranium trioxide (UO 3 ) , also called uranyl oxide , uranium(VI) oxide , and uranic oxide ,

4182-513: The production area as materials, by-products or products. Workers were exposed to chlorinated and non-chlorinated solvents, metals and metal salts, and nuisance dusts. Community residents may have been exposed to these substances through ground water pathways, soil contamination , and air dispersion of emissions from the site. Two separate medical surveillance programs, for former workers and community residents, have been funded by settlements of class action litigation against National Lead of Ohio,

SECTION 50

#1732800969204

4264-704: The production of fabricated uranium fuel cores by chemical and metallurgical techniques". The plant was known as the Feed Materials Production Center since the uranium fuel cores it produced were the 'feed' for the AEC's plutonium production reactors. These nuclear reactors were located at Oak Ridge, Tennessee , the Savannah River Site in South Carolina and at Hanford in the state of Washington. The uranium metal produced

4346-402: The radium-bearing Q-11 ore [the "hot" material], concrete shielding was provided around appropriate process equipment and the 'hot' side of each area was enclosed by concrete walls. The principal function of Plant 2/3 was uranium purification and conversion of uranium bearing materials into uranium trioxide (UO3), or orange oxide. There are three principal forms of uranium residues, each having

4428-458: The reactor. The Scrap Recovery Plant , the name given to Plant 8 , process primarily involves upgrading uranium recycle materials from FMPC and off-site operations to prepare feed materials for head-end processing in the Refinery. Operations include drum washing, filtering Refinery tailings, operation of rotary kiln, box, muffle, and oxidation furnaces, and screening of furnace products. Bomb liner material received from Plant 5 in mobile hoppers

4510-466: The rods. The Hanford slugs were then placed in the Heald machine, which cuts the slugs to desired lengths and finishes and radiuses the ends. The Savannah River slugs were reduced to exact dimensions of size, surface, and straightness on a centerless grinder after which a contour was placed on the surface by a thread rolling machine. The slugs were numbered and put on a basket on a conveyor that passes through

4592-403: The same term [REDACTED] This disambiguation page lists articles associated with the title NLO . If an internal link led you here, you may wish to change the link to point directly to the intended article. Retrieved from " https://en.wikipedia.org/w/index.php?title=NLO&oldid=1171338327 " Category : Disambiguation pages Hidden categories: Short description

4674-419: The solution. The UNH solution was passed through a multistage liquid-liquid counter current tower with tributyl phosphate and kerosene to extract the uranyl nitrate. The impurities exit the tower as the raffinate stream for further processing. The extract solution was passed through another counter current extraction tower to re-extract the uranyl nitrate from the kerosene into deionized water . The kerosene

4756-468: The solution. The solution was concentrated from 90 grams uranium per liter to 1300 grams uranium per liter in two stages. The concentrated solution now in 250 gallon batches was further heated, in a process known as Pot Denitration, to thermally denitrate the UNH to uranium trioxide . The uranium trioxide material was then pneumatically removed from the denitration pots and packaged out in hoppers with

4838-450: The stream fed to it, producing a sample approximately 0.1% of the original lot size. The main stream was conveyed to a drumming station where it was packaged in 55-gallon or 30-gallon drums for use in the Refinery. The official weight was taken at this point. The INX line was similar to the Q-11 line except that the thawing tunnel has been omitted and a hammer mill and bucket elevator replaces

4920-559: The surface areas was completed in December 2006, and the site was turned into the Fernald Preserve nature preserve . Thousands of tons of contaminated concrete, sludge, liquid waste, and soil were removed from the site and replaced with man-made wetlands and greenery. Ongoing cleanup operations include routine monitoring of the environmental conditions with test wells, including the uranium groundwater plume extending south of

5002-412: The time of the initial examination, and over 100,000 one-ml aliquots of these biospecimens have been stored at −80 °C since then. In June 1984, 39-year-old pipe fitter, David "Dave" Bocks disappeared on shift and was reported missing. A witness reported seeing Bocks and a supervisor inside of a vehicle at about 4:00 AM with the windows rolled up on a hot night having a serious discussion. At 5:00 AM,

SECTION 60

#1732800969204

5084-637: The total condenser. These were passed through potassium hydroxide scrubbers to remove the last traces of acid and then discharged to the atmosphere. Plant 5 , the Metals Production Plant main process equipment consisted of eleven jolters, five filling machines, forty-four reduction furnaces, two breakout stations in the Reduction Area and twenty-eight vacuum casting furnaces in the Recast Area. The conversion of UF to metal

5166-440: The witness reported seeing Bocks and speaking with him, who stated he was putting up his tools and headed toward Plant 4. His remains were later discovered inside a uranium processing furnace located in Plant 6; a sudden 28-degree drop in furnace temperature (which was kept at a constant 1350 degrees F) had been recorded at 5:15 AM during the night of Bocks' disappearance. The investigations found insufficient evidence that foul play

5248-481: Was a uranium processing facility located near the rural town of New Baltimore , about 20 miles (32 km) northwest of Cincinnati , which fabricated uranium fuel cores for the U.S. nuclear weapons production complex from 1951 to 1989. During that time, the plant produced 170,000 metric tons uranium (MTU) of metal products and 35,000 MTU of intermediate compounds, such as uranium trioxide and uranium tetrafluoride . Fernald came under criticism in 1984 when it

5330-520: Was accessible to the other main AEC sites. In addition, the site was close to Cincinnati's large labor force, the landscape was level making the site's construction easy, it was isolated, which provided safety and security, and it was located 30 to 50 feet above a large water aquifer , which supplied the water needed for uranium metal processing. From 1951 to 1989 Fernald converted uranium ore into metal, and then fabricated this metal into target elements for nuclear reactors. Annual production rates ranged from

5412-490: Was accomplished by the thermite reduction of green salt with magnesium in a refractory lined steel reaction vessel. 450 pounds of green salt were blended with approximately 72 pounds of magnesium. The resulting mixture was uniformly packed into the reduction "bomb", which has previously been lined with refractory slag in a jolting apparatus. Following these steps, the bomb was capped with refractory, sealed, and placed in one of 49 electric muffle furnaces. The furnace temperature

5494-430: Was completed in 1954 and the thorium process was begun in October 1954. Plant 9 was originally designed and constructed as a thorium metal production plant, yet had to be regarded as a semi-development works because of a lack of process information. The two basic processes, hydrofluoric acid precipitation of thorium fluoride and induction de-zincing and melting, which were used to start the plant, were not able to produce

5576-415: Was constructed of stainless steel for the hydrogen reduction of orange oxide to uranium dioxide , by the reaction: UO 3 + H 2 → UO 2 + H 2 O. The UO 2 was then fed directly to the first of the next three furnaces in series. These furnaces were constructed of Inconel for the hydrofluorination of uranium dioxide to green salt. The reaction was: UO 2 + 4HF → UF 4 + 2H 2 O. Orange oxide

5658-411: Was emptied at an unloading station and elevated to a surge hopper. Material as needed was sent from the surge hopper through a jaw crusher and into a shelf type oxidation furnace. Here the metallic uranium was oxidized to triuranium octoxide (U 3 O 8 ). The material discharged from the furnace was lifted to a surge hopper and then as needed was sent through a roll mill and ground to -325 mesh size. It

5740-409: Was filtered and the uranium bearing cake was introduced to a drying furnace. The dried UAP was sent to the refinery. In addition to the wet system described, several furnaces were installed in the plant for massive metal oxidation, pyrohydrolysis, drying, chip and sludge combustion, etc. Most of the furnaces can be used for more than one of the above operations. During the summer of 1962, a new facility

5822-445: Was in the form of derbies, ingots, billets and fuel cores. The FMPC also served as the country's central repository for another radioactive metal, thorium . The plant was located in the rural town of Fernald, which is about 20 miles (32 km) northwest of Cincinnati, Ohio , and occupies 1,050 acres (425 hectares). This location was chosen because it was between the uranium ore delivery ports of New York and New Orleans , and it

5904-633: Was involved. However, some, including Bocks' family, believed that he was murdered by one or more coworkers who suspected him of being a whistleblower in the 1984 nuclear emissions scandal. The production process at the Fernald Feed Materials Production Center begins at Plant 1 , also known as the Sampling Plant . The principal function of the Sampling Plant was to obtain representative samples of

5986-532: Was learned that the plant was releasing millions of pounds of uranium dust into the atmosphere, causing major radioactive contamination of the surrounding areas. News about the plant's operations led to the 1989 closure of nearby Fort Scott Camp , then the oldest Roman Catholic summer camp in the country. In 1948 the Atomic Energy Commission , predecessor to the U.S. Department of Energy , established "a large scale integrated facility for

6068-497: Was moved through the hydrofluorination furnace by ribbon flight screws and contacted counter-currently by hydrofluoric acid vapors. The UF 4 was removed from the third furnace and conveyed to a packaging station where the product was packaged in 10-gallon pails for use in the Metal Plant, or in 5-ton containers for shipment to the cascades. The off-gases containing water vapor formed in the reaction and excess hydrofluoric acid

6150-454: Was raised to approximately 1,225 °F and after about four hours the thermite type reduction reaction occurs: UF 4 + 2Mg → 2MgF 2 + U (metal). The charge was then allowed to separate and cool in the furnace for 10 minutes, after which it was removed and cooled to room temperature. Finally, the solidified uranium metal (derby) was separated from the slag and liner materials in a sequence of manual and mechanical operations that take place at

6232-421: Was received from the Refinery in five-ton mobile hoppers, which were mounted on seal hoppers to feed the reduction furnace at a rate of approximately 375 pounds per hour for producing metal grade UF 4 . The powder was agitated and carried through the reduction furnace by a ribbon flight screw. Dissociated ammonia was metered to the reduction reactors and passed counter-currently to the bed of uranium oxide within

6314-419: Was received in 55-gallon drums. The drums were deheaded before processing and were conveyed through a thawing tunnel, which also provided surge capacity of deheaded drums. The drums were lifted to the top of the building by a skip hoist where they were emptied into a surge hopper that feeds the magnetic separator and jaw crusher. From the jaw crusher, the one-half inch material passes through a rotary drum dryer to

6396-483: Was removed from the first furnace and were sent to hydrofluoric acid recovery. The gases first passed to a partial condenser that removed all of the water in the form of 70% aqueous hydrofluoric acid. The remainder of the gases was then passed to a total condenser, which condenses the remainder of the acid as anhydrous hydrofluoric acid. The gases at this point contain only the nitrogen from seals and purge gases and small amounts of hydrofluoric acid that did not condense in

6478-549: Was started in Plant 8 for the production of UF 4 by an aqueous precipitation technique known as the Winlo process. The Winlo process was developed for the low-cost chemical conversion of relatively pure uranium concentrates to green salt by a hydrometallurgical process. The feed to the plant Winlo system was made up of a combination of black oxide (U 3 O 8 ) generated by burning metallic residues, uranyl chloride solutions generated by dissolving massive metal residues in hydrochloric acid, and UAP produced from low-grade residues in

6560-601: Was the reduction of the UF 6 gas, which involved mixing it with hydrogen gas at 480–650 °C in metal reactors to produce UF 4 powder. Hydrogen fluoride was a valuable byproduct of the reaction, which was: UF 6 + H 2 → UF 4 + 2HF. In addition, most of the thorium production activity at the FMPC took place inside the Pilot Plant. Thorium production activities began in 1964 and continued until 1980. The Pilot Plant met

6642-462: Was then fed into carbon brick digestion tanks where the uranium was dissolved in hydrochloric acid containing a little sodium chlorate . The undissolved solids were filtered off and dumped into a truck, which hauls the spent material to a scrap dump. Uranium in the filtrate was sent to a precipitation tank and precipitated with ammonium hydroxide (NH 4 OH), in presence of phosphoric acid to form UAP (uranyl ammonium phosphate). The resulting slurry

6724-408: Was then processed through a wash to be recycled back through the extraction process. The resulting UNH solution was now ready for further concentrating and thermal denitration. The UNH solution was concentrated through a process known as "boildown". In this process, heat was applied to the solution from steam coils inside the boildown tanks. The water was removed through evaporation, thus concentrating

#203796