Magnetic Isotope Effect in the Uranium Isotopes Separation

Total Page:16

File Type:pdf, Size:1020Kb

Magnetic Isotope Effect in the Uranium Isotopes Separation MAGNETIC ISOTOPE EFFECT IN THE URANIUM ISOTOPES SEPARATION I. V. Zhyganiuk Institute for Safety Problems of Nuclear Power Plants, Nat. Acad. of Sci. of Ukraine 36a, Kirova str., Chornobyl 07270, Ukraine* Institute of Artificial Intelligence Problems, Nat. Acad. of Sci. of Ukraine and 40, Academician Glushkov Ave., Kyiv 03680, Ukraine A. V. Zubko and O. B. Lysenko Institute of Environmental Geochemistry, Nat. Acad. of Sci. of Ukraine and 34a, Palladin Ave., Kyiv 03142, Ukraine When uranyl nitrate is photolysed in the water solution, light isotope 235U is separated from isotope 238U ; an enrichment factor K = 1:04 . The initial samples were depleted by a light isotope of uranium 235U (degree 훽 = 0:00455). Regenerated uranyl nitrate was enriched by an isotope of uranium 235U (degree 훼 = 0:00464). Uranium tetrafluoride was depleted by an isotope of uranium 235U (degree 훽 = 0:00446). Uranium isotopes are separated by the magnetic isotope effect (MIE) in uranyl nitrate photoreduction. Keywords: uranium isotopes, magnetic isotope effect. In memory of Academician Emlen Sobotovich, an pairs induced by photolysis in heavy water solu- outstanding scientist tions; authors investigated MIE in these chem- ical reactions. These results are presented in this manuscript. For more details about MIE, I. INTRODUCTION see [2–10]. These effects and processes have been used for a new chemical separation of ura- The results of a theoretical investiga- nium isotopes. tion of interactions between electron magnetic arXiv:1802.02530v1 [physics.chem-ph] 7 Feb 2018 moments and nuclear–magnetic moment pub- lished in work [1] in 1975; this work was II. EXPERIMENTAL the first to show that existence to the MIE. In the photoinduced reaction uranyl ni- Buchachenko A. and his group originally discov- trate was regenerated in the р-methoxyphenol ered the MIE in 1976 [2]. and heavy water solution. The initial samples Uranyl nitrate ions complexes are being of uranyl nitrate were depleted by a light iso- regenerated uranyl-ion and nitrate-ion radicals tope of uranium 235U (degree 훽 = 0:00455). *Electronic address: [email protected] In work [9], the initial samples of uranyl ni- 2 trate were enriched by an isotope of uranium → hν 235U (degree 훼 = 0:112). Our experiments 235 • + • 235 were conducted in solutions of following con- [ UO2 OAr ] T→S UO2 (NO3 ) 2 −3 centration: UO2(NO3)2 — 1:6 · 10 mol/l, [р- −2 → methoxyphenol] — 5:0·10 , NH4F — 1:0 mol/l, hν 238 • + H2SO4 — 0:5 mol/l in heavy water. UO •• 2 % [238 UO+ OAr ] → Depleted uranium dioxide was dissolved in 2 238 UF4 6 concentrated nitric acid; this solution was evap- orated; we had received uranyl nitrate in dry Figure 1: Scheme of the processes were being oc- residue. Solutions were prepared and mixed; curred in the photolysis of uranyl; in this scheme introduce next denotation: unpaired electron (·), they were placed in a quartz vessel. Next replaced phenol (Ar), triplet state (T), singlet state step, the solutions were deoxygenated flushing + (S), uranoyl (UO2 ) with argon; the quartz vessel was hermetically sealed. III. RESULTS AND THEIR Further, the solutions had been irradiat- DISCUSSION ing by an ultraviolet lamp (characteristics of the lamp: Δ휆 = 350 ÷ 450 nm; P = 61W ), A triplet-singlet conversion had been fin- ished in radical pair before the uranyl regen- until a suspension with UF4 was formed in so- lutions. Next, the irradiation had been stop- erated to the uranyl nitrate; it is presented by Fig. 1. The triplet-singlet conversion has been ping, before the precipitate with UF4 didn’t completed formation. Then, the suspension occurred because electrons spines precessed in magnetic field of uranium nucleus 235U. An with UF4 was being decanted in the centrifuge. + Here, we had separated uranium tetrafluoride uranoyl UO2 is a singly charged complex of in the precipitate. Uranium isotope ratios were uranyl-ion with unpaired electron. At this stage 2+ being measured in the uranium tetrafluoride of reaction, an uranyl-ion UO2 is being en- 235 + and the uranyl nitrate. These results were be- riched by isotope U; the uranoyl UO2 is be- 235 ing obtained by MI-1201 mass spectrometer (at ing depleted by isotope U. Uranoyl formed State Institution ”Institute of Environmental the insoluble precipitate with uranium tetraflu- Geochemistry, National Academy of Sciences of oride UF4 in a disproportionation reaction. 235 Ukraine”). The degree of enriched 훼 in isotope U (the degree of depleted (훽)) or isotope ratio in the sample determined to the formula 휈(235U) 훼 = ; (1) 휈(235U) + 휈(238U) 3 where is 휈(235U) isotope substance amount factor K(1) to have the value of 1:02. In present 235U ; is 휈(238U) isotope substance amount work, the enrichment factor K(1) to have the 238U. larger value 1:04 (see formula (2)) than value Since, the averaged values degree of en- from paper [9]. riched or the isotope ratio: 1) the initial The enrichment factor related the sepa- (0) uranyl nitrate sample 훽 2+ = 0:00454, 2) ura- rated methods of uranium isotopes are shown UO2 nium tetrafluoride precipitate 훽UF4 = 0:00446, in papers [10, 11]. The Steenbeck’s centrifu- and 3) regenerated uranyl nitrate 훼 2+ = gal isotopes separations methods occupied a UO2 0:00464. Therefore, in this work isotope sep- first place in accordance with efficiency. But, aration 235U238U enrichment factor equal: the MIE method of isotopes separation takes the second place. Unfortunately, for implement 훼UO2+ (1 − 훼UO2+ ) K(1) = 2 2 = 1:040; (2) 훽UF4 (1 − 훽UF4 ) centrifugal isotopes separation method we nec- (1) where K is the enrichment factor, and 훼 2+ essary have high expenses for factory building, UO2 is the degree of enriched regenerated uranyl ni- and for high technical complexity of construc- trate, 훽UF4 is the degree of depleted precipitate tion. Industrial method of isotopes separation with UF4 . by the gaseous diffusion is being implemented Isotopic composition of regenerated uranyl in the big industrial cluster includes plant and nitrate and uranium tetrafluoride was measured a power station. The building of such industrial by mass spectrometer. The enrichment factor cluster is a very expensive process. Therefore, of uranyl nitrate photolysed with MIE equal the industrial method of isotopes separation by 1:04, see formula (2). the gaseous diffusion is a difficult technical and The experimental evidence of the degrees economical problem. An initial compound is of enriched 훼 with isotope 235U from the regen- uranium hexafluoride for the centrifugal iso- erated uranyl nitrate showed on Fig. 2. Here, topes separation methods and for the method we see 16 dots under the line corresponding of isotopes separation by the gaseous diffusion. (0) to degree 훽 2+ = 0:00454, where uranyl ni- In the period of terrorist danger, the plant with UO2 trate depleted with isotope 235U. Next, we gaseous toxic uranium hexafluoride is a critical see 8 dots allocated in a vicinity of the line infrastructure object. corresponding to degree of the initial sample For the last 40 years, laser uranium sepa- (0) 훽 2+ = 0:00454. In the 41 experiments uranyl rations have been investigated for the industrial UO2 nitrate was enriched with isotope 235U, as we processes [10]. Unfortunately, these investiga- see 41 dots above the line corresponding to de- tions haven’t resulted in the commercial ura- (0) gree 훽 2+ = 0:00454. nium enrichment technology. UO2 It follows from work [9] that enrichment 4 Figure 2: Values of the degree of enriched 훼 in isotope 235U from the 65 experiments (for each of value showed confidence interval with " = ±0:00035): degree of depleted of the initial uranyl nitrate sample 훽 = 0:00454 (1), and degrees of enriched (see formula (1)) regenerated uranyl nitrate (2). Next, from papers [11, 12] follows that the studying. Authors are studying kinetic prop- MIE method of uranium isotopes separation erties ions, and stability of hydrate complexes has a maximum enrichment factor except for with ions in water solutions. centrifugal isotopes separation methods. The authors cordially thank Academician As of now, authors of the presented article of the NAS of Ukraine V. G. Baryakhtar for his are studying process of the uranium isotopes permanent attention and numerous discussions. separation in the uranium oxides from natural We are also grateful to our coauthors Cor- samples. These processes of uranium isotopes responding Member of the NAS of Ukraine separation have been induced MIE. R. Ya. Belevtsev, and Professor V. V. Dolin. We The isotope separation 235U from 238U in thank also Professor N. P. Malomuzh for the the photoinduced reaction uranyl nitrate with fruitful discussions of the results obtained. MIE in the water solutions demand further [1] G.T. Evans, R.G. Lawler, Molecular Physics [3] E.V. Sobotovich, I.V. Florinsky, O.B. Lysenko, 30, 1085 (1975). D.M. Grodzinsky, Man and the Geosphere [2] A.L. Buchachenko, E.M. Galimov, G.A. Niki- (Nova Science Publishers, New York, 2010). forov, Dokl. Acad. Sci. USSR 228, 379 (1976). [4] A.L. Buchachenko, R.G. Lawler, Accounts of 5 Chemical Research 50, 877 (2017). vich, V.D. Borman, A.V. Tikhomirov, The the- [5] A.L. Buchachenko, Magnetic isotope effect ory of cascades for separation of binary and in chemistry and biochemistry (Nova Science multicomponent isotope mixes (National Re- Publishers, New York, 2009). search Nuclear University MEPhI’, Moscow, [6] O. B. Lysenko, V.V. Radchuk, Y. L. Zab- 2011) [in Russian]. ulonov, V.B. Shatilo, Yu.N. Demikhov, [11] O.B. Lysenko, V.V. Radchuk, R.Y. Belevtsev, J.Phys.Chem. Biophys 6, 2161 (2016). I.V. Zhyganiuk, A.V. Zubko, in Proc. of the [7] N.A. Skul’skii, O.B. Lysenko, 15th International Research and Application Yu.N. Demikhov, and E.V.
Recommended publications
  • Extraction Processing of Concentrated Solutions of Uranyl Nitrate with High Impurities Content V.M
    View metadata, citation and similar papers at core.ac.uk brought to you by CORE provided by Electronic archive of Tomsk Polytechnic University Сhemistry UDC 546.791.02.238:66.061.51 EXTRACTION PROCESSING OF CONCENTRATED SOLUTIONS OF URANYL NITRATE WITH HIGH IMPURITIES CONTENT V.M. Korotkevich, V.V.Lazarchuck, T.G. Shikerun, V.I. Shamin, N.A. Mikhailova, F.A. Dorda Federal Unitary Enterprise Siberian Group of Chemical Enterprises, Seversk Еmail: [email protected] Process flowsheet of recycling uranium concentrated solutions with its purification from insoluble impurities of iron, silicon, molybde num, calcium oxides and hydroxides and soluble impurities with application of centrifugal extractors cascade has been developed and suggested for commercial introduction. The process was carried out at extractant saturation (30 % tributyl phosphate in hydrocarbon diluent) in extraction assembly lower than a limiting level (85...95 g/l) and in wash assembly – at limiting saturation (up to 120 g/l). As a result the waste uranium content in watertail solutions 0,01...0,04 g/l and minimal content of impurities in reextractors is provided. Perspective program on development of nuclear technology are also: reliability of hermetization, possi power engineering proposes to involve wide range of raw bility of remote service, resistance to corrosive attack of materials from uranium ores to secondary uranium ma structural materials, duration of overhaul period etc. terials into processing at atomic enterprises. In this case In Russia the centrifugal extractor of ECТseries the problem of reprocessing concentrated uranium so with continuous extraction of solid phase [3], which may lutions with high impurity content occurs.
    [Show full text]
  • Nitrate (UO2 (NO)) 4
    July 7, 1970 H. VETZKE ETA 3,519,403 METHOD FOR THE PREPARATION OF URANIUM DIOXIDE POWDER (UO) WITH GOOD PRESSING AND SINTERING PROPERTIES FROM URANIUM HEXAFLUORIDE (UF) OR AQUEOUS SOLUTIONS OF URANYL Fied Dec. 18, 1967 NiTRATE (UO2 (NO)) 4. Sheets-Sheet l mixer nozzles --race to fitter Fig.1 Schematic drawing of a batch process for the precipitation of AUC. July 7, 1970 H. VETZKE EA 3,519,403 METHOD FOR THE PREPARATION OF URANIUM DIOXIDE POWDER (UO) WITH GOOD PRESSING AND SINTERING PROPERTIES FROM RANIUM HEXAFLUORIDE (UF) OR AQUEOUS SOLUTIONS OF URANYL Filed Dec. 8, 1967 NiTRATE (UO2 (NO)) 4. Sheets-Sheet 3. mixer nozzles UF6 Of U02 (NO3)2ad tC92--X Ex-Ns / to filter cooling precipitation Vessel vessel Fig. 2 Schematic drawing of a continuous process for the precipitation of AUC July 7, 1970 H, VETZKE ETAL 3,519,403 METHOD FOR THE PREPARATION OF URANIUM DIOXIDE POWDER (UO) WITH GOOD PRESSING AND SINTERING PROPERTIES FROM URANIUM HEXAFLUORIDE (UF) OR AQUEOUS SOLUTIONS OF URANYL Filed Dec. 18, 1967 NiTRATE (UO (NO)2) 4. Sheets-Sheet 3 Off gas Off gas 487\m Nx UO2 powder XXX.& X.X S& steam / H2 Fig. 3 Ot Schematic drawing of a fluidized bed furnace for the reduction of AUC to U02, July 7, 1970 H. VEZKE ETAL 3,519,403 METHOD FOR THE PREPARATION OF URANIUM DIOXIDE POWDER (UO) WITH GOOD PRESSING AND SINTERING PROPERTIES FROM URANIUM HEXAFLUORIDE (UF) OR AQUEOUS SOLUTIONS OF URANYL NITRATE (UO2 (NO)a) Filed Dec. 18, 1967 4. Sheets-Sheet 1 -- Offgas Step 1: Decomposition, reduction and pyrohydrolysis i Step 2: Pyrohydrolysis Step 3: Controlled oxidation an o- are as an un- Fig.
    [Show full text]
  • United States Pmao" ICC Patented June 30, '1959 1 2 Adsorption on Manganese Dioxide, but It May on the 2,892,677 Other Hand He Left in the Solution
    r. 2,892,677 United States Pmao" ICC Patented June 30, '1959 1 2 adsorption on manganese dioxide, but it may on the 2,892,677 other hand he left in the solution. If it is removed, a certain amount of manganese nitrate is formed from the ' SEPARATION OF URANIUM FROM THORIUM manganese dioxide in the solution and this nitrate reacts AND PROTACTINIUM with the sodium diethyldithiocarbamate to give manga William Kenneth Rodgerson Musgrave, Durham, Eng ' nese diethyldithiocarbamate, which must subsequently be land, assignor, by mesne assignments, to the United separated from the uranium. ,, . .States of America as represented by the United States Whether or not the protactinium has been removed, Atomic Energy Commission the solution is brought to a pH of between 2 and 3, for No Drawing. Application November 27, 1946 10 example by the addition of ammonia. The sodium di Serial No. 712,722 ethyldithiocarbamate is then dissolved in a solvent in which the subsequently formed uranyl diethyldithiocar '8 Claims. (Cl. 23—14.5) bamate is also soluble. Such a solvent is, for example, amyl acetate or methyl isobutyl ketone, the former being This invention relates to the separation of uranium 15 preferable for the reasons which will be indicated below. from thorium and protactinium. A mixture of these The sodium diethyldithiocarbamate is dissolved in amyl elements is obtained, for example, as the result of irradia acetate to form a solution containing 0.25% of the tion by neutrons of so-called thorium carbonate, which former, and this solution is then shaken up with the is a mixture of thorium oxide and thorium carbonate.
    [Show full text]
  • Solvent Extraction of Uranium with Acetylacetone and Tri-N-Butyl
    DAEHAN HWAHAK HWOEJEE (Journal of the Korean Chemical Society) Vol. 24, No. 3, 1980 Printed in the Republic of Korea 아세 틸아세톤과 트리부틸인산의 도데칸용액 에 의한 우라늄의 용매추출 裴奎善-鄰奇碩 韓國核燃料開發公團 (1980. 2. 27 接受 ) Solvent Extraction of Uranium with Acetylacetone and Tri-n-Butyl Phosphate in “-Dodecane Kyu Sun Bai and Key Suck Jung Korea Nuclear Fuel Development Institute, Daeduck 300-32, Korea (Received Feb. 27, 1980) 요 악 . 도데칸에 녹인 아세틸아세톤과 트리부틸인산으로 묽은 질산우라닐수용액에서 우라늄 (VI) 을 추출했다 . pHl 이상에서 이 혼합추출제의 상승적 효과가 관측되었다 . 추출되는 화학종은 1:2:1 및 1:2:2 우라닐 -아세털 아세톤 -트리부털 인산착물이다 . 이들 반응의 추출정수들을 측정하였다 . ABSTRACT. Uranium (VI) was extracted from dilute aqueous solutions of uranyl nitrate with acetylacetone and tri-n-butyl phosphate in n-dodecane. Synergistic effect was observed with the mixed reagents above pH 1, The species extracted are the 1:2:1 and the 1:2:2 uranyl-AA-TBP complexes. The extraction constants for these reactions have been determined. by crystallization of the salt as UO2(NO3)2 INTRODUCTION •6H2O. HAA and TBP were dissolved in do­ Acetylacetone (HAA) is a simple -diketone. decane and uranyl nitrate in water. Equal A weak acid with pKa=8. 2% HAA has long volumes of organic and aqueous phases were been used as a chelating agent for many equilibrated in 100 mZ separatory funnels by metals.2 It is quite soluble in water and its vigorous shaking for several minutes. Equili­ brium temperature was 25 °C or ambient. pH distribution coefficient is E=5. 95 for benzene/ water system.3 Because of its solubility in measurements were made by using a Corning water, HAA has not been so widely used as, Model 130 pH meter.
    [Show full text]
  • Material Safety Data Sheet
    SAFETY DATA SHEET URANYL NITRATE SOLUTION SECTION 1: CHEMICAL PRODUCT & COMPANY IDENTIFICATION New Brunswick Laboratory U.S. Department of Energy 9800 South Cass Avenue Argonne, IL 60439 1-630-252-CRMS (2767) Emergency Phone Numbers: 1-630-252-6130 or 1-630-252-5731 Chemical Name: Uranyl Nitrate Solution, UO2(NO3)2 Other Identifiers: Certified Reference Material (CRM) standard or Safeguards Measurement Evaluation (SME) sample Use and Restrictions: This material is prepared for use as a standard or in inter-laboratory comparison programs at analytical laboratories, which routinely handle uranium and/or plutonium. NBL expects that recipients of their material are in compliance with 29 CFR 1910.1200(h) which requires employers to provide employees with effective information and training on hazardous chemicals in their work area. SECTION 2: HAZARDS IDENTIFICATION OSHA HAZARDS: Skin Corrosion/Irritation Category 1B. Serious Eye Damage/Irritation Category 1 TARGET ORGANS: Skin, Eyes, Kidneys. GHS Label elements, including precautionary statements Signal Word: DANGER Pictogram: Page 1 of 12 Hazard Statement(s) H314 Causes severe skin burns and eye damage H373 May cause damage to organs through prolonged or repeated exposure. H411 Toxic to aquatic life with long lasting effects. Precautionary statement(s) P260 Do not breathe dust/ fume/ gas/ mist/ vapors/ spray. P262 Do not get in eyes, on skin, or on clothing. P264 Wash skin thoroughly after handling. P273 Avoid release to the environment. P280 Wear protective gloves/protective clothing/eye protection/face protection P310 Immediately call a POISON CENTER or doctor/ physician if swallowed or inhaled. Other Hazard(s): Radioactive NFPA RATINGS (SCALE 0-4): Health=3 Fire=0 Reactivity=0 Special Hazard= OX SECTION 3: COMPOSITION/INFORMATION ON INGREDIENTS Chemical Name: Uranyl Nitrate Solution Common Names/Synonyms: CRM U045; CRM 135; CRM 145; CRM 145-B; CRM U930-D; Safeguards Measurement Evaluation (SME) Low Enrichment, Normal Enrichment, or High Enrichment Solutions; Uranyl Nitrate in Nitric Acid Solution.
    [Show full text]
  • Uranyl Nitrate, 1%
    Uranyl Nitrate, 1% 1. Identification Product Name: Uranyl Nitrate, 1% Item #: DI0103014, DI0103029, SKC1048-250, SKC1048-500 Web SDS: S231 Synonyms: N/A Recommended Use: Special Stains Restrictions on Use: N/A Manufacturer: In Case of Emergency: BBC Biochemical Chemtrec US 1-800-424-9300 409 Eleanor Lane, Chemtrec International 703-527-3887 Mount Vernon, WA 98273 1-800-635-4477 2. Hazards Identification OSHA Hazard Classification(s): Acute Toxicity - Oral - Category 4 Acute Toxicity - Inhalation - Category 4 Signal Word: Warning Hazard Statement(s): Harmful if swallowed. Harmful if inhaled. Pictogram(s): Precautionary Statement(s): Prevention: Wash body thoroughly after handling. Do not eat, drink or smoke when using this product. Avoid breathing dust, vapors. Use only outdoors or in a well-ventilated area. Response: If swallowed: Call a doctor if you feel unwell. Rinse mouth. If inhaled: Remove person to fresh air and keep comfortable for breathing. Call a doctor if you feel unwell. Storage: N/A Disposal: Dispose of contents/container in accordance with local regulations. Descriptions of Hazards not otherwise classified: N/A Percent of mixture with unknown acute toxicity: N/A 3. Composition and Information on Ingredients Chemical Name Common Name CAS # Concentration % Uranyl Nitrate 13520-83-7 1 Water 7732-18-5 99 4. First Aid Measures Eye Contact: If in eyes: Rinse cautiously with water for several minutes. Remove contact lenses, if present and easy to do. Continue rinsing. If eye irritation persists: Get medical advice/attention. Skin Contact: If on skin (or hair): Take off immediately all contaminated clothing and wash before reuse.
    [Show full text]
  • Physcio-Chemical Studies on the Systems Uranyl Nitrate Organic Solvent
    Durham E-Theses Physcio-chemical studies on the systems uranyl nitrate organic solvent - water Mathieson A. R., How to cite: Mathieson A. R., (1951) Physcio-chemical studies on the systems uranyl nitrate organic solvent - water, Durham theses, Durham University. Available at Durham E-Theses Online: http://etheses.dur.ac.uk/9766/ Use policy The full-text may be used and/or reproduced, and given to third parties in any format or medium, without prior permission or charge, for personal research or study, educational, or not-for-prot purposes provided that: • a full bibliographic reference is made to the original source • a link is made to the metadata record in Durham E-Theses • the full-text is not changed in any way The full-text must not be sold in any format or medium without the formal permission of the copyright holders. Please consult the full Durham E-Theses policy for further details. Academic Support Oce, Durham University, University Oce, Old Elvet, Durham DH1 3HP e-mail: [email protected] Tel: +44 0191 334 6107 http://etheses.dur.ac.uk PSYSIC0-CH3MICAL STUDIES OH THE SYSTEMS DEAUTL 1TITRATE - ORGANIC SOLVENT - WATER A.R. Mathieson, B.Sc.(Dunelm), A.R.I.C. Thesis presented for the degree of M. Sc. in Pure Science of the University of Durham, August 1951 The experimental work described in this thesis was performed at the Atomic Energy Research Establishment, Harwell, during the period November 1947 - December 1949* The results have already been published elsewhere: Mathieson "Stability of Complexes of Uranyl Nitrate with Ketones and Ethers", J.
    [Show full text]
  • Analysis of Mo Production Capacity in Uranyl Nitrate Aqueous
    A. Isnaeni,Atom atIndonesia al., / Atom Vol. Indonesia 40 No. 1 Vol.(2014) 40 40No. - 143 (2014) Analysis of 99Mo Production Capacity in Uranyl Nitrate Aqueous Homogeneous Reactor using ORIGEN and MCNP A. Isnaeni*, M.S. Aljohani, T.G. Aboalfaraj and S.I. Bhuiyan Nuclear Engineering Department, King Abdulaziz University P.O. Box 80240 Jeddah, Kingdom of Saudi Arabia A R T I C L E I N F O A B S T R A C T Article history: 99mTc is a very useful radioisotope in medical diagnostic procedure. 99mTc is Received 11 January 2014 produced from 99Mo decay. Currently, most of 99Mo is produced by irradiating 235U Received in revised form 18 February 2014 in the nuclear reactor. 99Mo mostly results from the fission reaction of 235U targets Accepted 28 February 2014 with a fission yield about 6.1%. A small additional amount is created from 98Mo 99 neutron activation. Actually Mo is also created in the reactor fuel, but usually we Keywords: 99 do not extract it. The fuel will become spent fuel which is a highly radioactive Mo waste. 99Mo production system in the aqueous homogeneous reactor offers a better Uranyl nitrate method, because all of the 99Mo can be extracted from the fuel solution. Fresh Homogeneous reactor reactor fuel solution consists of uranyl nitrate dissolved in water. There is no MCNP separation of target and fuel in an aqueous homogeneous reactor where target and ORIGEN fuel become one liquid solution, and there is no spent fuel generated from this reactor. Simulation of the extraction process is performed while reactor in operation (without reactor shutdown).
    [Show full text]
  • Uranyl Nitrate Hazard Summary Identification
    Common Name: URANYL NITRATE CAS Number: 10102-06-4 RTK Substance number: 1978 DOT Number: UN 2981 (Solid) Date: April 2000 ----------------------------------------------------------------------- ----------------------------------------------------------------------- HAZARD SUMMARY * Uranyl Nitrate can affect you when breathed in and may * If you think you are experiencing any work-related health be absorbed through the skin. problems, see a doctor trained to recognize occupational * Contact can irritate and burn the skin and eyes with diseases. Take this Fact Sheet with you. possible eye damage. * Breathing Uranyl Nitrate can irritate the nose, throat and WORKPLACE EXPOSURE LIMITS lungs causing coughing, wheezing and/or shortness of The following exposure limits are for soluble Uranium breath. compounds (measured as Uranium): * High exposures to Uranyl Nitrate can cause nausea, vomiting, muscle weakness, and convulsions. OSHA: The legal airborne permissible exposure limit * Uranyl Nitrate may damage the liver and kidneys. (PEL) is 0.05 mg/m3 averaged over an 8-hour * Repeated exposure to Uranyl Nitrate may affect the brain. workshift. * CONSULT THE NEW JERSEY DEPARTMENT OF HEALTH AND SENIOR SERVICES HAZARDOUS NIOSH: The recommended airborne exposure limit is SUBSTANCE FACT SHEET ON URANIUM. 0.05 mg/m3 averaged over a 10-hour workshift. IDENTIFICATION ACGIH: The recommended airborne exposure limit is Uranyl Nitrate is a pale yellow, radioactive solid with no 0.2 mg/m3 averaged over an 8-hour workshift odor. It is used in photographic processes, glazing ceramics, and 0.6 mg/m3 as a STEL (short term exposure and radiation shielding. limit). REASON FOR CITATION * The above exposure limits are for air levels only. When * Uranyl Nitrate is on the Hazardous Substance List skin contact also occurs, you may be overexposed, even because it is regulated by OSHA and cited by ACGIH, though air levels are less than the limits listed above.
    [Show full text]
  • Ammonium Diuranate' Prepared from Uranium Hexa¯Uoride J.A
    L Journal of Alloys and Compounds 323±324 (2001) 838±841 www.elsevier.com/locate/jallcom Recovery of uranium from the ®ltrate of `ammonium diuranate' prepared from uranium hexa¯uoride J.A. Seneda* , F.F. Figueiredo, A. Abrao,Ä F.M.S. Carvalho, E.U.C. Frajndlich Environmental and Chemical Center, Instituto de Pesquisas Energeticas e Nucleares, Trav.R, 400, SaoÄ Paulo, CEP 05508-900, Brazil Abstract The hydrolysis of uranium hexa¯uoride and its conversion to `ammonium diuranate' yields an alkaline solution containing ammonium ¯uoride and low concentrations of uranium. The recovery of the uranium has the advantage of saving this valuable metal and the avoidance of unacceptable discarding the above mentioned solution to the environment. The recovery of uranium(VI) is based on its complex with the excess of ¯uoride in the solution and its adsorption on to an anionic ion-exchange resin. The `ammonium diuranate' ®ltrate has an approximate concentration of 130 mg l21 of uranium and 20 g l21 of ammonium ¯uoride. An effective separation and recovery of the uranyl ¯uoride was achieved by choosing a suitable pH and ¯ow rate of the uranium-bearing solution on to the resin column. The ef¯uent ammonium ¯uoride will be recovered as well. Uranium ¯uoride adsorbed by the ion-exchanger is then transformed into the corresponding uranyl tricarbonate complex by percolation of a dilute ammonium carbonate solution. Finally, the free ¯uoride uranium carbonate is eluted from the resin with a more concentrate ammonium carbonate solution. The eluate now can be storage to be precipitated as ammonium uranyl carbonate (AUC).
    [Show full text]
  • 1% Uranyl Nitrate
    Page 1/8 SAFETY DATA SHEET In Accordance with ISO/DIS 11014 Review Date 04/06/2015 Revision Date 08/09/2012 1 Identification of the Substance/Mixture and Company Product Name: 1% Uranyl Nitrate MSDS Code: SSAHUNI1 Product Description: Laboratory Reagent Manufacturer/Supplier: American MasterTech 1330 Thurman Street Lodi, CA 95240 USA (800) 860-4073 European Authorized Representative: Emergo Europe Moleensraat 15 2513 BH The Hague, The Netherlands Emergency Telephone Number: Infotrac (800) 535-5053 (24 hours) - International (011) 352-323-3500 2 Hazards Identification Classification of the substance or mixture GHS07 Acute Tox. 4 H302 Harmful if swallowed. Acute Tox. 5 H333 May be harmful if inhaled. Classification according to Directive 67/548/EEC or Directive 1999/45/EC T; Toxic R23/25: Toxic by inhalation and if swallowed. R33: Danger of cumulative effects. Information concerning particular hazards for human and environment: The product has to be labelled due to the calculation procedure of international guidelines. Classification system: The classification was made according to the latest editions of international substances lists, and expanded upon from company and literature data. Label elements GHS label elements The product is classified and labeled according to the Globally Harmonized System (GHS). Hazard pictograms GHS07 Signal word Warning USA 34.2.6 Page 2/8 SAFETY DATA SHEET In Accordance with ISO/DIS 11014 Review Date 04/06/2015 Revision Date 08/09/2012 Product Name: 1% Uranyl Nitrate Hazard-determining components of labeling: Uranylnitrat-Hexahydrat Hazard statements Harmful if swallowed. May be harmful if inhaled. Precautionary statements If medical advice is needed, have product container or label at hand.
    [Show full text]
  • Experience with a Uranyl Nitrate/Uranium Dioxide Conversion Pilot Plant
    ENEA-RT/COMB/84/9 L. Arcuri, L. Pietrelli (ENEA-Dipartimento Ciclo del Combustibile, Casaccia) C. Rizzello (SN1A-TECH1NT) EXPERIENCE WITH A URANYL NITRATE —- URANIUM DIOXIDE CONVERSION PILOT PLANT. ^ Summary — A plant for the precipitation of sinterable nuclear grade UO. powders is described in this report. The plant lias been designed, built and set up by SMA TECH1NT. ENEA has been involved in the job as nuclear consultant. I Main process steps are: dissolution of U02 powder or sintered U02 pellets, udjutment of uranyl nitrate solutions, precipitation of uranium peroxide by means of hydrogen perox­ ide, centrifugation of the precipitate, drying, calcination and reduction to uranium diox­ ide. The report is divided in two main sections: the process description and the "hottest" report. Some laboratory data on precipitation of ammonium diuranate by means of NH.OH, are also reported. ElSEk COMITATO NAZIONALE PER LA RICERCA E PER LO SVILUPPO DELL'ENERGIA NUCLEARE E DELLE ENERGIE ALTERNATIVE L ARCURI, L PIETRELLI, C. RIZZELLO EXPERIENCE WITH A URANYL NITRATE — URANIUM DIOXIDE CONVERSION PILOT PLANT RT/COMB/84/9 Testo pervenuto in ottobre 1984 I contenuti tecnico-scientifici dei rapporti tecnici dell'Enea rispecchiano l'opinione degli autori e non necessariamente quella dell'ente INDEX 1. INTRODUCTION 2. DESCRIPTION OF THE PROCESS 2.1. DISSOLUTION 2.2. ADJUSTMENT 2.3. PRECIPITATION 2.4. CENTRIFUGATION 2.5. DRYING 2.6. CALCINATION, REDUCTION AND PASSIVATION 2.7. ANALYTICAL CHEMISTRY ASPECTS 3. TECHNICAL REPORT ON "HOT TEST" 3.1. POWDER DISSOLUTION 3.2. PELLETS DISSOLUTION 3.3. ADJUSTMENT AND PRECIPITATION 3.4. CENTRIFUGATION AND DRYING 3.5.
    [Show full text]