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Sample records for actinium 235

  1. Neutron-Induced Fission of Actinium-227, Protactinium-231 and Neptunium-237: Mass Distribution

    Results of radiochemical studies on the mass distribution in the neutron-induced fission of actinium-227, protactinium-231 and neptunium-237 have been presented. This work has been carried out as part of a programme to determine the mass distribution in the fission of heavy elements as a function of Z and A. All irradiations have been carried out in the core of the swimming-pool type reactor APSARA with cadmium shielding wherever necessary. Relative yields of several fission product nuclides have been obtained by a method involving a comparison of the fission product activities from the respective targets with those formed from uranium-235 simultaneously irradiated. Thermal-neutron fission yields of uranium-235 have been assumed. These results indicate a predominantly asymmetric mass distribution in all the three cases, and also a distinct though small symmetric peak in the case of actinium-227. (author)

  2. ADJ 235 Tutorials / adj235dotcom

    munna9

    2015-01-01

    ADJ 235 Entire Course (UOP)   For more course tutorials visit www.adj235.com   ADJ 235 Week 1 Checkpoint Legalizing Morality ADJ 235 Week 1 DQ 1 and DQ 2 ADJ 235 Week 2 Checkpoint Interpretation of Ethical Systems ADJ 235 Week 2 Assignment Deontological Versus Teleological Ethical Systems ADJ 235 Week 3 Checkpoint Undercover Operations ADJ 235 Week 3 DQ 1 and DQ 2 ADJ 235 Week 4 Checkpoint Law Enforcement Code of Ethics ADJ 235 Week 4 ...

  3. Extraction of actinium with di-(2-ethylhexyl)phosphoric acid from hydrochloric and nitric acid solutions

    The extraction of actinium with HDEHP from Cl- and NO3- systems has been investigated. It was found that extraction of actinium from HCl solutions is much better than from HNO3 solutions. Stability constants of actinium complexes Ac(X-)+2 with Cl- and NO3- ligands were determined. Our results show that the actinium formed less stable complexes with Cl- than with NO3- ligands. 5 refs., 3 figs., 1 tab. (author)

  4. The sorption of polonium, actinium and protactinium onto geological materials

    This paper describes a combined experimental and modeling program of generic sorption studies to increase confidence in the performance assessment for a potential high-level radioactive waste repository in Japan. The sorption of polonium, actinium and protactinium onto geological materials has been investigated. Sorption of these radioelements onto bentonite, tuff and granodiorite from equilibrated de-ionized water was studied under reducing conditions at room temperature. In addition, the sorption of actinium and protactinium was investigated at 60 C. Thermodynamic chemical modeling was carried out to aid interpretation of the results

  5. Separation of Actinium 227 from the uranium minerals

    The purpose of this work was to separate Actinium 227, whose content is 18%, from the mineral carnotite found in Gomez Chihuahua mountain range in Mexico. The mineral before processing is is pre-concentrated and passed, first through anionic exchange resins, later the eluate obtained is passed through cationic resins. The resins were 20-50 MESH QOWEX and 100-200 MESH 50 X 8-20 in some cased 200-400 MESH AG 50W-X8, 1X8 in other cases. The eluates from the ionic exchange were electrodeposited on stainless steel polished disc cathode and platinum electrode as anode; under a current ODF 10mA for 2.5 to 5 hours and of 100mA for .5 of an hour. it was possible to identify the Actinium 227 by means of its descendents, TH-227 and RA-223, through alpha spectroscopy. Due to the radiochemical purity which the electro deposits were obtained the Actinium 227 was low and was not quantitatively determined. A large majority of the members of the natural radioactive series 3 were identified and even alpha energies reported in the literature with very low percentages of non-identified emissions were observed. We conclude that a more precise study is needed concerning ionic exchange and electrodeposit to obtain an Actinium 227 of radiochemical purity. (Author)

  6. Spectroscopic and computational investigation of actinium coordination chemistry.

    Ferrier, Maryline G; Batista, Enrique R; Berg, John M; Birnbaum, Eva R; Cross, Justin N; Engle, Jonathan W; La Pierre, Henry S; Kozimor, Stosh A; Lezama Pacheco, Juan S; Stein, Benjamin W; Stieber, S Chantal E; Wilson, Justin J

    2016-01-01

    Actinium-225 is a promising isotope for targeted-α therapy. Unfortunately, progress in developing chelators for medicinal applications has been hindered by a limited understanding of actinium chemistry. This knowledge gap is primarily associated with handling actinium, as it is highly radioactive and in short supply. Hence, Ac(III) reactivity is often inferred from the lanthanides and minor actinides (that is, Am, Cm), with limited success. Here we overcome these challenges and characterize actinium in HCl solutions using X-ray absorption spectroscopy and molecular dynamics density functional theory. The Ac-Cl and Ac-OH2O distances are measured to be 2.95(3) and 2.59(3) Å, respectively. The X-ray absorption spectroscopy comparisons between Ac(III) and Am(III) in HCl solutions indicate Ac(III) coordinates more inner-sphere Cl(1-) ligands (3.2±1.1) than Am(III) (0.8±0.3). These results imply diverse reactivity for the +3 actinides and highlight the unexpected and unique Ac(III) chemical behaviour. PMID:27531582

  7. Discovery of the actinium, thorium, protactinium, and uranium isotopes

    Fry, C; Thoennessen, M

    2012-01-01

    Currently, 31 actinium, 31 thorium, 28 protactinium, and 23 uranium isotopes have so far been observed; the discovery of these isotopes is discussed. For each isotope a brief summary of the first refereed publication, including the production and identification method, is presented.

  8. Production of high-purity radium-223 from legacy actinium-beryllium neutron sources.

    Soderquist, Chuck Z; McNamara, Bruce K; Fisher, Darrell R

    2012-07-01

    Radium-223 is a short-lived alpha-particle-emitting radionuclide with potential applications in cancer treatment. Research to develop new radiopharmaceuticals employing (223)Ra has been hindered by poor availability due to the small quantities of parent actinium-227 available world-wide. The purpose of this study was to develop innovative and cost-effective methods to obtain high-purity (223)Ra from (227)Ac. We obtained (227)Ac from two surplus actinium-beryllium neutron generators. We retrieved the actinium/beryllium buttons from the sources and dissolved them in a sulfuric-nitric acid solution. A crude actinium solid was recovered from the solution by coprecipitation with thorium fluoride, leaving beryllium in solution. The crude actinium was purified to provide about 40 milligrams of actinium nitrate using anion exchange in methanol-water-nitric acid solution. The purified actinium was then used to generate high-purity (223)Ra. We extracted (223)Ra using anion exchange in a methanol-water-nitric acid solution. After the radium was separated, actinium and thorium were then eluted from the column and dried for interim storage. This single-pass separation produces high purity, carrier-free (223)Ra product, and does not disturb the (227)Ac/(227)Th equilibrium. A high purity, carrier-free (227)Th was also obtained from the actinium using a similar anion exchange in nitric acid. These methods enable efficient production of (223)Ra for research and new alpha-emitter radiopharmaceutical development. PMID:22697483

  9. ADJ 235 UOP Course Tutorial / adj235dotcom

    geenid

    2015-01-01

    ADJ 235 Entire Course (UOP) For more course tutorials visit www.adj235.com ADJ 235 Week 1 Checkpoint Legalizing Morality ADJ 235 Week 1 DQ 1 and DQ 2 ADJ 235 Week 2 Checkpoint Interpretation of Ethical Systems ADJ 235 Week 2 Assignment Deontological Versus Teleological Ethical Systems ADJ 235 Week 3 Checkpoint Undercover Operations ADJ 235 Week 3 DQ 1 and DQ 2 ADJ 235 Week 4 Checkpoint Law Enforcement Code of Ethics ADJ 235 Week 4 Assignment Law Enforce...

  10. ADJ 235 Courses Tutorial / indigohelp

    nesa

    2015-01-01

    ADJ 235 Week 1 Checkpoint Legalizing Morality ADJ 235 Week 1 DQ 1 and DQ 2 ADJ 235 Week 2 Checkpoint Interpretation of Ethical Systems ADJ 235 Week 2 Assignment Deontological Versus Teleological Ethical Systems ADJ 235 Week 3 Checkpoint Undercover Operations ADJ 235 Week 3 DQ 1 and DQ 2 ADJ 235 Week 4 Checkpoint Law Enforcement Code of Ethics ADJ 235 Week 4 Assignment Law Enforcement Deviance ADJ 235 Week 5 Checkpoint Attorneys Ethical Responsibilities ADJ ...

  11. Radium, thorium, and actinium extraction from seawater using an improved manganese-oxide-coated fiber

    Laboratory experiments were conducted to determine the efficiency with which improved manganese-oxide-coated acrylic fibers extract radium, thorium, and actinium from seawater. Tests were made using surface seawater spiked with 227Ac, 227Th and 223Ra. For sample volumes of approximately 30 liters and flow rates up to 0.5 liters per minute, radium and actinium are removed quantitatively. Approximately 80-95% of the thorium is removed under these same conditions. (Auth.)

  12. 31 CFR 540.315 - Uranium-235 (U235).

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Uranium-235 (U235). 540.315 Section... FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY HIGHLY ENRICHED URANIUM (HEU) AGREEMENT ASSETS CONTROL REGULATIONS General Definitions § 540.315 Uranium-235 (U235). The term uranium-235 or U235 means the...

  13. BUS 235 Course tutorial/ indigohelp

    SFVD

    2015-01-01

    For more classes visit www.indigohelp.com   BUS 235 Week 1 DQ 1 Marketing Trends BUS 235 Week 1 DQ 2 Customer Needs and Wants BUS 235 Week 2 DQ 1 Market Research BUS 235 Week 2 DQ 2 Customer Loyalty BUS 235 Week 3 DQ 1 Branding Debate BUS 235 Week 3 DQ 2 New Product Development BUS 235 Week 3 Assignment Retail Store (Walmart) BUS 235 Week 4 DQ 1 Price and Ethics BUS 235 Week 4 DQ 2 Service Marketing BUS 235 Week 5 DQ 1 Super Bowl Advertisin...

  14. ADJ 235 Courses/snaptutorial

    charles

    2015-01-01

    ­For more classes visits www.indigohelp.com                 ADJ 235 Week 1 Checkpoint Legalizing Morality ADJ 235 Week 1 DQ 1 and DQ 2 ADJ 235 Week 2 Checkpoint Interpretation of Ethical Systems ADJ 235 Week 2 Assignment Deontological Versus Teleological Ethical Systems ADJ 235 Week 3 Checkpoint Undercover Operations ADJ 235 Week 3 DQ 1 and DQ 2 ADJ 235 Week 4 Checkpoint Law Enforcement...

  15. Production of Actinium-225 via High Energy Proton Induced Spallation of Thorium-232

    The science of cancer research is currently expanding its use of alpha particle emitting radioisotopes. Coupled with the discovery and proliferation of molecular species that seek out and attach to tumors, new therapy and diagnostics are being developed to enhance the treatment of cancer and other diseases. This latest technology is commonly referred to as Alpha Immunotherapy (AIT). Actinium-225/Bismuth-213 is a parent/daughter alpha-emitting radioisotope pair that is highly sought after because of the potential for treating numerous diseases and its ability to be chemically compatible with many known and widely used carrier molecules (such as monoclonal antibodies and proteins/peptides). Unfortunately, the worldwide supply of actinium-225 is limited to about 1,000mCi annually and most of that is currently spoken for, thus limiting the ability of this radioisotope pair to enter into research and subsequently clinical trials. The route proposed herein utilizes high energy protons to produce actinium-225 via spallation of a thorium-232 target. As part of previous R and D efforts carried out at Argonne National Laboratory recently in support of the proposed US FRIB facility, it was shown that a very effective production mechanism for actinium-225 is spallation of thorium-232 by high energy proton beams. The base-line simulation for the production rate of actinium-225 by this reaction mechanism is 8E12 atoms per second at 200 MeV proton beam energy with 50 g/cm2 thorium target and 100 kW beam power. An irradiation of one actinium-225 half-life (10 days) produces ∼100 Ci of actinium-225. For a given beam current the reaction cross section increases slightly with energy to about 400 MeV and then decreases slightly for beam energies in the several GeV regime. The object of this effort is to refine the simulations at proton beam energies of 400 MeV and above up to about 8 GeV. Once completed, the simulations will be experimentally verified using 400 MeV and 8 GeV protons

  16. Production of Actinium-225 via High Energy Proton Induced Spallation of Thorium-232

    Harvey, James T.; Nolen, Jerry; Vandergrift, George; Gomes, Itacil; Kroc, Tom; Horwitz, Phil; McAlister, Dan; Bowers, Del; Sullivan, Vivian; Greene, John

    2011-12-30

    The science of cancer research is currently expanding its use of alpha particle emitting radioisotopes. Coupled with the discovery and proliferation of molecular species that seek out and attach to tumors, new therapy and diagnostics are being developed to enhance the treatment of cancer and other diseases. This latest technology is commonly referred to as Alpha Immunotherapy (AIT). Actinium-225/Bismuth-213 is a parent/daughter alpha-emitting radioisotope pair that is highly sought after because of the potential for treating numerous diseases and its ability to be chemically compatible with many known and widely used carrier molecules (such as monoclonal antibodies and proteins/peptides). Unfortunately, the worldwide supply of actinium-225 is limited to about 1,000mCi annually and most of that is currently spoken for, thus limiting the ability of this radioisotope pair to enter into research and subsequently clinical trials. The route proposed herein utilizes high energy protons to produce actinium-225 via spallation of a thorium-232 target. As part of previous R and D efforts carried out at Argonne National Laboratory recently in support of the proposed US FRIB facility, it was shown that a very effective production mechanism for actinium-225 is spallation of thorium-232 by high energy proton beams. The base-line simulation for the production rate of actinium-225 by this reaction mechanism is 8E12 atoms per second at 200 MeV proton beam energy with 50 g/cm2 thorium target and 100 kW beam power. An irradiation of one actinium-225 half-life (10 days) produces {approx}100 Ci of actinium-225. For a given beam current the reaction cross section increases slightly with energy to about 400 MeV and then decreases slightly for beam energies in the several GeV regime. The object of this effort is to refine the simulations at proton beam energies of 400 MeV and above up to about 8 GeV. Once completed, the simulations will be experimentally verified using 400 MeV and 8 Ge

  17. Comment: 235 [Taxonomy Icon

    Full Text Available koji mold Aspergillus oryzae Aspergillus_oryzae_L.png 235.png Osamu Mizutani (Tohoku University ... ing)) licensed under CC Attribution2.1 Japan 撮影: 水 谷治(東北大学(現 酒類総研)) Photo: Osamu Mizutani ...

  18. ADJ 235 UOP COURSE Tutorial/UOPHELP

    vasu

    2015-01-01

    ADJ 235 Week 1 Checkpoint Legalizing Morality ADJ 235 Week 1 DQ 1 and DQ 2 ADJ 235 Week 2 Checkpoint Interpretation of Ethical Systems ADJ 235 Week 2 Assignment Deontological Versus Teleological Ethical Systems ADJ 235 Week 3 Checkpoint Undercover Operations ADJ 235 Week 3 DQ 1 and DQ 2 ADJ 235 Week 4 Checkpoint Law Enforcement Code of Ethics ADJ 235 Week 4 Assignment Law Enforcement Deviance ADJ 235 Week 5 Checkpoint Attorneys Ethical Responsibilities ADJ ...

  19. A new method for the determination of low-level actinium-227 in geological samples

    We developed a new method for the determination of 227Ac in geological samples. The method uses extraction chromatographic techniques and alpha-spectrometry and is applicable for a range of natural matrices. Here we report on the procedure and results of the analysis of water (fresh and seawater) and rock samples. Water samples were acidified and rock samples underwent total dissolution via acid leaching. A DGA (N,N,N',N'-tetra-n-octyldiglycolamide) extraction chromatographic column was used for the separation of actinium. The actinium fraction was prepared for alpha spectrometric measurement via cerium fluoride micro-precipitation. Recoveries of actinium in water samples were 80 ± 8 % (number of analyses n = 14) and in rock samples 70 ± 12 % (n = 30). The minimum detectable activities (MDA) were 0.017-0.5 Bq kg-1 for both matrices. Rock sample 227Ac activities ranged from 0.17 to 8.3 Bq kg-1 and water sample activities ranged from below MDA values to 14 Bq kg-1of 227Ac. From the analysis of several standard rock and water samples with the method we found very good agreement between our results and certified values. (author)

  20. Analysis of the gamma spectra of the uranium, actinium, and thorium decay series

    Momeni, M.H.

    1981-09-01

    This report describes the identification of radionuclides in the uranium, actinium, and thorium series by analysis of gamma spectra in the energy range of 40 to 1400 keV. Energies and absolute efficiencies for each gamma line were measured by means of a high-resolution germanium detector and compared with those in the literature. A gamma spectroscopy method, which utilizes an on-line computer for deconvolution of spectra, search and identification of each line, and estimation of activity for each radionuclide, was used to analyze soil and uranium tailings, and ore.

  1. Analysis of the gamma spectra of the uranium, actinium, and thorium decay series

    This report describes the identification of radionuclides in the uranium, actinium, and thorium series by analysis of gamma spectra in the energy range of 40 to 1400 keV. Energies and absolute efficiencies for each gamma line were measured by means of a high-resolution germanium detector and compared with those in the literature. A gamma spectroscopy method, which utilizes an on-line computer for deconvolution of spectra, search and identification of each line, and estimation of activity for each radionuclide, was used to analyze soil and uranium tailings, and ore

  2. 32 CFR 235.5 - Responsibilities.

    2010-07-01

    ... 32 National Defense 2 2010-07-01 2010-07-01 false Responsibilities. 235.5 Section 235.5 National... SALE OR RENTAL OF SEXUALLY EXPLICIT MATERIAL ON DOD PROPERTY § 235.5 Responsibilities. (a) The... its responsibilities as set forth in § 235.6. (b) The Secretaries of the Military Departments...

  3. In-source laser spectroscopy developments at TRILIS—towards spectroscopy on actinium and scandium

    Resonance Ionization Laser Ion Sources (RILIS) have become a versatile tool for production and study of exotic nuclides at Isotope Separator On-Line (ISOL) facilities such as ISAC at TRIUMF. The recent development and addition of a grating tuned spectroscopy laser to the TRIUMF RILIS solid state laser system allows for wide range spectral scans to investigate atomic structures on short lived isotopes, e.g., those from the element actinium, produced in uranium targets at ISAC. In addition, development of new and improved laser ionization schemes for rare isotope production at ISAC is ongoing. Here spectroscopic studies on bound states, Rydberg states and autoionizing (AI) resonances on scandium using the existing off-line capabilities are reported. These results allowed to identify a suitable ionization scheme for scandium via excitation into an autoionizing state at 58,104 cm − 1 which has subsequently been used for ionization of on-line produced exotic scandium isotopes.

  4. 7 CFR 235.3 - Administration.

    2010-01-01

    ... programs in accordance with the applicable requirements of this part, 7 CFR parts 210, 215, 220, 225, 226... 7 Agriculture 4 2010-01-01 2010-01-01 false Administration. 235.3 Section 235.3 Agriculture... CHILD NUTRITION PROGRAMS STATE ADMINISTRATIVE EXPENSE FUNDS § 235.3 Administration. (a) Within...

  5. 32 CFR 235.7 - Information requirements.

    2010-07-01

    ... 32 National Defense 2 2010-07-01 2010-07-01 false Information requirements. 235.7 Section 235.7 National Defense Department of Defense (Continued) OFFICE OF THE SECRETARY OF DEFENSE (CONTINUED) MISCELLANEOUS SALE OR RENTAL OF SEXUALLY EXPLICIT MATERIAL ON DOD PROPERTY § 235.7 Information requirements....

  6. 45 CFR 235.110 - Fraud.

    2010-10-01

    ... 45 Public Welfare 2 2010-10-01 2010-10-01 false Fraud. 235.110 Section 235.110 Public Welfare... PROGRAMS § 235.110 Fraud. State plan requirements: A State plan under title I, IV-A, X, XIV, or XVI of the... criteria for identifying situations in which a question of fraud in the program may exist, and...

  7. 7 CFR 905.235 - Assessment rate.

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Assessment rate. 905.235 Section 905.235 Agriculture... TANGELOS GROWN IN FLORIDA Assessment Rates § 905.235 Assessment rate. On and after August 1, 2007, an assessment rate of $0.0072 per 4/5 bushel carton or equivalent is established for Florida citrus...

  8. 7 CFR 915.235 - Assessment rate.

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Assessment rate. 915.235 Section 915.235 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... Assessment Rates § 915.235 Assessment rate. On and after April 1, 2005, an assessment rate of $0.27 per...

  9. 7 CFR 906.235 - Assessment rate.

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Assessment rate. 906.235 Section 906.235 Agriculture... RIO GRANDE VALLEY IN TEXAS Rules and Regulations § 906.235 Assessment rate. On and after August 1, 2004, an assessment rate of $0.12 per 7/10-bushel carton or equivalent is established for oranges...

  10. 49 CFR 235.9 - Civil penalty.

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Civil penalty. 235.9 Section 235.9 Transportation... SIGNAL SYSTEM OR RELIEF FROM THE REQUIREMENTS OF PART 236 § 235.9 Civil penalty. Any person (an entity of... violates any requirement of this part or causes the violation of any such requirement is subject to a...

  11. 49 CFR 235.20 - Protests.

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Protests. 235.20 Section 235.20 Transportation... SIGNAL SYSTEM OR RELIEF FROM THE REQUIREMENTS OF PART 236 § 235.20 Protests. (a) A protest against the... concise statement of the interest of protestant in the proceeding. (b) Protests shall be filed with...

  12. origin of elements of the Uranium-235 family observed in the Ellez river near the EL-4 experimental nuclear reactor in dismantling (Monts d'Arree- Finistere department)

    In a previous study which concerned the catchment basin of the harbour of Brest, the A.C.R.O. put in evidence a marking by artificial radioelements around the power plant of Brennilis which can be imputed without ambiguities to the nuclear installation. It also put in evidence abnormalities concerning the natural radioactivity which justifies this new study. In the area of the Monts d'Arree, actinium 227 (227Ac), non born by its ascendents which are 235U and 231Pa is observed. This phenomenon is characterized by mass activities superior to these ones of 235U and able to reach these ones of 238U. Its presence corresponds with the drainage of the Ellez river since the former channel of radioactive effluents releases from the nuclear power plant EL-4 up to the reservoir Saint-Herblot situated 6 km downstream. The strongest values of radioactivity are registered near the disused power plant, at this place a relationship exists between the level of actinium 227 and this one of the artificial radioactivity as it exists a relationship with the decay products of radon exhaled from the subsoil (210Pb). But its presence is not limited to a part of the Ellez river, it is equally observed in terrestrial medium, in places in priori not influenced by the direct liquid effluents of the power plant. This place is situated at more than 4 km and without any connection with the Ellez waters. At this stage of the study, it is not possible to answer with certainty the question of the origin of this phenomenon. A new reorientation is considered indispensable to clarify definitively the origin of this unknown phenomenon in the scientific publications and the environmental monitoring. (N.C.)

  13. Developments towards in-gas-jet laser spectroscopy studies of actinium isotopes at LISOL

    Raeder, S.; Bastin, B.; Block, M.; Creemers, P.; Delahaye, P.; Ferrer, R.; Fléchard, X.; Franchoo, S.; Ghys, L.; Gaffney, L. P.; Granados, C.; Heinke, R.; Hijazi, L.; Huyse, M.; Kron, T.; Kudryavtsev, Yu.; Laatiaoui, M.; Lecesne, N.; Luton, F.; Moore, I. D.; Martinez, Y.; Mogilevskiy, E.; Naubereit, P.; Piot, J.; Rothe, S.; Savajols, H.; Sels, S.; Sonnenschein, V.; Traykov, E.; Van Beveren, C.; Van den Bergh, P.; Van Duppen, P.; Wendt, K.; Zadvornaya, A.

    2016-06-01

    To study exotic nuclides at the borders of stability with laser ionization and spectroscopy techniques, highest efficiencies in combination with a high spectral resolution are required. These usually opposing requirements are reconciled by applying the in-gas-laser ionization and spectroscopy (IGLIS) technique in the supersonic gas jet produced by a de Laval nozzle installed at the exit of the stopping gas cell. Carrying out laser ionization in the low-temperature and low density supersonic gas jet eliminates pressure broadening, which will significantly improve the spectral resolution. This article presents the required modifications at the Leuven Isotope Separator On-Line (LISOL) facility that are needed for the first on-line studies of in-gas-jet laser spectroscopy. Different geometries for the gas outlet and extraction ion guides have been tested for their performance regarding the acceptance of laser ionized species as well as for their differential pumping capacities. The specifications and performance of the temporarily installed high repetition rate laser system, including a narrow bandwidth injection-locked Ti:sapphire laser, are discussed and first preliminary results on neutron-deficient actinium isotopes are presented indicating the high capability of this novel technique.

  14. ADJ 235 uop course tutorial/uop help

    andor

    2015-01-01

     For more course tutorials visit www.uophelp.com     ADJ 235 Week 1 Checkpoint Legalizing Morality ADJ 235 Week 1 DQ 1 and DQ 2 ADJ 235 Week 2 Checkpoint Interpretation of Ethical Systems ADJ 235 Week 2 Assignment Deontological Versus Teleological Ethical Systems ADJ 235 Week 3 Checkpoint Undercover Operations ADJ 235 Week 3 DQ 1 and DQ 2 ADJ 235 Week 4 Checkpoint Law Enforcement Code of Ethics ADJ 235 Week 4 Assignment Law Enforcemen...

  15. Dicty_cDB: SLA235 [Dicty_cDB

    Full Text Available SL (Link to library) SLA235 (Link to dictyBase) - - - Contig-U16325-1 SLA235E (Link... to Original site) - - - - - - SLA235E 470 Show SLA235 Library SL (Link to library) Clone ID SLA235 (Link to...ycdb.biol.tsukuba.ac.jp/CSM/SL/SLA2-B/SLA235Q.Seq.d/ Representative seq. ID SLA23...5E (Link to Original site) Representative DNA sequence >SLA235 (SLA235Q) /CSM/SL/SLA2-B/SLA235Q.Seq.d/ CCAAA...GTTTTTAAAAAAAAAA AAAAAAATAATTATTAAATTTTTAAAATTATAAATAATAATCTTCTTATG sequence update 1997. 5. 7 Transla

  16. Recommended decay data for 235-neptunium

    An evaluation has been made of the decay of 235Np, a nuclide that has become popular for monitoring neptunium chemistry in the environment. Compared with other radioactive nuclides, 235Np produces few emissions that are suitable for quantitative analysis. A semi-theoretical study was undertaken, and it is recommended that four K-shell X rays are used to monitor 235Np. (U.K.)

  17. 50 CFR 600.235 - Financial disclosure.

    2010-10-01

    ... ADMINISTRATION, DEPARTMENT OF COMMERCE MAGNUSON-STEVENS ACT PROVISIONS Council Membership § 600.235 Financial... 50 Wildlife and Fisheries 8 2010-10-01 2010-10-01 false Financial disclosure. 600.235 Section 600.... Financial interest in harvesting, processing, or marketing (1) includes: (i) Stock, equity, or...

  18. 14 CFR 21.235 - Application.

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Application. 21.235 Section 21.235 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION AIRCRAFT CERTIFICATION... Administrator, to the Aircraft Certification Office for the area in which the manufacturer is located. (b)...

  19. 44 CFR 19.235 - Statutory amendments.

    2010-10-01

    ... 44 Emergency Management and Assistance 1 2010-10-01 2010-10-01 false Statutory amendments. 19.235 Section 19.235 Emergency Management and Assistance FEDERAL EMERGENCY MANAGEMENT AGENCY, DEPARTMENT OF... of factors related to the individual's personal appearance, poise, and talent. The pageant,...

  20. 24 CFR 235.206 - Substitute mortgagors.

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Substitute mortgagors. 235.206... MORTGAGE INSURANCE AND ASSISTANCE PAYMENTS FOR HOME OWNERSHIP AND PROJECT REHABILITATION Contract Rights and Obligations-Homes for Lower Income Families § 235.206 Substitute mortgagors. (a) Selling...

  1. 33 CFR 105.235 - Communications.

    2010-07-01

    ... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Communications. 105.235 Section... MARITIME SECURITY: FACILITIES Facility Security Requirements § 105.235 Communications. (a) The Facility... conditions at the facility. (b) Communication systems and procedures must allow effective and...

  2. 32 CFR 235.1 - Purpose.

    2010-07-01

    ... OF SEXUALLY EXPLICIT MATERIAL ON DOD PROPERTY § 235.1 Purpose. This part implements 10 U.S.C. 2489a... sexually explicit materials on property under the jurisdiction of the Department of Defense or by...

  3. 49 CFR 235.3 - Application.

    2010-10-01

    ... SIGNAL SYSTEM OR RELIEF FROM THE REQUIREMENTS OF PART 236 § 235.3 Application. (a) Except as provided in... part of the general railroad system of transportation. (b) This part does not apply to rail...

  4. Origin of elements of the Uranium-235 family observed in the Ellez river near the EL-4 experimental nuclear reactor in dismantling (Monts d'Arree- Finistere department); Origine des elements de la famille de l'uranium-235 observes dans la riviere Ellez a proximite du reacteur nucleaire experimental EL4 en cours de demantelement (Mont d'Arree - departement du Finistere). Resultats et premiers constats annee 2006

    NONE

    2006-07-01

    In a previous study which concerned the catchment basin of the harbour of Brest, the A.C.R.O. put in evidence a marking by artificial radioelements around the power plant of Brennilis which can be imputed without ambiguities to the nuclear installation. It also put in evidence abnormalities concerning the natural radioactivity which justifies this new study. In the area of the Monts d'Arree, actinium 227 ({sup 227}Ac), non born by its ascendents which are {sup 235}U and {sup 231}Pa is observed. This phenomenon is characterized by mass activities superior to these ones of {sup 235}U and able to reach these ones of {sup 238}U. Its presence corresponds with the drainage of the Ellez river since the former channel of radioactive effluents releases from the nuclear power plant EL-4 up to the reservoir Saint-Herblot situated 6 km downstream. The strongest values of radioactivity are registered near the disused power plant, at this place a relationship exists between the level of actinium 227 and this one of the artificial radioactivity as it exists a relationship with the decay products of radon exhaled from the subsoil ({sup 210}Pb). But its presence is not limited to a part of the Ellez river, it is equally observed in terrestrial medium, in places in priori not influenced by the direct liquid effluents of the power plant. This place is situated at more than 4 km and without any connection with the Ellez waters. At this stage of the study, it is not possible to answer with certainty the question of the origin of this phenomenon. A new reorientation is considered indispensable to clarify definitively the origin of this unknown phenomenon in the scientific publications and the environmental monitoring. (N.C.)

  5. Dicty_cDB: SSC235 [Dicty_cDB

    Full Text Available SS (Link to library) SSC235 (Link to dictyBase) - - - Contig-U16581-1 SSC235F (Link to Original site) SS...C235F 463 - - - - - - Show SSC235 Library SS (Link to library) Clone ID SSC235 (Link to...ycdb.biol.tsukuba.ac.jp/CSM/SS/SSC2-B/SSC235Q.Seq.d/ Representative seq. ID SSC23...5F (Link to Original site) Representative DNA sequence >SSC235 (SSC235Q) /CSM/SS/SSC2-B/SSC235Q.Seq.d/ ANTAA...pdate 1998. 8. 5 Translated Amino Acid sequence xk*kkkkkk*kki**vlkwysfnkkkkkttiisskkkiknkkkknkkk***aipwdleki

  6. 24 CFR 235.1234 - Term of assistance payment contract in connection with mortgages insured under section 235(r) of...

    2010-04-01

    ... certified by the mortgagee and shall continue until the contract is terminated pursuant to 24 CFR 235.375... pursuant to 24 CFR 235.375. The mortgagor will acknowledge receipt of a notice containing the expiration... in connection with mortgages insured under section 235(r) of the Act. 235.1234 Section...

  7. Decay scheme of the U235

    A study of the Th231 excited levels from the alpha decay of the U235, is carried out. The alpha particle spectrum was measured by means of a semiconductor counter spectrometer with an effective resolution of 18 keV. Nineteen new lines were identified. The gamma-ray spectrum was measured with thin samples of U235, free from decay products, and in such geometrical conditions, that most of the interference effects were eliminated. The gamma-gamma coincidence spectra have made easier a better knowledge of the transition between the several levels. (Author) 110 refs

  8. 46 CFR 108.235 - Construction.

    2010-10-01

    ... limit drop test in 14 CFR 29.725, or a load of not less than 75 percent of the helicopter maximum weight... GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) A-MOBILE OFFSHORE DRILLING UNITS DESIGN AND EQUIPMENT Construction and Arrangement Helicopter Facilities § 108.235 Construction. (a) Each helicopter deck must...

  9. 32 CFR 235.6 - Procedures.

    2010-07-01

    ... OF SEXUALLY EXPLICIT MATERIAL ON DOD PROPERTY § 235.6 Procedures. (a) The Board shall periodically... determine whether any such material is sexually explicit in accordance with this part. (b) If the Board... jurisdiction may be sexually explicit as defined herein, and such material is not addressed by the...

  10. 32 CFR 235.4 - Policy.

    2010-07-01

    ... OF SEXUALLY EXPLICIT MATERIAL ON DOD PROPERTY § 235.4 Policy. It is DoD policy that: (a) No sexually explicit material may be offered for sale or rental on property under the DoD jurisdiction, and no member..., shall offer for sale or rental any sexually explicit material. (b) Material shall not be deemed...

  11. 32 CFR 235.3 - Definitions.

    2010-07-01

    ... SALE OR RENTAL OF SEXUALLY EXPLICIT MATERIAL ON DOD PROPERTY § 235.3 Definitions. For the purpose of this part, the following definitions apply: Dominant theme. A theme of any material that is superior in... Exchanges, and ship stores. Sexually explicit material. Material, the dominant theme of which is...

  12. 21 CFR 514.235 - Judicial review.

    2010-04-01

    ... Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) ANIMAL DRUGS, FEEDS, AND RELATED PRODUCTS NEW ANIMAL DRUG APPLICATIONS Judicial Review § 514.235 Judicial review. (a... manufacturer or distributor of an identical, related, or similar drug product, as defined in § 310.6 of...

  13. The Coriolis attenuation problem in 235U

    A new version of the particle-rotor model, featuring diagonalization of a state-dependent pairing force and the full recoil term, has been applied to 235U. A significant improvement is obtained in the description of the Coriolis coupled K=5/2, 7/2 and 9/2 rotational bands. No ad hoc Coriolis attenuation factors are used. (orig.)

  14. Indirect NMR detection of 235U in gaseous uranium hexafluoride

    Ursu, I.; Demco, D.E.; Bogdan, M.; Fitori, P.; Darabont, A.

    1985-01-01

    The possibility to use nuclear magnetic resonance in indirect detection of the 235U nucleus in gaseous UF6 is discussed. The 19F absorption spectra linewidths in gaseous UF6 was investigated as a function of 235U enrichment, revealing a dependence on the isotope concentration. The 19F-235U indirect scalar coupling modulated by 235U quadrupole relaxation is the relaxation mechanism responsible for this enrichment effect.

  15. Photonuclear data evaluation of U235

    This report presents cross-sections calculation up to 130 MeV for U235. The photoabsorption process is described by the giant dipole resonance and quasi deuteron mechanisms. Neutron emission is treated within the preequilibrium and statistical models while fission is also calculated within this statistical approach using a double-humped fission barrier. The U235(γ,n), (γ,2n) and (γ,f) cross-sections are calculated with the TALYS-0.64 code using a coupled channels optical potential. Charges in level densities did not affect results significantly. Fission barrier heights and widths were modified to reproduce experimental data. Neither fission level densities nor other default fission parameters were changed. More calculations are needed in order to check cross-sections sensitivity to other level densities and fission models. (A.C.)

  16. 32 CFR 235.2 - Applicability and scope.

    2010-07-01

    ... 32 National Defense 2 2010-07-01 2010-07-01 false Applicability and scope. 235.2 Section 235.2 National Defense Department of Defense (Continued) OFFICE OF THE SECRETARY OF DEFENSE (CONTINUED) MISCELLANEOUS SALE OR RENTAL OF SEXUALLY EXPLICIT MATERIAL ON DOD PROPERTY § 235.2 Applicability and scope....

  17. 8 CFR 235.6 - Referral to immigration judge.

    2010-01-01

    ... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Referral to immigration judge. 235.6 Section 235.6 Aliens and Nationality DEPARTMENT OF HOMELAND SECURITY IMMIGRATION REGULATIONS INSPECTION OF PERSONS APPLYING FOR ADMISSION § 235.6 Referral to immigration judge. (a) Notice—(1) Referral by Form...

  18. 49 CFR 234.235 - Insulated rail joints.

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Insulated rail joints. 234.235 Section 234.235..., DEPARTMENT OF TRANSPORTATION GRADE CROSSING SIGNAL SYSTEM SAFETY AND STATE ACTION PLANS Maintenance, Inspection, and Testing Maintenance Standards § 234.235 Insulated rail joints. Each insulated rail joint...

  19. 49 CFR 192.235 - Preparation for welding.

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Preparation for welding. 192.235 Section 192.235... BY PIPELINE: MINIMUM FEDERAL SAFETY STANDARDS Welding of Steel in Pipelines § 192.235 Preparation for welding. Before beginning any welding, the welding surfaces must be clean and free of any material...

  20. Physical conditions in star forming regions around S235

    Kirsanova, Maria S; Sobolev, Andrej M; Henkel, Christian; Tsivilev, Alexander P

    2013-01-01

    Gas density and temperature in star forming regions around Sh2-235 are derived from ammonia line observations. This information is used to evaluate formation scenarios and to determine evolutionary stages of the young embedded clusters S235 East1, S235 East2, and S235 Central. We also estimate the gas mass in the embedded clusters and its ratio to the stellar mass. S235 East1 appears to be less evolved than S235 East2 and S235 Central. In S235 East1 the molecular gas mass exceeds that in the other clusters. Also, this cluster is more embedded in the parent gas cloud than the other two. Comparison with a theoretical model shows that the formation of these three clusters could have been stimulated by the expansion of the Sh2-235 HII region (hereafter S235) via a collect-and-collapse process, provided the density in the surrounding gas exceeds $3\\cdot10^3$ cm$^{-3}$, or via collapse of pre-existing clumps. The expansion of S235 cannot be responsible for star formation in the southern S235 A-B region. However, fo...

  1. Centrifuge for separation of enriched 235U

    The invention claim is for a centrifuge for enrichment of 235U characterized by: (1) a rotor provided with hollow upper and lower rotating shafts which serve, respectively, as a feed conduit for a light inert-gas/UF6-gas mixture and as a discharge conduit for the light inert gas, and provided with top and bottom end-plates having vents for discharging the 235U-enriched gas and 235U-depleted gas in equal amounts; (2) a fixed outer jacket which accomodates the freely rotating rotor in such a manner as to form annular slits between the shoulders of the rotor and the inner wall of the jacket, and is equipped at the mid-section with gas-inlet conduits for injecting the inert light gas into the annular space between the rotor and the jacket through the openings provided at the tips of the conduits in the direction of the rotor's rotation and also tangentially to the rotor, and is further equipped near the top and bottom with gas-outlet conduits fitted with control valves; and (3) heating and cooling units installed at the top and bottom of the annualr space between the rotor and the jacket. (U.S.)

  2. International 235U fission foil mass intercomparison

    In the measurement of neutron fission cross sections, one of the larger uncertainties is associated with the mass determination of the fissionable deposit. Inconsistencies in determinations of the fission cross sections may be a result of systematic errors associated with the measurement of the deposit mass. As part of a study to check the consistency of mass scales at a number of laboratories throughout the world, two 235U deposits from the Khlopin Radium Institute (KRI) in Leningrad, USSR, were made available through the assistance of the International Atomic Energy Agency for measurements at the National Bureau of Standards (NBS) and Argonne National Laboratory (ANL). These deposits are directly traceable to foils used in very precise measurements of the 235U(n,f) cross section made in a collaborative effort by KRI and the Technical University of Dresden (TUD), GDR. The study undertaken at the NBS consisted of two parts. One part was the measurement of the alpha-decay rates of the two 235U samples (KRI VI and KRI-XV) with a low-geometry-counting spectrometry facility. The other was the measurement of the total alpha disintegration rate of the samples employing a 2II alpha counter

  3. Practical Gamma Counting of Unirradiated Uranium-235

    During the fabrication of reactor fuel elements it is necessary to have assurance regarding the accuracy of the fabricator's uranium assignment within the specified tolerances. Destructive analysis of random samples is both expensive and time-consuming. Where the uranium-bearing components are suitable for gamma counting, a non-destructive method of assay can be used with greater efficiency and equal accuracy. The particular method described was used for checking fuel cores of nominal 30 wt.% enriched uranium in aluminium measuring about two inches square by 0.080 in. and 0.160 in. thick. The equipment was a basic Nal scintillation counter equipped with a single-channel analyser. The analyser, however, was operated with a very wide window covering both the 90-keV and 184-keV peaks characteristic of uranium-235. In practice, the threshold level acid the window opening, were adjusted to give the optimum maximum count rate as indicated by a ratemeter. The counting of a fuel core was then performed with the Nal crystal essentially unshielded and located several inches above the fuel core. The counting time was adjusted to yield a total count in the range of 105 to 106 in order to minimize the counting error. Effects due to variations in the counting geometry and to non-uniform uranium distribution were minimized by the relatively large separation of the crystal from the fuel core. Effects due to shifting of analyser window were minimized by use of a wide opening. To compensate for possible non-uniform uranium distribution through the thickness of a fuel core, each core was counted on both sides. The total count obtained in this manner was directly proportioned to the uranium-235 content of the fuel core. In application, the counting equipment was set up in the fabricator's plant and a number of production fuel cores were counted. The plotting of the total counts against the fabricator's uranium-235 assignment revealed an unexpected error in the fabricator's system

  4. Groundwater seepage from the Ranger uranium mine tailings dam: radioisotopes of radium, thorium and actinium. Supervising Scientist report 106

    Monitoring of bores near the Ranger uranium mine tailings dam has revealed deterioration in water quality in several bores since 1983. In a group of bores to the north of the dam, increases have been observed of up to 500 times for sulphate concentrations and of up to 5 times for 226Ra concentrations. Results are presented here of measurements of members of the uranium, thorium and actinium decay series in borewater samples collected between 1985 and 1993. In particular, measurements of all four naturally-occurring radium isotopes have been used in an investigation of the mechanism of radium concentration changes. For the most seepage-affected bores the major findings of the study include: 228Ra/226Ra 223Ra /226Ra and 224Ra/228Ra ratios all increased over the course of the study; barium concentrations show high seasonal variability, being lower in November than May, but strontium concentrations show a steady increase with time. Calculations show that the groundwater is probably saturated with respect to barite but not with respect to celestite or anglesite; sulphide concentrations are low in comparison with sulphate, and are higher in November than in May; and 227Ac concentrations have increased with time, but do not account for the high 223Ra/226Ra ratios. It is concluded on the basis of these observations that increases in Ra isotope concentrations observed in a number of seepage-affected bores arise from increases in salinity leading to desorption of radium from adsorption sites in the vicinity of the bore rather by direct transport of radium from the tailings. Increased salinity is also causing the observed increases in 227Ac and strontium concentrations, while formation of a barite solid phase in the groundwater is causing the removal of some radium from solution. This is the cause of the increasing radium isotope ratios noted above

  5. Decay scheme of the U{sup 2}35; Esquema de desintegracion del U-235

    Gaeta, R.

    1965-07-01

    A study of the Th{sup 2}31 excited levels from the alpha decay of the U{sup 2}35, is carried out. The alpha particle spectrum was measured by means of a semiconductor counter spectrometer with an effective resolution of 18 keV. Nineteen new lines were identified. The gamma-ray spectrum was measured with thin samples of U{sup 2}35, free from decay products, and in such geometrical conditions, that most of the interference effects were eliminated. The gamma-gamma coincidence spectra have made easier a better knowledge of the transition between the several levels. (Author) 110 refs.

  6. Preparation of 235U target by electrodeposition

    A target for the production of fission 99Mo in a nuclear reactor is composed of an enclosed, cylindrical vessel. Preferable vessel is comprised of stainless steel, having a thin, continuous, uniform layer of 235U integrally bonded to its inner walls. Two processes are introduced for electrodepositing uranium on to the inner walls of the vessel. One processes is electrodepositing UO2 from UO2(NO3)2-(NH4)2CO4·H2O solution; the other is electrodepositing pure uranium metal from molten salt. Its plating efficiency and plating quantity from a molten bath is higher than UO2 from the aqueous system. (authors)

  7. Dicty_cDB: CFJ235 [Dicty_cDB

    Full Text Available TTGTGTTGATGCTT CAACATGGCAATCCTATTCTGGTGGTATTATTACAACTGGTTGTGGTAAAAACATTGATC ATTGTGTTCAAGTA Length of 3' end seq. 554 Connect...ed seq. ID CFJ235P Connected seq. >CFJ235P.Seq ATATCAGTTTTACATCTTTTTTAAATATATATCTACTATATCTAA...ATTACAACTGGTTGTGGTAAAAACATTGATC ATTGTGTTCAAGTA Length of connected seq. 664 Full length Seq ID - Full length Seq. - Length of full length seq. - ... ...D859313.1 F15.001A09F020226 F15 Pisum sativum cDNA clone F15001A09, mRNA sequence. 48 5e-08 2 U19267 |U19267.1 Zinn...CF (Link to library) CFJ235 (Link to dictyBase) - - - Contig-U07719-1 CFJ235P (Link

  8. Multipole components of 235U photofission

    The absolute electrofission cross section for 235U has been experimentally obtained in the energy range 5.8 - 18.0 MeV, using the electron beam of the Linear Accelerator of Institute of Physics of the University of Sao Paulo. From a combined analysis of this cross section and a previously measured photofission cross section, using virtual photon spectra calculated in the Distorted Wave Born Approximation (DWBA), the '' non electric dipole photofission'' cross section σNDEγ,f (ω) has been obtained, which contains all multipolarities allowed by the reaction Kinematics, except El. This cross section presents a resonant shape, probably associated with the Giant Quadrupole Resonance (GQR). Once the fission channel exhausts a great amount of the Energy Weighted Sum Rule (EWSR), it is therefore the major decay mode of the GQR. All these aspects agree with the ones verified for the other Uranium isotopes previously analysed in this Laboratory. (author)

  9. 33 CFR 162.235 - Puget Sound Area, Wash.

    2010-07-01

    ...: The Corps of Engineers also has regulations dealing with this section in 33 CFR Part 207. ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Puget Sound Area, Wash. 162.235...) PORTS AND WATERWAYS SAFETY INLAND WATERWAYS NAVIGATION REGULATIONS § 162.235 Puget Sound Area, Wash....

  10. Dicty_cDB: CHG235 [Dicty_cDB

    Full Text Available CH (Link to library) CHG235 (Link to dictyBase) - - - Contig-U16308-1 CHG235P (Link to Original ... .10.25 Translated Amino Acid sequence k*NSFNNNNLIFFIVF KDIMKNFYYFILILLFFNEVCYSLKDGEIKLHLIPHSHCDSGWT STMNEY ... NPINTKQTKITLYP SEIKAMKLLIIKI Frame B: k*NSFNNNNLIFFIVF KDIMKNFYYFILILLFFNEVCYSLKDGEIKLHLIPHSHCDSGWT STMNEY ...

  11. Dicty_cDB: SHE235 [Dicty_cDB

    Full Text Available SH (Link to library) SHE235 (Link to dictyBase) - - - Contig-U15792-1 SHE235P (Link to Original ... |DV426996.1 NADY185TR Aedes aegypti infected with Dengue ... virus Pool library Aedes aegypti cDNA clone NADY18 ...

  12. Dicty_cDB: CHQ235 [Dicty_cDB

    Full Text Available CH (Link to library) CHQ235 (Link to dictyBase) - - - Contig-U11840-1 | Contig-U13129-1 CHQ235P ... mplete sequence. 149 2e-93 11 AF288090 |AF288090.1 Rhodomonas ... salina mitochondrial DNA, complete genome. 88 8e-1 ...

  13. 31 CFR 235.4 - Check Forgery Insurance Fund.

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Check Forgery Insurance Fund. 235.4... SERVICE, DEPARTMENT OF THE TREASURY FINANCIAL MANAGEMENT SERVICE ISSUANCE OF SETTLEMENT CHECKS FOR FORGED CHECKS DRAWN ON DESIGNATED DEPOSITARIES § 235.4 Check Forgery Insurance Fund. The Check Forgery...

  14. Observation of the uranium 235 nuclear magnetic resonance signal

    Le Bail, H.; Chachaty, C.; Rigny, P.; Bougon, R.

    1983-01-01

    The first observation of the nuclear magnetic resonance of the uranium 235 is reported. It has been performed on pure liquid uranium hexafluoride at 380 K. The measured magnetogyric ratio is | γ(235U) | = 492.6 ± 0.2 rad.s-1 G-1.

  15. Nuclear Excitation by Electronic Transition of U-235

    Chodash, Perry Adam [Univ. of California, Berkeley, CA (United States)

    2015-07-14

    Nuclear excitation by electronic transition (NEET) is a rare nuclear excitation that is theorized to occur in numerous isotopes. One isotope in particular, 235U, has been studied several times over the past 40 years and NEET of 235U has never been conclusively observed. These past experiments generated con icting results with some experiments claiming to observe NEET of 235U and others setting limits for the NEET rate. This dissertation discusses the latest attempt to measure NEET of 235U. If NEET of 235U were to occur, 235mU would be created. 235mU decays by internal conversion with a decay energy of 76 eV and a half-life of 26 minutes. A pulsed Nd:YAG laser operating at 1064 nm with a pulse energy of 789 mJ and a pulse width of 9 ns was used to generate a uranium plasma. The plasma was captured on a catcher plate and electrons emitted from the catcher plate were accelerated and focused onto a microchannel plate detector. A decay of 26 minutes would suggest the creation of 235mU and the possibility that NEET occurred. However, measurements performed using a variety of uranium targets spanning depleted uranium up to 99.4% enriched uranium did not observe a 26 minute decay. Numerous other decays were observed with half-lives ranging from minutes up to hundreds of minutes. While NEET of 235U was not observed during this experiment, an upper limit for the NEET rate of 235U was determined. In addition, explanations for the con icting results from previous experiments are given. Based on the results of this experiment and the previous experiments looking for NEET of 235U, it is likely that NEET of 235U has never been observed.

  16. Monsanto Gives Washington U. $23.5 Million.

    Culliton, Barbara J.

    1982-01-01

    Reviews various provisions of a five-year, $23.5-million research agreement between Washington University and the Monsanto Company. The scientific focus of this venture will be on proteins and peptides which modify cellular behavior. (SK)

  17. Assay Method for 235U in Low-Density Waste

    2008-01-01

    <正>235U assay method will provide a semi-quantitative assay for any uranium lumps that might exist in low-density, low-Z material waste boxes within a short count time. These materials will consist of

  18. Direct measurement of uranium 235 concentration in uranium hexafluoride containers

    A simple, portable and autonomous apparatus is described. Isotopic ratio of uranium 235 can be determined in UF6 containers (type 30B or 48Y) without contact with the fissile material. A thermal neutron source induces, through the container wall, nuclear fissions. Fast neutrons produced by the nuclear reaction are detected and counted giving the concentration in uranium 235. Results obtained are presented and discussed

  19. Dicty_cDB: SHH235 [Dicty_cDB

    Full Text Available SH (Link to library) SHH235 (Link to dictyBase) - G23190 DDB0230077 Contig-U16076-1 SHH235P (Lin ... 24 |AF454824.1 Enterococcus faecalis pathogenicity island , complete sequence. 42 2e-04 9 AC116984 |AC116984. ... 999.1 Enterococcus faecalis putative pathogenicity island , partial sequence. 42 7e-04 5 dna update 2006. 4. ...

  20. Nuclear excitation by electronic transition of 235U

    Chodash, P. A.; Burke, J. T.; Norman, E. B.; Wilks, S. C.; Casperson, R. J.; Fisher, S. E.; Holliday, K. S.; Jeffries, J. R.; Wakeling, M. A.

    2016-03-01

    Background: Nuclear excitation by electronic transition (NEET) is a rare nuclear excitation that can occur in isotopes containing a low-lying nuclear excited state. Over the past 40 yr, several experiments have attempted to measure NEET of 235U and those experiments have yielded conflicting results. Purpose: An experiment was performed to determine whether NEET of 235U occurs and to determine its excitation rate. Method: A pulsed Nd:YAG laser operating at 1064 nm with a pulse energy of 790 mJ and a pulse width of 9 ns was used to generate a uranium plasma. The plasma was collected on a catcher plate and electrons from the catcher plate were accelerated and focused onto a microchannel plate detector. An observation of a decay with a 26-min half-life would suggest the creation of Um235 and the possibility that NEET of 235U occurred. Results: A 26-min decay consistent with the decay of Um235 was not observed and there was no evidence that NEET occurred. An upper limit for the NEET rate of 235U was determined to be λNEETconfidence level of 68.3%. Conclusions: The upper limit determined from this experiment is consistent with most of the past measurements. Discrepancies between this experiment and past measurements can be explained by assuming that past experiments misinterpreted the data.

  1. A U-235 confirmation method with a discriminating view

    Reprocessed spent nuclear fuel that has gone through various stages of chemical processing is currently stored at the INEEL. The material consists of three categories: clean U-235 with radiation readings in the mR/h range, U-235 and fission products up to 900 mR/h, and U-235 with U-232 from 100--200 mR/h. The material is contained in plastic bottles and stored in steel structures consisting of seven vertically arranged individual compartments. A total of forty stacks reside in individual concrete wells. This material is considered hard to measure due to excessive radiation exposure to personnel involved with handling the material during mass and NaI U-235 confirmation measurements for Safeguards inventory purposes. A U-235 confirmation method was developed to assay the individual items in place with the ability to discriminate one item from the other items in the stack. Equipment used with this method includes a portable high-resolution gamma-ray detection system, an appropriate tungsten shield and collimator, and a laser-positioning device. A discrimination control test was incorporated to compare the gamma-ray signal of an item in place to the background signal when the item is removed. Total discrimination of the 186-keV gamma ray signal was achieved

  2. 235Cf anti ν discrepancy and the sulfur discrepancy

    The cantankerous discrepancy among measured values of anti ν for 235Cf appears at last to be nearing a final resolution. A recent review has summarized the progress that has been achieved through revaluation upward by 0.5% of two manganese bath values anti ν and the performance of a new liquid scintillator measurement. A new manganese bath measurement at INEL is in reasonably good agreement with previous manganese bath values of 235Cf anti ν. It now appears that the manganese bath values could still be systematically low by as much as 0.4% because the BNL-325 thermal absorption cross section for sulfur may be as much as 10% low. There is a bona fide discrepancy between measurements of the sulfur cross section by pile oscillators and the values derived from transmission measurements. The resolution of this discrepancy is a prerequisite to the final resolution of the 235Cf anti ν discrepancy. 22 references

  3. Integral cross section measurement of the 235U(n ,n') Um235 reaction in a pulsed reactor

    Bélier, G.; Bond, E. M.; Vieira, D. J.; Authier, N.; Becker, J. A.; Hyneck, D.; Jacquet, X.; Jansen, Y.; Legendre, J.; Macri, R.; Méot, V.; Romain, P.

    2015-04-01

    The integral measurement of the neutron inelastic cross section leading to the 26-minute half-life Um235 isomer in a fission-like neutron spectrum is presented. The experiment has been performed at a pulsed reactor, where the internal conversion decay of the isomer was measured using a dedicated electron detector after activation. The sample preparation, efficiency measurement, irradiation, radiochemistry purification, and isomer decay measurement will be presented. We determined the integral cross section for the 235U(n ,n') Um235 reaction to be 1.00 ±0.13 b . This result supports an evaluation performed with talys-1.4 code with respect to the isomer excitation as well as the total neutron inelastic scattering cross section.

  4. 77 FR 29986 - Savannah River Site Building 235-F Safety

    2012-05-21

    ... site workers who are normally in the facilities, construction sites, and trailers located adjacent to... Solidification Building construction sites to examine how these facilities would respond to a significant... facilities, construction sites, and trailers located adjacent to Building 235-F. Development of this...

  5. Dicty_cDB: SLI235 [Dicty_cDB

    Full Text Available SL (Link to library) SLI235 (Link to dictyBase) - G24235 DDB0191526 Contig-U01384-1 | Contig-U12 ... ****lkklkkkktlii Frame B: yhskhsrtsw*igsrs*rlkesig*skw *nh*rcwyir*syr*yqskigscyqslccshk *fyhptklikcc*nr*** ...

  6. Some 235U reference fission product yield data evaluation

    To satisfy the requirement of application for reference fission product yield data, the data have been and will be continuously evaluated. Present work, in which the reference data for 20 product nuclides from 235U fission were evaluated, is a part of the whole work

  7. 48 CFR 2052.235-70 - Publication of research results.

    2010-10-01

    ... publication in refereed scientific and engineering journals or dissemination to the public of any information... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Publication of research....235-70 Publication of research results. As prescribed in 2035.70(a)(1), the contracting officer...

  8. 48 CFR 235.006-70 - Manufacturing Technology Program.

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Manufacturing Technology... CONTRACTING 235.006-70 Manufacturing Technology Program. In accordance with 10 U.S.C. 2521(d), for acquisitions under the Manufacturing Technology Program— (a) Award all contracts using competitive...

  9. 46 CFR 172.235 - Extent of damage.

    2010-10-01

    ... BULK CARGOES Special Rules Pertaining to Great Lakes Dry Bulk Cargo Vessels § 172.235 Extent of damage... Damage Collision Penetration Longitudinal extent 0.495 L2/3 or 47.6 feet. (1/3 L2/3 or 14.5 m),...

  10. 29 CFR 99.235 - Program-specific audits.

    2010-07-01

    ... § 99.235 Program-specific audits. (a) Program-specific audit guide available. In many cases, a program-specific audit guide will be available to provide specific guidance to the auditor with respect to internal control, compliance requirements, suggested audit procedures, and audit reporting requirements....

  11. 24 CFR 235.230 - Condition of multifamily structure.

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Condition of multifamily structure... Involving Condominium Units § 235.230 Condition of multifamily structure. (a) When a family unit is conveyed... principal rating organization doing business in the state. If the property is located in a state which...

  12. 4-Chloro-2,3,5-trifluorobenzoic Acid

    Shuitao Yu

    2015-11-01

    Full Text Available A new tetrahalogenated benzoic acid 4-chloro-2,3,5-trifluorobenzoic acid was synthesized from methyl 2,3,4,5-tetrafluorobenzoate via three steps. The structure of the newly synthesized compound was established by FTIR, NMR, MS and elemental analysis.

  13. 24 CFR 8.29 - Homeownership programs (sections 235(i) and 235(j), Turnkey III and Indian housing mutual self...

    2010-04-01

    ... order to accommodate his or her specific handicap. The cost of making a facility accessible under this... the extent such costs exceed allowable mortgage limits, they may be passed on to the prospective homebuyer, subject to maximum sales price limitations (see 24 CFR 235.320.)...

  14. 48 CFR 235.015-70 - Special use allowances for research facilities acquired by educational institutions.

    2010-10-01

    ... research facilities acquired by educational institutions. 235.015-70 Section 235.015-70 Federal Acquisition... CONTRACTING RESEARCH AND DEVELOPMENT CONTRACTING 235.015-70 Special use allowances for research facilities acquired by educational institutions. (a) Definitions. As used in this subsection— (1) Research...

  15. 41 CFR 102-41.235 - May we sell forfeited drug paraphernalia?

    2010-07-01

    ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false May we sell forfeited drug paraphernalia? 102-41.235 Section 102-41.235 Public Contracts and Property Management Federal... Requiring Special Handling Drug Paraphernalia § 102-41.235 May we sell forfeited drug paraphernalia? No,...

  16. Preliminary Study on the Determination of ~(235)U and ~(239)Pu Using Delayed Neutron Counting Method

    2011-01-01

    The preliminary study on the fast measurements of 235U and 239Pu in samples containing 235U, 239Pu and 235U-239Pu mixture using delayed neutron counting method is introduced. All samples were irradiated for 30 s using the 30 kW Miniature Neutron

  17. 48 CFR 1852.235-74 - Additional Reports of Work-Research and Development.

    2010-10-01

    ...-Research and Development. 1852.235-74 Section 1852.235-74 Federal Acquisition Regulations System NATIONAL... Provisions and Clauses 1852.235-74 Additional Reports of Work—Research and Development. As prescribed in 1835.070(e), insert a clause substantially the same as the following: Additional Reports of...

  18. 22 CFR 23.5 - Claims for settlement by Department of State or General Accounting Office.

    2010-04-01

    ... General Accounting Office. 23.5 Section 23.5 Foreign Relations DEPARTMENT OF STATE FEES AND FUNDS FINANCE AND ACCOUNTING § 23.5 Claims for settlement by Department of State or General Accounting Office. Claims for settlement by the Department of State or by the General Accounting Office shall be...

  19. 16 CFR 23.5 - Misuse of the word “vermeil.”

    2010-01-01

    ... 16 Commercial Practices 1 2010-01-01 2010-01-01 false Misuse of the word âvermeil.â 23.5 Section 23.5 Commercial Practices FEDERAL TRADE COMMISSION GUIDES AND TRADE PRACTICE RULES GUIDES FOR THE JEWELRY, PRECIOUS METALS, AND PEWTER INDUSTRIES § 23.5 Misuse of the word “vermeil.” (a) It is unfair...

  20. 24 CFR 235.331 - Increased maximum mortgage amount for physically handicapped persons.

    2010-04-01

    ... for physically handicapped persons. 235.331 Section 235.331 Housing and Urban Development Regulations... maximum mortgage amount for physically handicapped persons. If the mortgage relates to a dwelling unit to be occupied by a handicapped person as defined in § 235.5(c)(2), the otherwise applicable...

  1. 41 CFR 102-117.235 - How do I get a cost comparison?

    2010-07-01

    ... MANAGEMENT Shipping Household Goods § 102-117.235 How do I get a cost comparison? (a) You may calculate a cost comparison internally according to 41 CFR 302-8.3. (b) You may request GSA to perform the cost... comparison? 102-117.235 Section 102-117.235 Public Contracts and Property Management Federal...

  2. Composite delayed-neutron spectra from U-235

    Delayed-neutron spectra from thermal neutron-induced fission of U-235 have been measured over the neutron energy range, .01 - 2.0 MeV, for delay times following fission ranging from 0.17 - 85.5 s. A helium jet system was used for the rapid transport of fission products to a low-background area, where the spectra were determined from beta-neutron correlations using the neutron time-of-flight method

  3. Sistem Pakar Pada Perangkat Mobile Untuk Mendeteksi Kerusakan Docucenter 235

    Azhary, M. Fadli

    2011-01-01

    Development for mobile device is relieve to give efficient and faster information. Expert system is subdivision of artificial intelligence for solving in expert human problems. This study for implementation expert system working with backward chaining method that compatible for diagnose. In implementation, system giving user option “Yes” or “No” for answer some question. Those questions are pack based on technician experience and from guide book to solve troubleshooting for Docucenter 235. Th...

  4. Building 235-F Goldsim Fate And Transport Model

    Savannah River National Laboratory (SRNL) personnel, at the request of Area Completion Projects (ACP), evaluated In-Situ Disposal (ISD) alternatives that are under consideration for deactivation and decommissioning (D and D) of Building 235-F and the Building 294-2F Sand Filter. SRNL personnel developed and used a GoldSim fate and transport model, which is consistent with Musall 2012, to evaluate relative to groundwater protection, ISD alternatives that involve either source removal and/or the grouting of portions or all of 235-F. This evaluation was conducted through the development and use of a Building 235-F GoldSim fate and transport model. The model simulates contaminant release from four 235-F process areas and the 294-2F Sand Filter. In addition, it simulates the fate and transport through the vadose zone, the Upper Three Runs (UTR) aquifer, and the Upper Three Runs (UTR) creek. The model is designed as a stochastic model, and as such it can provide both deterministic and stochastic (probabilistic) results. The results show that the median radium activity concentrations exceed the 5 ρCi/L radium MCL at the edge of the building for all ISD alternatives after 10,000 years, except those with a sufficient amount of inventory removed. A very interesting result was that grouting was shown to basically have minimal effect on the radium activity concentration. During the first 1,000 years grouting may have some small positive benefit relative to radium, however after that it may have a slightly deleterious effect. The Pb-210 results, relative to its 0.06 ρCi/L PRG, are essentially identical to the radium results, but the Pb-210 results exhibit a lesser degree of exceedance. In summary, some level of inventory removal will be required to ensure that groundwater standards are met

  5. Building 235-F Goldsim Fate And Transport Model

    Taylor, G. A.; Phifer, M. A.

    2012-09-14

    Savannah River National Laboratory (SRNL) personnel, at the request of Area Completion Projects (ACP), evaluated In-Situ Disposal (ISD) alternatives that are under consideration for deactivation and decommissioning (D&D) of Building 235-F and the Building 294-2F Sand Filter. SRNL personnel developed and used a GoldSim fate and transport model, which is consistent with Musall 2012, to evaluate relative to groundwater protection, ISD alternatives that involve either source removal and/or the grouting of portions or all of 235-F. This evaluation was conducted through the development and use of a Building 235-F GoldSim fate and transport model. The model simulates contaminant release from four 235-F process areas and the 294-2F Sand Filter. In addition, it simulates the fate and transport through the vadose zone, the Upper Three Runs (UTR) aquifer, and the Upper Three Runs (UTR) creek. The model is designed as a stochastic model, and as such it can provide both deterministic and stochastic (probabilistic) results. The results show that the median radium activity concentrations exceed the 5 ?Ci/L radium MCL at the edge of the building for all ISD alternatives after 10,000 years, except those with a sufficient amount of inventory removed. A very interesting result was that grouting was shown to basically have minimal effect on the radium activity concentration. During the first 1,000 years grouting may have some small positive benefit relative to radium, however after that it may have a slightly deleterious effect. The Pb-210 results, relative to its 0.06 ?Ci/L PRG, are essentially identical to the radium results, but the Pb-210 results exhibit a lesser degree of exceedance. In summary, some level of inventory removal will be required to ensure that groundwater standards are met.

  6. Overview of recent U235 neutron cross section evaluation work

    Lubitz, C. [Lockheed Martin Corp., Schenectady, NY (United States)

    1998-10-01

    This report is an overview (through 1997) of the U235 neutron cross section evaluation work at Oak Ridge National Laboratory (ORNL), AEA Technology (Harwell) and Lockheed Martin Corp.-Schenectady (LMS), which has influenced, or appeared in, ENDF/B-VI through Release 5. The discussion is restricted to the thermal and resolved resonance regions, apart from some questions about the unresolved region which still need investigation. The important role which benchmark testing has played will be touched on.

  7. Activity of BKM120 and BEZ235 against Lymphoma Cells

    Monica Civallero

    2015-01-01

    Full Text Available Non-Hodgkin lymphomas encompass a heterogeneous group of cancers, with 85–90% arising from B lymphocytes and the remainder deriving from T lymphocytes or NK lymphocytes. These tumors are molecularly and clinically heterogeneous, showing dramatically different responses and outcomes with standard therapies. Deregulated PI3K signaling is linked to oncogenesis and disease progression in hematologic malignancies and in a variety of solid tumors and apparently enhances resistance to antineoplastic therapy, resulting in a poor prognosis. Here, we have evaluated and compared the effects of the pan-PI3K inhibitor BKM120 and the dual PI3K/mTOR inhibitor BEZ235 on mantle, follicular, and T-cell lymphomas. Our results suggest that BKM120 and BEZ235 can effectively inhibit lymphoma cell proliferation by causing cell cycle arrest and can lead to cell death by inducing apoptosis and autophagy mediated by ROS accumulation. Despite great advances in lymphoma therapy after the introduction of monoclonal antibodies, many patients still die from disease progression. Therefore, novel treatment approaches are needed. BKM120 and BEZ235 alone and in combination are very effective against lymphoma cells in vitro. If further studies confirm their effectiveness in animal models, they may be promising candidates for development as new drugs.

  8. Calculation of resonance self-shielding in 235U

    The self-shielded fission rates for 235U measured by Czirr have been computed in the 0.464- to 464-eV range with the 235U resolved resonance parameters of the current version of ENDF/B-VI. The main purpose of describing the neutron cross sections of the fissile isotopes with resonance parameters is for the calculation of resonance self-shielding in reactors. Czirr has measured the relative self-shielded fission rate behind absorber thicknesses varying from 0.5 to 19 g/cm2 of uranium. These measurements have repeatedly been used to test the validity of sets of resonance parameters. However, previous calculations of these experiments were limited and inconclusive. An evaluation of the 235U resolved resonance region extending to 2.2 keV was recently completed and incorporated into ENDF/B-VI. The resonance parameters of this evaluation were used to compute the self-shielded fission rates for energy groups 0 to 8 (energies from 0.464 to 464 eV) of the Czirr measurement

  9. Ternary Fission of U235 by Resonance Neutrons

    Recently a number of papers have appeared indicating considerable variations in the ratio of the ternary-fission cross-section to the binary-fission cross-section of U235 on transition from one neutron resonance to another. However, such variations have not been discovered in U233 and Pu239. The paper reports investigations of the ternary fission of U235 by neutrons with an energy of 0.1 to 30 eV. Unlike other investigators of the ternary fission of U235 , we identified the ternary-fission event by the coincidence of one of the fission fragments with a light long-range particle. This made it passible to separate ternary fissions from the possible contribution of the (n, α)reaction. The measurements were performed at the fast pulsed reactor of the Joint Institute for Nuclear Research by the time-of-flight method. A flight length of 100 m was used, giving a resolution of 0.6 μs/m. Gas scintillation counters filled with xenon at a pressure of 2 atm were used to record the fission fragments and the light long-range particle. A layer of enriched U235 ∼2 mg/cm2 thick and ∼300 cm2 in area was applied to an aluminium foil 20-fim thick. The scintillations from the fission fragments were recorded in the gas volume on one side of the foil and those from the light long-range particles in that on the other. In order to assess the background (e.g . coincidences of the pulse from a fragment with that from a fission gamma quantum or a proton from the (n, p) reaction in the aluminium foil), a measurement was carried out in which the volume recording the long-range particle was shielded with a supplementary aluminium filter 1-mm thick. The results obtained indicate the absence of the considerable variations in the ratio between the ternary-and binary- fission cross-sections for U235 that have been noted by other authors. Measurements showed no irregularity in the ratio of the cross-sections in the energy range 0.1 to 0.2 eV. The paper discusses the possible effect of the (n,

  10. Different evolutionary stages in S235A-B

    Felli, Marcello; Massi, Fabrizio; Cesaroni, Riccardo

    The star forming region S235A-B has been studied at high resolution with radio (IRAM Interferometer and VLA) and infrared (JCMT and Spitzer) observations. The region was mapped in HCO^+, C^34S, H[2]CS, SO[2] and CH[3]CN as well as in the 1.2 and 3.3 continuum, in the cm continuum at 6, 3.6, 1.3 and 0.7 cm and in the 22 GHz water maser line, in the far infrared at 450 and 850 micron and in the mid infrared from 3.6 to 8 micron. Use was made of the Medicina water maser patrol, from 1987 to 2005, to study the maser variability. S235A is a classical HII region, well resolved and with a very good match between radio and infrared images. To the south of it, molecular and continuum mm observations as well as infrared observations reveal the presence of newly formed YSOs placed in between S235A and S235B: a molecular core and an unresolved mm source centred on one maser component, with indication of mass infall onto the core. Two bipolar outflows and a jet originate from the same position. No cm radio continuum emission is detected either from the compact molecular core or from the jet-like structure, suggesting emission from dust in both cases. Evidence is found for a molecular rotating disk perpendicular to the main bipolar outflow. The derived parameters indicate that the YSO is an intermediate luminosity object in a very early evolutionary phase. Its main source of energy could come from gravitational infall thus making this YSO a rare link between the earliest evolutionary phases of massive stars and low mass protostars of class 0-I. Two compact radio continuum sources (VLA-1 and VLA-2) and three separate maser spots were found. VLA-1 coincides with one of the maser spots and with an IR source (M1). VLA-2 lies towards S235B and represents the first radio detection from this peculiar nebula. The two other maser spots coincide with the rotating disk perpendicular to the bipolar molecular outflow. The Spitzer images reveal a red object towards the molecular core which is

  11. Evaluation of 235U(n,f) above 100 keV for ENDF/B-V and the implications of a unified 235U mass scale

    A previously reported evaluation of 235U(n,f) in the fast neutron energy range was updated to include data published up to the 1978 Harwell Conference on Neutron Physics. The shape of the cross section resulting from this evaluation and a normalization factor extracted from data provided within the framework of this evaluation were used by the Subcommittee on Standards and Normalizations of the Cross Section Evaluation Working Group to establish 235U(n,f) for ENDF/B-V above 100 keV. The 235U sample mass comparisons made between different laboratories were compiled in order to investigate the implications of different sample masses on recent 235U(n,f) data. A new intercomparison of several such samples was carried out using absolute and relative alpha-counting and relative fast neutron fission counting. The result of this work is a unified 235U mass scale with an uncertainty of 0.6%. 39 references

  12. Neutron induced fission of 235sub(U)

    In order to achieve a better understanding of the fision process it is essential to get experimental data on the details of the mass, energy and angular distributions, and the mass versus energy and mass versus angular distribution correlations as function of excitation energy. The present work describes the result of such a measurement for 235U(n,f) with thermal 235U(n,f) reaction has a rather high cross section, especially for thermal neutrons. The changes in the average total kinetic energy relative to the thermal value have been measured at several neutron energies above thermal, and the angular anisotropy of the fission fragments averaged over all fragment masses has been determined in several measurements. Many of the thermal values, the average kinetic energy and average angular anisotropy values at higher neutron energies were compared with measurements using other techniques. Good agreement is found. It indicates that the chamber works as intended and it gives confidence to the data measured for the first time with the present setup. It furthermore allows to use the chamber with confidence in future measurements on less known fission reactions and at less explored excitation energies of the compound nucleus. (author)

  13. Resonance structure in the fission of (235U+n)

    A new multilevel reduced R-matrix analysis of the neutron-induced resonance cross sections of 235U has been carried out. We used as a constraint in the analysis the angular anisotropy measurements of Pattenden and Postma, obtaining a Bohr-channel (or J, K channel) representation of the resonances in a two-fission vector space for each spin state. Hambsch et al., have reported definitive measurements of the mass- and kinetic-energy distributions of fission fragments of (235U+n) in the resonance region and analyzed their results according to the fission-channel representation of Brosa et al., extracting relative contributions of the two asymmetric and one symmetric Brosa fission channels. We have explored the connection between Bohr-channel and asymmetric Brosa-channel representations. The results suggest that a simple rotation of coordinates in channel space may be the only transformation required; the multilevel fit to the total and partial cross sections is invariant to such a transformation. (orig.)

  14. 238UF6 and 235UF6 spectra measurement in mid IR spectral range

    Making use of a diode laser one measured the absorption spectra of 238UF6 and 235UF6 molecules within v1+v3 combined oscillation band at λ=7.68 μm wavelength. To determine the possibility to measure 235UF6/ 238UF6 isotope ratio with the required accuracy one measured the absorption factors of 235UF6 and 238UF6 isotope specimens and determined the sources of the errors and the ways to minimize them

  15. 235U Holdup Measurement Program in support of facility shutdown

    In 1989, the Department of Energy directed shutdown of an enriched uranium processing facility at Savannah River Site. As part of the shutdown requirements, deinventory and cleanout of process equipment and nondestructive measurement of the remaining 235U holdup were required. The holdup measurements had safeguards, accountability, and nuclear criticality safety significance; therefore, a technically defensible and well-documented holdup measurement program was needed. Appropriate standards were fabricated, measurement techniques were selected, and an aggressive schedule was followed. Early in the program, offsite experts reviewed the measurement program, and their recommendations were adopted. Contact and far-field methods were used for most measurements, but some process equipment required special attention. All holdup measurements were documented, and each report was subjected to internal peer review. Some measured values were checked against values obtained by other methods; agreement was generally good

  16. Isotopic analysis of uranium hexafluoride highly enriched in U-235

    Isotopic analysis of uranium in the form of the hexafluoride by mass-spectrometry gives gross results which are not very accurate. Using a linear interpolation method applied to two standards it is possible to correct for this inaccuracy as long as the isotopic concentrations are less than about 10 per cent in U-235. Above this level, the interpolations formula overestimates the results, especially if the enrichment of the analyzed samples is higher than 1.3 with respect to the standards. A formula is proposed for correcting the interpolation equation and for the extending its field of application to high values of the enrichment (≅2) and of the concentration. It is shown that by using this correction the results obtained have an accuracy which depends practically only on that of the standards, taking into account the dispersion in the measurements. (authors)

  17. Uranium-235 and childhood leukaemia around Greenham Common airfield

    There has been considerable publicity recently concerning the possible release of enriched uranium from the Greenham Common USAF base near Newbury in Berkshire. Evidence for the release relies on an internal report of the Atomic Weapons Research Establishment at Aldermaston, the authors of which postulated that it resulted from a fire in 1958 involving a B47 bomber standing on the runway. Their report contained a much publicised contour map of excess 235U levels estimated from the ratio of 235U to 238U in 26 evergreen leaf samples examined. The current concern of the inhabitants of Newbury centres mostly on the incidence of leukaemia, which was known beforehand to be slightly elevated in parts of West Berkshire, at least for young children. A number of cases have received considerable press publicity, with suggestions that their homes are located close to the base or the flight-path. The reports are, however, anecdotal and are not based on a complete register of cases. We have examined the evidence for this putative association by re-analysing the uranium data and determining the spatial relationship to the base of cases of childhood leukaemia diagnosed in the years 1966-87. We conclude that, although the excess uranium found has a non-random distribution, it does not support the pattern depicted by the contours and bears no relation to the incidence of childhood leukaemia for the period we examined. In any case, the increase in level of environmental radiation as a result of the putative release must be very small and is at variance with the reporting in some of the national press. (author)

  18. Adolescent idiopathic scoliosis: Retrospective analysis of 235 surgically treated cases

    Unnikrishnan Ranjith

    2010-01-01

    Full Text Available Background : The surgical treatment of adolescent idiopathic scoliosis (AIS has taken great strides in the last two decades. There have been no long term reported studies on AIS from India with documented long term followup. In this study we review a single surgical team′s series of 235 surgically treated cases of AIS with a follow-up from two to six years. Materials and Methods : Pre operative charts, radiographs and MRI scans for 235 patients were collected for this study. The patients were grouped into three groups where anterior correction and fusion (n=47, posterior correction and fusion (n=123 and combined anterior release and posterior instrumentation (n=65 was performed. Each group was divided into two subgroups based on the surgical approach and instrumentation strategy (all screw construct or hybrid construct used. Patients were followed up for coronal and saggital plane corrections, apical vertebral translation (AVT, trunk balance and back pain. The percentage of correction was calculated in each group as well as sub groups. Results : The incidence of MRI detected intraspinal anomaly in this series is 5.9% with 3.4% of them requiring neurosurgical procedure along with scoliosis correction. Average coronal major curve correction was 66% in the all screw group and 58.5% in the hybrid group. The coronal plane correction was better when the all screw constructs were employed. Also, the AVT and trunk balance was better with the all screw constructs. The anterior corrections resulted in better correction of the AVT and trunk balance as compared to the posterior correction. There were eight (3.4% complications in this series. The coronal and saggital plane correction paralleled the published international standards. Conclusion : The coronal plane correction was better when all screw constructs were employed. Use of all pedicle screw systems obviated the need for costoplasty in most cases. The increased incidence of intraspinal anomaly may

  19. 40 CFR 80.235 - How does a refiner obtain approval as a small refiner?

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false How does a refiner obtain approval as a small refiner? 80.235 Section 80.235 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...) The small refiner status application must contain the following information for the company...

  20. Dispersion of the Neutron Emission in U{sup 235} Fission

    Feynman, R. P.; de Hoffmann, F.; Serber, R.

    1955-01-01

    Equations are developed which allow the calculation of the average number of neutrons per U{sup235} fission from experimental measurements. Experimental methods are described, the results of which give a value of (7.8 + 0.6){sup ½} neutrons per U{sup 235} thermal fission.

  1. 24 CFR 990.235 - PHAs that will experience a subsidy increase.

    2010-04-01

    ... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false PHAs that will experience a subsidy increase. 990.235 Section 990.235 Housing and Urban Development Regulations Relating to Housing and Urban Development (Continued) OFFICE OF ASSISTANT SECRETARY FOR PUBLIC AND INDIAN HOUSING, DEPARTMENT OF HOUSING AND URBAN DEVELOPMENT THE...

  2. Determination of 235U/238U Ratio on Urine by ICP-MS

    LLNL Internal Dosimetry Program - The new procedure satisfies the requirement to determine 235U/238U ratio in bioassay urine samples. MDA - The LC and MDA95 for 235U are well below the required detection limit of 0.00035 μg/L. Turn around time - Analysis of 10 samples plus 2 QCs can be completed in one work day (8 hours).

  3. 40 CFR 52.235 - Control strategy for ozone: Oxides of nitrogen.

    2010-07-01

    ... nitrogen. 52.235 Section 52.235 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR... for ozone: Oxides of nitrogen. EPA is approving an exemption request submitted by the Monterey Bay... the area from implementing the oxides of nitrogen (NOX) requirements for reasonably available...

  4. 15 CFR 23.5 - Report to the Office of Juvenile Justice and Delinquency Prevention.

    2010-01-01

    ... 15 Commerce and Foreign Trade 1 2010-01-01 2010-01-01 false Report to the Office of Juvenile Justice and Delinquency Prevention. 23.5 Section 23.5 Commerce and Foreign Trade Office of the Secretary... Office of Juvenile Justice and Delinquency Prevention. The Department of Commerce will compile and...

  5. R-matrix analyses of the 235U and 239Pu neutron cross sections

    The resonance parameter analysis code SAMMY was used to perform consistent resonance analyses of several 235U and 239Pu fission and capture cross section and transmission measurements up to 110 eV for 235U and up to 1 keV for 239Pu. The method of analysis, the measurement selection and the results are briefly outlined in this paper

  6. 46 CFR 10.235 - Suspension or revocation of merchant mariner credentials.

    2010-10-01

    ... 46 Shipping 1 2010-10-01 2010-10-01 false Suspension or revocation of merchant mariner credentials. 10.235 Section 10.235 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY MERCHANT MARINE OFFICERS AND SEAMEN MERCHANT MARINER CREDENTIAL General Requirements for All Merchant Mariner Credentials §...

  7. 235例院前急救分析

    王海全

    2005-01-01

    目的:探讨院前急救的特点.方法:回顾性分析235例院前急救的疾病分类及心肺复苏(CPR)成功率状况.结果:需现场急救的疾病前3位是脑血管疾病、外科急症、心血管疾病,分别占26.38%、23.38%和17.45%;现场需CPR者53例,40~45岁以下以车祸、坠楼、中毒、意外居多,60岁以上以心、脑血管疾病为主,CPR成功率低,仅5.66%,主要与CPR开始时间延迟相关.结论:院前急救的重点是心、脑血管疾病和外伤;缩短CPR开始时间,提高CPR抢救成功率.

  8. Simulated (n,f) cross section of isomeric 235m-U

    The neutron-induced fission cross section on the 235U, T1/2 ∼ 26 min isomer has been deduced for incident neutron energies in the range En=0.1-2.5 MeV, using the surrogate-reaction technique. In this technique, 236U fission probabilities measured in the 234U(t, pf) reaction have been converted into 235U(n,f) and 235mU(n,f) cross sections, using reaction theory to compensate for the differences in angular-momentum and parity distributions in the fissioning systems, transferred by the (t,p) and neutron-induced reactions. Based on the comparison between the 235U(n,f) cross section extracted in this work and independent experimental data, the deduced 235mU(n,f) cross section is believed to be reliable to 20% below En ∼ 0.5 MeV and 10% at higher energies. The surrogate-reaction technique, its validation in the case of the 235U(n,f) cross section, and the deduced 235mU(n,f) cross section are discussed. Validation of this method allows (n,f) cross sections for many short-lived nuclei, as well as isomeric nuclei, to be extracted from measured fission probabilities

  9. 21 CFR 2.35 - Use of secondhand containers for the shipment or storage of food and animal feed.

    2010-04-01

    ... storage of food and animal feed. 2.35 Section 2.35 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT... Foods § 2.35 Use of secondhand containers for the shipment or storage of food and animal feed. (a... State public health agencies have revealed practices whereby food and animal feed stored or shipped...

  10. DM235 (sunifiram): a novel nootropic with potential as a cognitive enhancer

    Ghelardini C; Galeotti N.; Gualtieri F.; Romanelli M; Bucherelli C.; Baldi E.; Bartolini A.

    2002-01-01

    DM235 (sunifiram), a new compound structurally related to piracetam, prevented the amnesia induced by scopolamine (1.5 mg kg–1 i.p.), after intraperitoneal (0.001–0.1 mg kg–1) or oral (0.01–0.1 mg kg–1) administration, as shown by a passive avoidance test in mice. The antiamnesic effect of DM235 was comparable to that of well-known nootropic drugs such as piracetam (30–100 mg kg–1 i.p.), aniracetam (100 mg kg–1 p.o.) or rolipram (30 mg kg–1 p.o.). DM235 also prevented mecamylamine (20 mg kg–1...

  11. Prompt-Neutron Emission from U235 Fission Fragments

    A gadolinium-loaded large liquid scintillation counter is being used in conjunction with a neutron beam from the HERALD reactor at the Atomic Weapons Research Establishment, Aldermaston, to study neutron emission in the fission process. In particular, the neutron emission from individual fission fragments is observed. A fission-fragment detector comprising two gold-silicon suríace barrier counters operating in coincidence is situated at the edge of a 1-m-diam. spherical scintillation tank. The solid-state counters are placed on opposite sides of an evaporated fissile deposit on a thin nickel backing. A system of collimators selects for measurement only those fission events that have fragments travelling in the direction along the incident neutron beam and along the axis of the scintillator. Numbers of neutrons detected within 10 ps of a fission event are recorded. The angular correlation of neutron emission with fragment direction is used to associate the neutrons with the particular fission fragment that emitted them. Energies of both fragments are available from the solid-state counters, and identification of fragment mass and of the total kinetic energy of the fragment pair is made. The number of neutrons emitted by each fragment of the pair has been measured as a function of both the fragment mass and the total kinetic energy of the pair for thermal neutrons incident on U2'35. The usual asymmetry in the distribution of excitation energy between the heavy and light fragments is observed. The variation of the number of neutrons from the pair as a function of mass ratio is also determined. (author)

  12. U-235 sample-mass determinations and intercomparisons

    The neutron-induced fission cross section of U-235 is not only one of the most-frequently used references but is also of direct importance in reactor applications. As a consequence, knowledge of this cross section is required with approx. 1% uncertainty as reflected in corresponding entries in request lists, which have persisted since the last 10 to 15 years. Measurements to that level of accuracy require the investigation of the contributing components, one of which is the fission mass. The latter is most often determined by others than the experimenter who measures the differential cross sections or integral reaction-rate ratios in a reactor test facility. The isotopic composition and the sample mass are usually obtained from associated chemistry departments or standard laboratories, however, the experimenter has still the responsibility to assure that the values he uses are adequately described by the quoted uncertainties. This can be achieved by comparing samples from different origins. It was in this spirit that an intercomparison of fission samples obtained from different US laboratories, which were involved in cross section measurements, was carried out in 1979. The notable outcome of this effort was that a bias of approx. 0.7% was found between the standard laboratory and other contributing laboratories (which was, however, within the stated uncertainty). The National Bureau of Standards (NBS) has since then worked on a redefinition of the mass assignments of its reference samples, has revised its mass scale by 0.8%, and has reduced its uncertainty by a factor of two (to about +-0.5%). However, this new mass scale includes values relative to others. In the present work these have been removed in order to compare mass scales as independent from one another as possible. Independence already appears hard to come by. Results are presented

  13. Targeted disruption of py235ebp-1: Invasion of erythrocytes by Plasmodium yoelii using an alternative py235 erythrocyte binding protein

    Ogun, Solabomi A.

    2011-02-17

    Plasmodium yoelii YM asexual blood stage parasites express multiple members of the py235 gene family, part of the super-family of genes including those coding for Plasmodium vivax reticulocyte binding proteins and Plasmodium falciparum RH proteins. We previously identified a Py235 erythrocyte binding protein (Py235EBP-1, encoded by the PY01365 gene) that is recognized by protective mAb 25.77. Proteins recognized by a second protective mAb 25.37 have been identified by mass spectrometry and are encoded by two genes, PY01185 and PY05995/PY03534. We deleted the PY01365 gene and examined the phenotype. The expression of the members of the py235 family in both the WT and gene deletion parasites was measured by quantitative RT-PCR and RNA-Seq. py235ebp-1 expression was undetectable in the knockout parasite, but transcription of other members of the family was essentially unaffected. The knockout parasites continued to react with mAb 25.77; and the 25.77-binding proteins in these parasites were the PY01185 and PY05995/PY03534 products. The PY01185 product was also identified as erythrocyte binding. There was no clear change in erythrocyte invasion profile suggesting that the PY01185 gene product (designated PY235EBP-2) is able to fulfill the role of EBP-1 by serving as an invasion ligand although the molecular details of its interaction with erythrocytes have not been examined. The PY01365, PY01185, and PY05995/PY03534 genes are part of a distinct subset of the py235 family. In P. falciparum, the RH protein genes are under epigenetic control and expression correlates with binding to distinct erythrocyte receptors and specific invasion pathways, whereas in P. yoelii YM all the genes are expressed and deletion of one does not result in upregulation of another. We propose that simultaneous expression of multiple Py235 ligands enables invasion of a wide range of host erythrocytes even in the presence of antibodies to one or more of the proteins and that this functional

  14. Inhibition of proliferation in bone tumor cells after irradiation by 235U, 147Pm, 153Sm

    The inhibition of proliferation in bone tumor cells after simple or mixed irradiation by 235U, 147Pm, 153Sm was studied. Experimental results indicated that proliferation of bone tumor cells was significantly inhibited at 12 h∼24 h after a simple irradiation by 235U (128.4 Bq), 147Pm (7.4 x 105 Bq), and 153Sm (7.4 x 105 Bq) as well as mixed irradiation by 235U + 147Pm (64.2 Bq + 3.7 x 105 Bq), 235U + 153Sm (64.2 Bq + 3.7 x 105 Bq), 147Pm + 153Sm (3.7 x 105 Bq + 3.7 x 105 Bq). The findings show that the inhibition rate with mixed irradiation was more than that with simple irradiation

  15. Study of correcting the effect of daughter age on determining 235U enrichment of fuel rods

    Gamma-ray passive technique is a very effective method to assay and determine 235U enrichment of nuclear power plant fuel rods. There is a weakness in this passive method, i.e. only after the uranium isotope daughters of UO2 pellets have reached to equilibrium with uranium parent, then the 235U enrichment can be determined. This weakness greatly restricts the application of the method. A new two-peak and two-window technique is developed that can overcome the interference of uranium daughter decay in determining 235U enrichment of nuclear fuel rods, and the results are very satisfactory. The new technique will play an important role in the gamma-ray passive technique for determining 235U enrichment of fuel rods. This new technique also makes the gamma-ray passive method perfectly. (11 figs., 6 tabs.)

  16. 77 FR 26737 - Foreign-Trade Zone 235-Lakewood, NJ: Notification of Proposed Production Activity; Cosmetic...

    2012-05-07

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF COMMERCE Foreign-Trade Zones Board Foreign-Trade Zone 235--Lakewood, NJ: Notification of Proposed Production Activity; Cosmetic Essence Innovations, LLC (Fragrance Bottling); Holmdel, NJ Cosmetic Essence...

  17. Determination of 235U/238U Ratio on Urine by ICP-MS

    Collins, L; Gobaleza, A; Langston, R; Radev, R; Than, C; Wong, C; Wood-Zika, A

    2011-10-19

    LLNL Internal Dosimetry Program - The new procedure satisfies the requirement to determine {sup 235}U/{sup 238}U ratio in bioassay urine samples. MDA - The L{sub C} and MDA{sub 95} for {sup 235}U are well below the required detection limit of 0.00035 {mu}g/L. Turn around time - Analysis of 10 samples plus 2 QCs can be completed in one work day (8 hours).

  18. Verification of 235U enrichment in SNM receipts at the DOE Feed Materials Production Center

    A diversity of uranium-bearing, nonirradiated materials with 235U assays from fully depleted to a maximum of 10 wt % 235U, is routinely returned to this DOE site for reprocessing. It is necessary to confirm the 235U isotopic content of Special Nuclear Material (SNM) receipts both for accountability and nuclear criticality safety purposed. Methods and instrumentation have been developed for an isotopic verification facility by which 235U isotopic content is rapidly and nondestructively determined. The 185 keV gamma photon emitted by 235U is measured using a dual-channel gamma spectrometer which incorporates automatic background subtraction and an optimized collimator/NaI(Tl) detector assembly. Measured activities are then related to 235U isotopic content by means of appropriate standards that have been destructively analyzed in the laboratory. Use of the described facility for the past seven years has resulted in improved nuclear safety procedures, better use of storage space and more stringent nuclear materials accountability

  19. Fractionation of 238U/235U by reduction during low temperature uranium mineralisation processes

    Murphy, Melissa J.; Stirling, Claudine H.; Kaltenbach, Angela; Turner, Simon P.; Schaefer, Bruce F.

    2014-02-01

    Investigations of ‘stable’ uranium isotope fractionation during low temperature, redox transformations may provide new insights into the usefulness of the 238U/235U isotope system as a tracer of palaeoredox processes. Sandstone-hosted uranium deposits accumulate at an oxidation/reduction interface within an aquifer from the low temperature reduction of soluble U(VI) complexes in groundwaters, forming insoluble U(IV) minerals. This setting provides an ideal environment in which to investigate the effects of redox transformations on 238U/235U fractionation. Here we present the first coupled measurements of 238U/235U isotopic compositions and U concentrations for groundwaters and mineralised sediment samples from the same redox system in the vicinity of the high-grade Pepegoona sandstone-hosted uranium deposit, Australia. The mineralised sediment samples display extremely variable 238U/235U ratios (herein expressed as δUCRM145238, the per-mil deviation from the international NBL standard CRM145). The majority of mineralised sediment samples have δUCRM145238 values between -1.30±0.05 and 0.55±0.12‰, spanning a ca. 2‰ range. However, one sample has an unusually light isotopic composition of -4.13±0.05‰, which suggests a total range of U isotopic variability of up to ca. 5‰, the largest variation found thus far in a single natural redox system. The 238U/235U isotopic signature of the mineralised sediments becomes progressively heavier (enriched in 238U) along the groundwater flow path. The groundwaters show a greater than 2‰ variation in their 238U/235U ratios, ranging from δUCRM145238 values of -2.39±0.07 to -0.71±0.05‰. The majority of the groundwater data exhibit a clear systematic relationship between 238U/235U isotopic composition and U concentration; samples with the lowest U concentrations have the lowest 238U/235U ratios. The preferential incorporation of 238U during reduction of U(VI) to U(IV) and precipitation of uranium minerals leaves

  20. Standard test method for measurement of 235U fraction using enrichment meter principle

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 This test method covers the quantitative determination of the fraction of 235U in uranium using measurement of the 185.7 keV gamma-ray produced during the decay of 235U. 1.2 This test method is applicable to items containing homogeneous uranium-bearing materials of known chemical composition in which the compound is considered infinitely thick with respect to 185.7 keV gamma-rays. 1.3 This test method can be used for the entire range of 235U fraction as a weight percent, from depleted (0.2 % 235U) to highly enriched (97.5 % 235U). 1.4 Measurement of items that have not reached secular equilibrium between 238U and 234Th may not produce the stated bias when low-resolution detectors are used with the computational method listed in Annex A2. 1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.6 This standard may involve hazardous materials, operations, and equipment. This standard does not purport to address all of the safety co...

  1. Fine structure at the diffusion welded interface of Fe3Al/Q235 dissimilar materials

    Wang Juan; Li Yajiang; Wu Huiqiang

    2001-12-01

    The interface of Fe3Al/Q235 dissimilar materials joint, which was made by vacuum diffusion welding, combines excellently. There are Fe3Al, FeAl phases and -Fe (Al) solid solution at the interface of Fe3Al/Q235. Aluminum content decreases from 28% to 1.5% and corresponding phase changes from Fe3Al with DO3 type body centred cubic (bcc) structure to -Fe (Al) solid solution with B2 type bcc structure. All phases are present in sub-grain structure level and there is no obvious brittle phases or micro-defects such as pores and cracks at the interface of Fe3Al/Q235 diffusion joint.

  2. Determination of parameters of Johnson-Cook models of Q235 B steel%Q235 B钢Johnson-Cook模型参数的确定

    林莉; 支旭东; 范锋; 孟上九; 苏俊杰

    2014-01-01

    使用万能材料试验机、扭转试验机和霍普金森拉杆装置研究了Q235B钢在常温~950℃的准静态、动态力学性能,获得了Q235 B强度与等效塑性应变,应变率和温度的关系以及延性与应力三轴度,应变率和温度的关系。基于实验结果,修改了Johnson-Cook(J-C)强度模型中的应变强化项以及Johnson-Cook失效模型中的温度软化项,并结合数值仿真标定了相关模型参数。最后通过Taylor撞击试验验证了模型参数的有效性。%Strength and ductility data for Q235 B steel from 20 ℃ to 950 ℃ were obtained from tension tests with smooth cylindrical specimens (SCSs).The strain rate sensitivity was studied by conducting split hopkinson tension bar (SHTB)tests and uniaxial tension tests of SCSs.The influence of stress triaxiality on ductility was revealed by conducting upsetting tests of cylinder specimens,tension tests of pre-notched cylinder specimens and torsion tests of SCSs.Slightly modified versions of two Johnson-Cook (J-C ) models describing flow stress and failure strain were presented to characterize the properties of Q235 B steel as a function of strain rate,temperature and stress triaxiality.The corresponding model parameters were calibrated based on the test data and with the help of finite element simulation.The validity of the model parameters was verified with Taylor impact tests.

  3. Determination of 235U isotope abundance by measuring selected pairs of fission products

    A new method to determine experimentally the isotopic abundance of uranium has been developed by measuring the ratios of selected fission product pairs. The relationship between the 235U abundance and the ratios of 14 MeV neutron-induced fission products, which are N(3892Sr)/N(44105Ru) and N(3892Sr)/N(53135I), have been obtained. The results of 4 test samples show that the relative deviations between the measured and the reference 235U abundances are less than ±3%.

  4. Determination of U235 enrichment from nuclear fuel by neutronic activation

    The enrichment of 235U in UO2 pellets samples through the instrumental neutron activation analysis method (I.N.A.A.) was determined. By high resolution gamma-ray spectrometry (H.R.G.S.), from analysis of isotopic ratios between fission products peaks from 235U and 239Np different energies peaks from 238U, the enrichment was achieved. The 'Boatstrap' statistics technique for the analytical results, which is based in shaping results of an unknown distribution to the Gaussian distribution by B replications in interested statistics such as: the mean and its standard error, was introduced. (M.J.C.)

  5. Corrosion Resistance of Plasma Sprayed Ceramic CompositeCoatings on Q235 Substrate

    2001-01-01

    The corrosion resistance of SiO2/Al2O3, TiO2/Al2O3 and (SiO2+TiO2)/Al2O3 ceramic composite coatings on Q235 substrate fabricated by means of plasma spraying was investigated. The results show that Al2O3+13 wt pct TiO2 ceramic coating has the highest density, the lowest connected porosity and the best corrosion resistance. The corrosion mechanism of Q235 with ceramic coating has also been studied.

  6. Analysis of the 235U neutron cross sections in the resolved resonance range

    Using recent high-resolution measurements of the neutron transmission of 235U and the spin-separated fission cross-section data of Moore et al., a multilevel analysis of the 235U neutron cross sections was performed up to 300 eV. The Dyson Metha Δ3 statistics were used to help locate small levels above 100 eV where resonances are not clearly resolved even in the best resolution measurements available. The statistical properties of the resonance parameters are discussed

  7. Analysis of the 235U neutron cross sections in the resolved resonance range

    Using recent high-resolution measurements of the neutron transmission of 235U and the spin-separated fission cross-section data of Moore et al., a multilevel analysis of the 235U neutron cross sections was performed up to 300 eV. The Dyson Metha Δ3 statistics were used to help locate small levels above 100 eV where resonances are not clearly resolved even in the best resolution measurements available. The statistical properties of the resonance parameters are discussed. 13 refs., 8 figs., 1 tab

  8. Total kinetic energy release in the fast neutron-induced fission of $^{235}$U

    Yanez, R; Loveland, W.; King, J.; Barrett, J. S.; Fotiades, N.; Lee, H. Y.

    2015-01-01

    We have measured the total kinetic energy (TKE) release for the $^{235}$U(n,f) reaction for $E_{n}$=2-100 MeV using the 2E method with an array of Si PIN diode detectors. The neutron energies were determined by time of flight measurements using the white spectrum neutron beam at the LANSCE facility. (To calibrate the apparatus, the TKE release for $^{235}$U(n$_{th}$,f) was also measured using a thermal neutron beam from the OSU TRIGA reactor). The TKE decreases non-linearly from 169.0 MeV to ...

  9. Total kinetic energy release in the fast neutron-induced fission of $^{235}$U

    Yanez, R; Loveland, W.; King, J.; Barrett, J. S.; Fotiades, N.; Lee, H. Y.

    2016-01-01

    We have measured the total kinetic energy (TKE) release for the $^{235}$U(n,f) reaction for $E_{n}$=2-100 MeV using the 2E method with an array of Si PIN diode detectors. The neutron energies were determined by time of flight measurements using the white spectrum neutron beam at the LANSCE facility. To benchmark the TKE measurement, the TKE release for $^{235}$U(n$_{th}$,f) was also measured using a thermal neutron beam from the Oregon State University TRIGA reactor, giving pre-neutron emissi...

  10. ASSOCIATION OF ANGIOTENSINOGEN GENE M235T VARIANT IN PRE-ECLAMPSIA

    Pre-eclampsia (PE) is multisystem and multifactorial complication of pregnancy. The precise cause of pre-eclampsia has not been determined but mal adoption of the rennin and angiotensinogen (AGT) system may play a role. The products of genes involving the components of this system may be potential candidates for pre-eclampsia and hypertension related to pregnancy. This study was designed to determine whether the M235T variants of AGT gene were associated with the prevalence of pre-eclampsia and also to evaluate the role of plasma AGT in the development of the disease. Hence, developed, rapid and reliable PCR based assay was used to screen individuals for the M235T alleles. This assay was also used to genotype prospectively both recruited pregnant women with pre-eclampsia (n=24) and controls (n=11). Plasma AGT was determined by radioimmunoassay (RIA). The results of the PCR based assay revealed a significant association of 235T allele with the prevalence of all pre-eclamptic patients, Chi-square (x2) = 3.714, P0.05). Also, pre-eclamptic women exhibited significant higher levels of plasma AGT (52.15 ± 1.63) versus controls (44.76 ± 4.6) with P value < 0.001. This gave clear evidence that T235T allele and plasma AGT contributed to the development of pre-eclampsia with pregnancy and correlated with severity of the disease

  11. 19 CFR 10.235 - Filing of claim for preferential tariff treatment.

    2010-04-01

    ... 19 Customs Duties 1 2010-04-01 2010-04-01 false Filing of claim for preferential tariff treatment... Trade Partnership Act § 10.235 Filing of claim for preferential tariff treatment. (a) Declaration. In connection with a claim for preferential tariff treatment for an article described in § 10.233(a)(1)...

  12. An ideal cascade for uranium 235 enrichment by centrifuge jet nozzle process

    The design of an ideal cascade for the process of isotope separation by centrifugation for the U235 enrichment, is presented. A selection of building materials used in fabrication of isotope separation plants, showing the importance of aluminium, due the bauxite mines in Northern Brazil, is done. (M.C.K.)

  13. Calculation of Prompt Fission Neutron Spectra for ~(235)U (n,f)

    2011-01-01

    The prompt fission neutron spectra for neutron-induced fission of 235U at En<5 MeV are calculated using the nuclear evaporation theory with a semi-empirical model, in which the non-constant temperature and the constant temperature related to the Fermi gas model

  14. 50 CFR 23.5 - How are the terms used in these regulations defined?

    2010-10-01

    ... participate in or support a recovery activity for that species in cooperation with one or more of the species... ENDANGERED SPECIES OF WILD FAUNA AND FLORA (CITES) Introduction § 23.5 How are the terms used in these... context otherwise requires, in this part: Affected by trade means that either a species is known to be...

  15. Relationship of blood pressure variability and angiotensinogen T235M polymorphism with Binswanger’s disease

    位慧芳

    2013-01-01

    Objective To detect the relationship of blood pressure variability(BPV) and angiotensinogen(AGT) T235M polymorphism with Binswanger’s disease(BD). Methods Totally 122 cases with BD and 108 cases with essential hypertension had been enrolled. Ambulatory blood pressure monitoring was used to get the data

  16. Verification of 235U mass content in nuclear fuel plates by an absolute method

    Nuclear Safeguards is referred to a verification System by which a State can control all nuclear materials (NM) and nuclear activities under its authority. An effective and efficient Safeguards System must include a system of measurements with capabilities sufficient to verify such NM. Measurements of NM using absolute methods could eliminate the dependency on NM Standards, which are necessary for other relative or semi-absolute methods. In this work, an absolute method has been investigated to verify the 235U mass content in nuclear fuel plates of Material Testing Reactor (MTR) type. The most intense gamma-ray signature at 185.7 keV emitted after α-decay of the 235U nuclei was employed in the method. The measuring system (an HPGe-spectrometer) was mathematically calibrated for efficiency using the general Monte Carlo transport code MCNP-4B. The calibration results and the measured net count rate were used to estimate the 235U mass content in fuel plates at different detector-to-fuel plate distances. Two sets of fuel plates, containing natural and low enriched uranium, were measured at the Fuel Fabrication Facility. Average accuracies for the estimated 235U masses of about 2.62% and 0.3% are obtained for the fuel plates containing natural and low enriched uranium; respectively, with a precision of about 3%

  17. MGAU: A new analysis code for measuring {sup 235}U enrichments in arbitrary samples

    Gunnink, R.; Ruhter, W.D.; Miller, P. [Lawrence Livermore National Lab., CA (United States); Goerten, J.; Swinhoe, M.; Wagner, H. [Commission of the European Communities, Luxembourg (Luxembourg). Safeguards Directorate; Verplancke, J. [Canberra Applied Systems Europe, Zellik (Belgium); Bickel, M.; Abousahl, S. [Inst. for Reference Materials and Measurements, Geel (Belgium)

    1994-01-14

    We have developed a computerized analysis method for determining {sup 235}U enrichment in uranium items where no suitable reference standards exist or where nonreproducible conditions make calibration impossible. The method requires no calibrations and is capable of accuracies of 1--2% in only a few minutes.

  18. MGAU: A new analysis code for measuring 235U enrichments in arbitrary samples

    We have developed a computerized analysis method for determining 235U enrichment in uranium items where no suitable reference standards exist or where nonreproducible conditions make calibration impossible. The method requires no calibrations and is capable of accuracies of 1--2% in only a few minutes

  19. Determination of 235U isotope abundance by difference method of fission yield

    Background: Determination of the uranium isotope abundance ratio of fuel pins is a significant stage for the quality control in safe operations of reactor. Purpose: The aim is to establish a method to examine the 235U abundance of fuel rod with fast neutron as an excitation source. Methods: Taking the fission-yield ratios of Y-bar88Rb/Y-bar104Tc and Y-bar92Sr/Y-bar104Tc as the subjects of research, the relation curves between the average yield ratios and the 235U isotopic abundance as well as the expressions Y-bar1/Y-bar2=f(H0), in which the average yield ratio (Y-bari/Y-barj ) is a function of the 235U isotopic abundance (H0), were obtained and presented based on the previous studies. Results: In order to testify the accuracy of the method, the simulation sample of 72.2% is measured by working curve, and RSD is less than 2%. Within the limit of error, the results of sample analysis are in correspondence with those of passive gamma ray method. Conclusion: All of these results indicate that the method is feasible to determine the 235U abundance of fuel rod. (authors)

  20. 33 CFR 183.235 - Level flotation test without weights for persons capacity.

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Level flotation test without..., DEPARTMENT OF HOMELAND SECURITY (CONTINUED) BOATING SAFETY BOATS AND ASSOCIATED EQUIPMENT Flotation Requirements for Outboard Boats Rated for Engines of More Than 2 Horsepower Tests § 183.235 Level...

  1. 40 CFR 266.235 - What waste treatment does the storage and treatment conditional exemption allow?

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false What waste treatment does the storage... HAZARDOUS WASTES AND SPECIFIC TYPES OF HAZARDOUS WASTE MANAGEMENT FACILITIES Conditional Exemption for Low-Level Mixed Waste Storage, Treatment, Transportation and Disposal. Treatment § 266.235 What...

  2. Quantification of 235 U and 226 Ra in soil samples by means of Gamma spectroscopy

    In this work it is presented the Gamma Spectroscopy method which is realized in the Environmental Radiological Surveillance Laboratory using the option of deconvolution of a commercial software for the quantification of 235 U and 226 Ra; also is presented the method for the 226 Ra correction activity. (Author)

  3. 78 FR 68813 - Foreign-Trade Zone 235-Lakewood, New Jersey Application for Reorganization/Expansion Under...

    2013-11-15

    ... (Board Order 1008, 63 FR 67854, 12/09/98) and expanded on November 20, 2008 (Board Order 1589, 73 FR... Foreign-Trade Zones Board Foreign-Trade Zone 235--Lakewood, New Jersey Application for Reorganization...) Board by the Township of Lakewood, New Jersey, grantee of FTZ 235, requesting authority to...

  4. 29 CFR 2.35 - Effect of DOL support on Title VII employment nondiscrimination requirements and on other...

    2010-07-01

    ... 29 Labor 1 2010-07-01 2010-07-01 true Effect of DOL support on Title VII employment nondiscrimination requirements and on other existing statutes. 2.35 Section 2.35 Labor Office of the Secretary of... Effect of DOL support on Title VII employment nondiscrimination requirements and on other...

  5. Application of double nuclear system concept for description of mass distribution of the 235U+n fission products

    A total mass distribution of the 235U+n nuclei fission fragments on the all mass (charge) range is obtained. The calculation data have good agreement with the experimental results that confirms the correct choice of theoretical model and concept of the nuclear complex formation (double nuclear system) like an intermediate system for description of the 235U+n fission processes

  6. Effects of NVP-BEZ235 on the proliferation, migration, apoptosis and autophagy in HT-29 human colorectal adenocarcinoma cells.

    Yu, Yang; Yu, Xiaofeng; Ma, Jianxia; Tong, Yili; Yao, Jianfeng

    2016-07-01

    The phosphoinositide 3 kinase (PI3K)/Akt/mammalian target of the rapamycin (mTOR) pathway plays a significant role in colorectal adenocarcinoma. NVP-BEZ235 (dactolisib) is a novel dual inhibitor of PI3K/mTOR. The effects of NVP-BEZ235 in human colorectal adenocarcinoma are still unclear. In the present study, we aimed to explore the proliferation, migration, apoptosis and autophagy in HT-29 human colorectal adenocarcinoma cells. HT-29 human colorectal adenocarcinoma cells were treated with NVP-BEZ235 (0, 0.001, 0.01, 0.1, 1 and 3 µM) for 24 and 48 h, respectively. Cells were also treated with NVP-BEZ235 (0.1 µM), DDP (100, 300 and 1,000 µM), and NVP-BEZ235 (0.1 µM) combined with DDP (100, 300 and 1,000 µM) respectively, and cultured for 24 h after treatment. MTT assay was utilized to evaluate the effects of NVP-BEZ235 alone or NVP-BEZ235 combined with cis-diamminedichloroplatinum (DDP) on proliferation of HT-29 cells. Cell wound-scratch assay was used detect cell migration. In addition, expression of microtubule-associated proteins 1A/1B light chain 3B (MAP1LC3B and LC3B) in HT-29 cells was detected by immunofluorescence at 48 h after NVP-BEZ235 (1 µM) treatment. Expression of proteins involved in cell cycle and proliferation (p-Akt, p-mTOR and cyclin D1), apoptosis (cleaved caspase-3), and autophagy (cleaved LC3B and Beclin-1) were detected by western blot analysis. NVP-BEZ235 inhibited the proliferation and migration of HT-29 human colorectal adenocarcinoma cells. NVP-BEZ235 decreased protein expression of p-Akt, p-mTOR and cyclin D1, and increased protein expression of cleaved caspase-3, cleaved LC3B and Beclin-1 as the concentrations and the incubation time of NVP-BEZ235 increased. In addition, NVP-BEZ235 and DDP had synergic effects in inhibiting cell proliferation and migration. The expression of protein involved in apoptosis (cleaved caspase-3) was higher in drug combination group compared to the NVP-BEZ235 single treatment group. NVP-BEZ235

  7. Electron microscopic and agarose gel electrophoretic studies on apoptosis in immune cells induced by enriched 235U

    At present, the apoptosis in Molt-4 cell (a human acute lymphoblastic leukemia cell line) and Ana-1 cell (a macrophage cell line) were studied after internal irradiation with enriched 235U. The cumulative radiation absorption dose of 235U in cultural cells through different periods were estimated. The morphological changes, which observed by electron microscopy, indicated that Molt-4 and Ana-1 immune cells after incubation with 235U, displayed nuclear fragmentation, margination of condensed chromatin, as well as the membrane-bounded apoptotic bodies formation. The agarose gel electrophoretic observations showed the DNA ladder pattern formation in Molt-4 cell as well as in Ana-1 cell. The experimental results showed that apoptosis induced by 235U in immune cells, were dependent on the 235U-treated time and cumulative radiation absorption dose

  8. A comparison of pitting susceptibility of Q235 and HRB335 carbon steels used for reinforced concrete

    GUOLIANG ZHAN

    2013-02-01

    Full Text Available The phase structure and the pitting susceptibility of two carbon steels, Q235 and HRB335, used for reinforced concrete, are investigated by phase observation, polarization curve measure-ments, electrochemical impedance spectroscopy, and Mott-Schottky analysis. It is found that Q235 is ferrite and HRB335 is pearlite. Q235 is more susceptible to chloride ions leading to pit-ting than HRB335. The polarization curves show that the breakdown potential of the passive film in saturated Ca(OH2 solution containing 0.4 M NaCl is 0 V for Q235 and 0.34 V for HRB335. The Mott-Schottky analyses show that passive films formed on Q235 and HRB335 in saturated Ca(OH2 solution containing chloride ions behave like an n-type semiconductor. The passive film formed on Q235 has a higher donor density, which explains why Q235 is more susceptible to pitting than HRB335.

  9. Simultaneous evaluation for (n,f) cross section of 235U, 239Pu, 238U and (n,γ) cross sections of 238U

    The fission cross sections for 235U, 238U, 239Pu, the capture cross sections for 238U and the ratios for 239Pu(n,f)/235U(n,f), 238U(m,f)/235U(n,f), 238U(n,γ)/235U(n,f) were firstly evaluated respectively. The experimental data were collected, analysed, selected and corrected. The data were fitted with spline fit program

  10. Fuel cycle cost comparison of choices in U-235 recycle in the HTGR

    An analysis of alternative options for the recycle of discharged makeup U-235 (''residual'' makeup) in HTGRs shows that the three-particle system which has been the reference plan remains optimal. This result considers both the resource utilization and the handling costs attendant to the alternative strategies (primarily in the recycle facility and in waste disposal). Furthermore, this result appears to be true under all forseeable economic conditions. A simple risk assessment indicates that recycle cost (including reprocessing, refabrication, and related waste disposal) would have to double or triple in order for the alternative U-235 recycle schemes to become attractive. This induces some degree of confidence in the choice of staying with the reference cycle in spite of the large degree of uncertainty over recycle and its costs

  11. The 235U Prompt Fission Neutron Spectrum in the BR1 Reactor at SCK•CEN

    Wagemans, Jan; Malambu, Edouard; Borms, Luc; Fiorito, Luca

    2016-02-01

    The BR1 research reactor at SCK•CEN has a spherical cavity in the graphite above the reactor core. In this cavity an accurately characterised Maxwellian thermal neutron field is present. Different converters can be loaded in the cavity in order to obtain other types of neutron (and gamma) irradiation fields. Inside the so-called MARK III converter a fast 235U(n,f) prompt fission neutron field can be obtained. With the support of MCNP calculations, irradiations in MARK III can be directly related to the pure 235U(n,f) prompt fission neutron spectrum. For this purpose MARK III spectrum averaged cross sections for the most relevant fluence dosimetry reactions have been determined. A calibration factor for absolute measurements has been determined applying activation dosimetry following ISO/IEC 17025 standards.

  12. Active Neutron Interrogation and Delayed Neutron Counting (AIDNEC) for assay of 235U

    A method has been developed for non destructive assay of 235U using active neutron interrogation followed by delayed neutron counting (AIDNEC) system. The neutrons from a plasma focus (PF) device were used to bombard the samples containing low enriched uranium ranging from 13 mg to 5 g. The PF device generates (1.2±0.3) x109 D-D fusion neutrons per shot with a pulse width of 46±5 ns. The delayed neutrons were monitored using a bank of six 3He detectors. The sensitivity of the system was found to be about 1000 cps per gram over the accumulation time of 25 seconds per neutron pulse of ∼109. The detection limit of the system is estimated to be 18 mg of 235U. (author)

  13. Studies of Neutron-Induced Fission of 235U, 238U, and 239Pu

    Duke, Dana; TKE Team

    2014-09-01

    A Frisch-gridded ionization chamber and the double energy (2E) analysis method were used to study mass yield distributions and average total kinetic energy (TKE) release from neutron-induced fission of 235U, 238U, and 239Pu. Despite decades of fission research, little or no TKE data exist for high incident neutron energies. Additional average TKE information at incident neutron energies relevant to defense- and energy-related applications will provide a valuable observable for benchmarking simulations. The data can also be used as inputs in theoretical fission models. The Los Alamos Neutron Science Center-Weapons Neutron Research (LANSCE - WNR) provides a neutron beam from thermal to hundreds of MeV, well-suited for filling in the gaps in existing data and exploring fission behavior in the fast neutron region. The results of the studies on 238U, 235U, and 239Pu will be presented. LA-UR-14-24921.

  14. Determination of U-235 quantity in fresh fuel elements by neutron coincidence collar technique

    The U-235 quantity per lenght of fresh fuel assemblies of the Angra-I first recharge was determined by Neutron Coincidence Collar technique (N.C.C.). This technique is well-founded in fresh fuel assemblies activation by thermal neutrons from AmLi source to generate U-235 fission neutrons. These neutrons are detected by coincidence method in polyethylene structure where 18 He-3 detectors were placed. The coincidence counting results, in active mode (AmLi), showed 0,7% to standard deviation and equal to 1,49% to mass in 1000s of counting. The accuracies of different calibration methods were evaluated and compared. The results showed that the operator declared values are consistent. This evaluation was part of technical-exchange program between Safeguards Laboratory from C.N.E.N. and Los Alamos National Lab., United States. (author)

  15. Candidate processes for diluting the 235U isotope in weapons-capable highly enriched uranium

    The United States Department of Energy (DOE) is evaluating options for rendering its surplus inventories of highly enriched uranium (HEU) incapable of being used to produce nuclear weapons. Weapons-capable HEU was earlier produced by enriching uranium in the fissile 235U isotope from its natural occurring 0.71 percent isotopic concentration to at least 20 percent isotopic concentration. Now, by diluting its concentration of the fissile 235U isotope in a uranium blending process, the weapons capability of HEU can be eliminated in a manner that is reversible only through isotope enrichment, and therefore, highly resistant to proliferation. To the extent that can be economically and technically justified, the down-blended uranium product will be made suitable for use as commercial reactor fuel. Such down-blended uranium product can also be disposed of as waste if chemical or isotopic impurities preclude its use as reactor fuel

  16. In-situ gamma-PHA measurements to support unconditional release of 235-F chiller units

    The Analytical Development Section of Savannah River Technology Center (SRTC) was requested by the Facility Decommission Division (FDD) to conduct in-situ gamma-ray pulse height analysis measurements to support the unconditional release of 235-F chiller units. The chiller units were used to cool process water in the 235-F facility. The measurements' main goal is to confirm that there is no process-related contaminants present on the chillers. For each of the two F-area clean water chillers, the authors have acquired ten gamma-ray pulse height analysis spectra. This report will discuss the purpose of the measurements, the experimental setup, data acquisition, calculations and results, and a conclusion of the study

  17. Calculation of prompt fission neutron spectra for 235U(n,f)

    CHEN Yong-Jing; JIA Min; TAO Xi; QIAN Jing; LIU Ting-Jin; SHU Neng-Chuan

    2012-01-01

    The prompt fission neutron spectra for the neutron-induced fission of 235U at En < 5 MeV are calculated using nuclear evaporation theory with a semi-empirical model,in which the nonconstant and constant temperatures related to the Fermi gas model are taken into account. The calculated prompt fission neutron spectra reproduce the experimental data well.For the n(thermal)+235U reaction,the average nuclear temperature of the fission fragment,and the probability distribution of the nuclear temperature,are discussed and compared with the Los Alamos model.The energy carried away by γ rays emitted from each fragment is also obtained and the results are in good agreement with the existing experimental data.

  18. Accurate determination of the 235U isotope abundance by gamma spectrometry

    The purpose of this manual is to serve as guide in applications of the Certified Reference Material EC-NRM-171/NBS-SRM-969 for accurate U-235 isotope abundance measurements on bulk uranium samples by means of gamma spectrometry. The manual provides a thorough description of this non-destructive assay technique. Crucial measurement parameters affecting the accuracy of the gamma-spectrometric U-235 isotope abundance determination are discussed in detail and, whereever possible, evaluated quantitatively. The correction terms and tolerance limits given refer both to physical and chemical properties of the samples under assay and to relevant parameters of typical measurement systems such as counting geometry, signal processing, data evaluation and calibration. (orig.)

  19. Statistical properties of the 235U resonance parameters up to 300 eV

    An accurate resonance analysis of the 235U neutron cross sections up to 300 eV is in progress for the ENDF/B-VI files. A detailed discussion of the data base and a description of the method of resonance analysis have been given elsewhere. The purpose of this paper is to report on the statistical properties of the 235U resonance parameters and compare our results with those of previous analyses. The statistical properties of nuclear levels are of both technical and theoretical interest. From the technical viewpoint, these properties are the basis for an extrapolation into the unresolved resonance region, which is of relevance to the calculation of effective group cross sections for reactor design. From the theoretical viewpoint, the resonance parameters obtained from a multilevel R-matrix analysis of a consistent set of neutron cross sections should satisfy a set of statistical properties arising from general properties of the nuclear Hamiltonian

  20. The 235U Prompt Fission Neutron Spectrum in the BR1 Reactor at SCK•CEN

    Wagemans Jan

    2016-01-01

    Full Text Available The BR1 research reactor at SCK•CEN has a spherical cavity in the graphite above the reactor core. In this cavity an accurately characterised Maxwellian thermal neutron field is present. Different converters can be loaded in the cavity in order to obtain other types of neutron (and gamma irradiation fields. Inside the so-called MARK III converter a fast 235U(n,f prompt fission neutron field can be obtained. With the support of MCNP calculations, irradiations in MARK III can be directly related to the pure 235U(n,f prompt fission neutron spectrum. For this purpose MARK III spectrum averaged cross sections for the most relevant fluence dosimetry reactions have been determined. A calibration factor for absolute measurements has been determined applying activation dosimetry following ISO/IEC 17025 standards.

  1. Chromosome aberrations induced in human lymphocytes by U-235 fission neutrons. Pt. 2

    Blood samples were spiked with Na-24 to study the separate effect of this nuclide on the incidence of chromosomal aberrations in neutron irradiated blood samples. A delay of 96 h was allowed before cultivation, so the results of chromosomal aberration analysis could be compared with the results obtained by direct irradiation of blood samples with U-235 fission neutrons. The absorbed dose was calculated using a simple conservative model. From the results obtained we can conclude that Na-24 alone was not the reason for the difference in the incidence of chromosomal aberrations between blood samples cultivated immediately after 'in vitro' irradiation by U-235 fission neutrons and samples which were cultivated after 96 h storage. (orig.)

  2. Evaluation of the fission cross sections for U-233 and U-235

    Activities of evaluation of nuclear data was started in Japan, 1963, and the results were published as JENDL-1., JENDL-2 and JENDL-3.1. The revised edition, JENDL-3.2 is now under preparation. The evaluation works of the fission cross sections for U-233 and U-235 and the encountered problems are discussed. For the 1 to 7 MeV region of U-233 cross section, the data by Poenitz adopted in JENDL-2 were discarded and finally ratio data by the Tohoku University were adopted in JENDL-3. The resolved resonance parameters for heavy nuclides including U-233 and U-235 are treated with the Reich-Moore formula in JENDL-3.2 instead of the previously used Breit and Wigner formula. (T.H.)

  3. Investigating Prompt Fission Neutron Emission from 235U(n,f) in the Resolved Resonance Region

    Göök Alf; Hambsch Franz-Josef; Oberstedt Stephan

    2016-01-01

    Investigations of prompt emission in fission is of importance in understanding the fission process in general and the sharing of excitation energy among the fission fragments in particular. Experimental activities at IRMM on prompt neutron emission from fission in response to OECD/NEA nuclear data requests is presented in this contribution. Main focus lies on currently on-going investigations of prompt neutron emission from the reaction 235U(n,f) in the region of the resolved resonances. For ...

  4. Measurement of 235U fission reaction-rates in combined device

    Fission reaction-rates of 235U (wrapped with Cd of 0.8 mm) in the combined setup were measured, using the enriched uranium fission chamber and capturing detector. The method of detecting the low-energy scattering, neutron background was studied. The experimental error is ±6.0%-±10.2%. The results was compared with the ones of 238U the fission reaction-rates. (authors)

  5. Criticality study of the storage of radioactive waste containing 235U

    The purpose of this study is to define the conditions of storage of nuclear waste drums containing 350 g of 235U (per drum). This study is valid for a square pitch stacking of cylindrical drums whose height/diameter ratio does not exceed 3. The reflector effect of concrete is taken into account. This study defines a conservative case that can be used under any hypothesis of moderation, of radiation coupling between drums and of fissile material density. (A.C.)

  6. Yields of Gamma- and X-Ray Radiation of Alpha-Decays of 235U

    Precise knowledge of gamma- and X-rays emission probabilities of uranium isotopes is vital for accurate gamma-spectrometric determination of the isotopic composition and quantity of uranium. The peak intensity ratio methods employing high resolution gammaspectrometry and intrinsic efficiency calibration approach are known to provide most accurate and reliable isotopic information. When applied to unshielded and moderately shielded material, these methods largely benefit from de-convolution of the 90-100 keV narrow spectral interval, which contains intense gamma- and X-ray lines of major uranium isotopes 235U and 238U. These are the 92.37 keV and 92.79 keV gamma-rays of 238U/234Th, and the 93.35 keV ThKα1 X-rays from alpha-decay of 235U. Although the emission probability ratios of these lines were accurately established, their absolute yields are still lacking accuracy. For instance, as resulted from recent study, the yields of 234Th lines become corrected by 30%, compared with their previous values. This consequently raised a question regarding validity of the yield data for the 93.35 keV line of 235U and triggered the present experimental study. This study was later extended to the reexamination of emission probabilities of other 235U gamma-lines with energies above 205 keV. The experimental data used in the current work was collected using SRM 969 and CRM 146 reference uranium samples. (author)

  7. Effect of laser cutting parameters on surface quality of low carbon steel (S235)

    I. Miraoui; M. Boujelbene; D. Katundi; E. Bayraktar; M. Zaied

    2012-01-01

    Purpose: This work analysis surface roughness parameters as a function of Laser power and cutting speed. The surface roughness parameters are determined after statistical analysis (ANOVA) and propose a simple mathematical model.Design/methodology/approach: Machining were carried out by Laser cutting (CO2) of sheet metal (low carbon steel, S235) produces different surface quality. The statistical processing of the experimental results enabled development of a mathematical model to calculate th...

  8. Measurements of delayed neutron parameters for U-235 and Np-237

    Loaiza, D.

    1997-07-01

    Delayed neutrons are emitted by excited nuclei formed in beta decay of fission products called delayed neutron precursors. About 1% of the total neutrons released in fission are delayed neutrons; however, this small fraction plays an important role in nuclear reactor control. The delayed neutrons determine the time-dependent behavior of reactors, and knowledge of parameters used to predict neutron emission rate is essential for establishing reactivity worths. The delayed neutron yields, decay constants, and the absolute yield for the six-group delayed neutrons have been measured for U-235 and Np-237. This experiment has been called for in the forecast of experiments needed to support operations in the US. The bare U-235 metal assembly Godiva IV at the Los Alamos Critical Experiment Facility (LACEF) provided the source of neutrons. Godiva IV generated about 10{sup 7} total fissions in the samples for the infinite and instantaneous irradiation needed to accentuate the shorter and longer-lived groups of delayed neutrons. The detection system used in the experiment consisted of 20 He-3 tubes embedded in a polyethylene cylinder. The delayed neutron activity resulting from the fast neutron-induced fission has been measured. The measured absolute yield for U-235 was determined to be 0.0163 {+-} 0.009 neutrons/fission. This value compares very well with the well-established Keepin absolute yield of 0.0165 {+-} 0.0005. The newly measured absolute yield value for Np-237 was 0.0126 {+-} 0.0007, which compares well to the recently reported value of 0.0129 {+-} 0.0004 by Saleh and Parish. The measured values for U-235 are corroborated with period (e-folding time) versus reactivity calculations.

  9. A Fast Test for Excessive U235 Concentrations in Enriched Fuel Elements

    This paper describes a new non-destructive method of detecting areas of enriched fuel elements containing excessive U235 , and an instrument designed to inspect uranium-aluminium alloy fuel for the NRU reactor using the new method. The new method is as precise as conventional methods but is m u c h faster. The improvement in test speed depends on the application, but typically m a y be a factor of four. Alternatively, the method m a y be used to improve the precision of the test without increasing the testing time. The method may be used when the U235 concentration in selected areas of a fuel element is estimated by measuring the intensity of 184-keV γ-rays (from the natural decay of U235 ) and when an area is considered acceptable if the measured intensity from it is less than a limiting intensity equivalent to the maximum allowable concentration. It the measured intensity is much less or much greater than the limiting intensity, much less time is required to make this decision than when they are nearly the same. The new method takes advantage of this. It thus inspects each area only as long as is necessary to make a decision with the required confidence. The average time taken in practical cases is less than that taken by conventional methods which inspect each area for a pre-selected time chosen to give the required confidence in the most difficult cases - when the measured and limiting intensities are nearly the same. The new method is based on sequential sampling theory. It may also be used to detect areas with undesirably low U235 concentration. (author)

  10. Statistical properties of the S-wave resonances of {sup 235}U

    Leal, L.C.; Derrien, H.; Larson, N.M.

    1997-06-01

    The resonance parameters of {sup 235}U in the energy range 0 eV to 2.25 keV were obtained from a generalized least squares analysis of a large set of experimental data using the Reich-Moore formalism in the fitting code SAMMY. The aim of the present paper is to present the statistical properties of the s-wave resonance parameters generated from this study.

  11. Uranium content and 235U/238U isotopic ratio in dental porcelain powders determined by neutron activation analysis

    The uranium contents and 235U/238U isotopic ratios in 48 dental porcelain powders of 8 brands marketed in Japan were determined by non-destructive neutron activation analysis. The photopeak counts of 277.6 keV of 239Np formed by the 238U(n,γ)239U (yield to)239Np + β- reaction and at 1.595.2 keV of 140La produced by 235U fission were measured with a Ge(Li) semiconductor detector system to determine the uranium content and 235U/238U isotopic ratio. The results of the analysis are tabulated and their significance discussed. (author)

  12. Fission fragment mass and angular distribution in 6,7Li+235,238U reactions

    Fission fragment (FF) angular distributions for 6,7Li+235,238U reactions and mass distributions for 6,7Li+ 238U reactions have been measured at energies near and above the Coulomb barrier. The angle integrated fission cross sections for 6Li induced reactions at sub-barrier energies are found to be higher than 7Li induced reactions possibly due to larger contribution of breakup induced fission in case of the former compared to the latter. The FF anisotropy for 6,7Li+235U was found to be smaller than 6,7Li+238U, manifesting the effect of target ground state spin. The statistical saddle point (SSP) model predictions were found to be consistent with the measured FF anisotropy for 6,7Li+235U, however they were under-estimated for 6,7Li+238U particularly at lower energies. Observation of larger FWHM of FF folding angle distribution and sharp increase in peak to valley ratio for FF mass distribution with the decrease in bombarding energy in 6,7Li+238U reactions confirms the presence of breakup induced fission. (authors)

  13. Fission fragment mass and angular distribution in 6,7Li+235,238U reactions

    Santra S.

    2013-12-01

    Full Text Available Fission fragment (FF angular distributions for 6,7Li+235,238U reactions and mass distributions for 6,7Li+238U reactions have been measured at energies near and above the Coulomb barrier. The angle integrated fission cross sections for 6Li induced reactions at sub-barrier energies are found to be higher than 7Li induced reactions possibly due to larger contribution of breakup induced fission in case of the former compared to the latter. The FF anisotropy for 6,7Li+235U was found to be smaller than 6,7Li+238U, manifesting the effect of target ground state spin. The statistical saddle point (SSP model predictions were found to be consistent with the measured FF anisotropy for 6,7Li+235U, however they were under-estimated for 6,7Li+238U particularly at lower energies. Observation of larger FWHM of FF folding angle distribution and sharp increase in peak to valley ratio for FF mass distribution with the decrease in bombarding energy in 6,7Li+238U reactions confirms the presence of breakup induced fission.

  14. Isotope fractionation of 238U and 235U during biologically-mediated uranium reduction

    Stirling, Claudine H.; Andersen, Morten B.; Warthmann, Rolf; Halliday, Alex N.

    2015-08-01

    A series of laboratory-controlled microbial experiments using gram-negative sulphate-reducing bacteria (Desulfovibrio brasiliensis) inoculated with natural uranium were performed to investigate 238U/235U fractionation during bacterially-mediated U reduction. Control experiments, without bacteria to drive U reduction, were conducted in parallel. Paired measurements of 238U/235U and U concentration for both the residual growth medium solution and the accumulated biologically-mediated precipitate were obtained using multiple-collector inductively coupled plasma mass spectrometry (MC-ICPMS). The control experiments show that only minor (similar α values. Competing processes such as U co-precipitation (e.g. adsorption) may act to lower the apparent value for α and possibly play a secondary role both in the microbial experiments of this study and in natural U reduction settings where variable α values are found. These results may suggest that microbes adept at inducing U(VI) reduction play a crucial role in facilitating significant 238U/235U isotope fractionation in nature.

  15. Resonance analysis and evaluation of the 235U neutron induced cross sections

    Neutron cross sections of fissile nuclei are of considerable interest for the understanding of parameters such as resonance absorption, resonance escape probability, resonance self-shielding,and the dependence of the reactivity on temperature. In the present study, new techniques for the evaluation of the 235U neutron cross sections are described. The Reich-Moore formalism of the Bayesian computer code SAMMY was used to perform consistent R-matrix multilevel analyses of the selected neutron cross-section data. The Δ3-statistics of Dyson and Mehta, along with high-resolution data and the spin-separated fission cross-section data, have provided the possibility of developing a new methodology for the analysis and evaluation of neutron-nucleus cross sections. The results of the analysis consists of a set of resonance parameters which describe the 235U neutron cross sections up to 500 eV. The set of resonance parameters obtained through a R-matrix analysis are expected to satisfy statistical properties which lead to information on the nuclear structure. The resonance parameters were tested and showed good agreement with the theory. It is expected that the parametrization of the 235U neutron cross sections obtained in this dissertation represents the current state of art in data as well as in theory and, therefore, can be of direct use in reactor calculations. 44 refs., 21 figs., 8 tabs

  16. Total kinetic energy release in the fast neutron-induced fission of $^{235}$U

    Yanez, R; King, J; Barrett, J S; Fotiades, N; Lee, H Y

    2016-01-01

    We have measured the total kinetic energy (TKE) release for the $^{235}$U(n,f) reaction for $E_{n}$=2-100 MeV using the 2E method with an array of Si PIN diode detectors. The neutron energies were determined by time of flight measurements using the white spectrum neutron beam at the LANSCE facility. To benchmark the TKE measurement, the TKE release for $^{235}$U(n$_{th}$,f) was also measured using a thermal neutron beam from the Oregon State University TRIGA reactor, giving pre-neutron emission $E^*_{TKE}=170.7\\pm0.4$ MeV in good agreement with known values. Our measurements are thus absolute measurements. The TKE in $^{235}$U(n,f) decreases non-linearly from 169.0 MeV to 161.4 MeV for $E_{n}$=2-90 MeV. Comparison of the data with the multi-modal fission model of Brosa indicates the TKE decrease is a consequence of the growth of symmetric fission and the corresponding decrease of asymmetric fission with increasing neutron energy. The average TKE associated with the Brosa superlong, standard I and standard II ...

  17. Molecular jet emission and a spectroscopic survey of S235AB

    Burns, R A; Hirota, T; Motogi, K; Imai, I; Omodaka, T

    2016-01-01

    Context. The S235AB star forming region houses a massive young stellar object which has recently been reported to exhibit possible evidence of jet rotation - an illusive yet crucial component of disk aided star formation theories. Aims. To confirm the presence of a molecular counterpart to the jet and to further study the molecular environment in in S235AB. Methods. We search for velocity wings in the line emission of thermal SiO (J=2-1, v=0), a tracer of shocked gas, which would indicate the presence of jet activity. Utilising other lines detected in our survey we use the relative intensities of intra species transitions, isotopes and hyperfine transitions to derive opacities, temperatures, column densities and abundances of various molecular species in S235AB. Results. The SiO (J=2-1, v=0) emission exhibits velocity wing of up to 75 km/s above and below the velocity of the star, indicating the presence of a jet. The molecular environment describes an evolutionary stage resemblant of a hot molecular core.

  18. New signposts of massive star formation in the S235A-B region

    Felli, M; Massi, F; Robberto, M; Cesaroni, Riccardo; Felli, Marcello; Massi, Fabrizio; Robberto, Massimo

    2006-01-01

    We report on new aspects of the star-forming region S235AB revealed through high-resolution observations at radio and mid-infrared wavelengths. Using the Very Large Array, we carried out sensitive observations of S235AB in the cm continuum (6, 3.6, 1.3, and 0.7) and in the 22 GHz water maser line. These were complemented with Spitzer Space Telescope Infrared Array Camera archive data to clarify the correspondence between radio and IR sources. We made also use of newly presented data from the Medicina water maser patrol, started in 1987, to study the variability of the water masers found in the region. S235A is a classical HII region whose structure is now well resolved. To the south, no radio continuum emission is detected either from the compact molecular core or from the jet-like structure observed at 3.3 mm, suggesting emission from dust in both cases. We find two new compact radio continuum sources (VLA-1 and VLA-2) and three separate maser spots. VLA-1 coincides with one of the maser spots and with a pre...

  19. Calculation of resonance self-shielding for 235U from 0 to 2250 eV

    Over the years, the evaluated 235U cross sections in the resolved energy range have been extensively revised. A major accomplishment was the first evaluation released to the ENDF/B-VI library. In that evaluation, the low energy range bound was lowered to 10-5 eV, and the upper limit raised to 2,250 eV. Several high-resolution measurements in conjunction with the Bayesian computer code SAMMY were used to perform the analysis of the 235U resonance parameters. SAMMY uses the Reich-Moore formalism, which is adequate for representing neutron cross sections of fissile isotopes, and a generalized least-squares (Bayes) technique for determining the energy-dependence of the neutron cross sections. Recently a re-evaluation of the 235U cross section in the resolved resonance region was completed. This evaluation has undergone integral tests in various laboratories throughout the USA and abroad. The evaluation has been accepted for inclusion in ENDF/B-VI release 5. The intent of this work is to present results of calculations of self-shielded fission rates carried out with these resonance parameters and to compare those fission rates with experimental data. Results of this comparison study provide an assessment of the resonance parameters with respect to the calculation of self-shielded group cross sections

  20. Activation Doppler Measurements on U 238 and U 235 in Some Fast Reactor Spectra

    Measurements of the Doppler effect in U-238 capture and U-235 fission have been made by means of the activation technique in three different neutron spectra in the fast critical assembly FR0. The experiments involved the irradiation of thin uranium metal foils or oxide disks, which were heated in a small oven located at the core centre. The measurements on U-238 were extended to 1780 deg K and on U-235 to 1470 deg K. A core region surrounding the oven was homogenized in order to facilitate the interpretation of results. The reaction rates in the uranium samples were detected by gamma counting. The experimental method was checked with regard to systematic errors by irradiations in a thermal spectrum. The data obtained for U-238 capture were corrected for the effect of neutron collisions in the oven wall, and were extrapolated to zero sample thickness. In the softest spectrum (core 5) a Doppler effect (relative increase in capture rate) of 0.260 ± 0.018 was obtained on heating from 343 to 1780 deg K, and in the hardest spectrum (core 3) the corresponding value was 0.030 ± 0.003. An appreciable Doppler effect in U-235 fission was obtained only in the softest spectrum, in which the measured increase in fission rate on heating from 320 to 1470 deg K was 0.007 ± 0.003

  1. Phytic acid as a corrosion inhibitor for 235 steel in NaCl solution%植酸自组装膜对Q235钢在氯化钠溶液中的缓蚀作用

    王凤平; 胡隋军; 唐丽娜

    2014-01-01

    The corrosion inhibition of phytic acid on Q235 steel in NaCl solution was investigated by weight loss technique ,scanning electronic microscopy and the energy spectrum of X rays .The results show that inhibition efficiency of phytic acid on Q 235 steel in NaCl solution is obviously different at different pH .Phytic acid can accelerate the corrosion rate of Q 235 steel under acidic condition .But under neutral and alkaline condition ,phytic acid has excellent corrosion inhibition for 235steel in NaCl solution .Nevertheless ,the corrosion inhibition efficiency of phytic acid for Q235 steel in NaCl solu-tion increases with increasing phytic acid concentration under neutral and alkaline condition .If the concentration of phytic acid is 0 .5% ,the inhibition efficiency is more than 90% .%从植物中提取的植酸作金属缓蚀剂对环境保护具有重要意义.采用失重法、扫描电子显微镜和X射线能谱研究了植酸对Q235钢在NaCl溶液中的缓蚀行为以及影响因素.失重实验结果表明,不同p H值植酸对Q 235钢的缓蚀效果明显不同,在酸性条件下植酸加速Q235钢的腐蚀,在中性及碱性条件下,植酸对Q235钢的腐蚀具有明显的抑制作用.中性或碱性条件下,NaCl溶液中植酸对Q235钢缓蚀效率随植酸浓度的增加而增加,植酸浓度达0.5%以上时,缓蚀效率高达90%以上.扫描电镜结果表明,植酸处理后的Q235钢表面生成膜在不同pH下明显不同,碱性条件下的生成膜明显好于酸性条件下的生成膜.

  2. Isotope fractionation of 238U and 235U during biologically-mediated uranium reduction

    Stirling, Claudine H.; Andersen, Morten B.; Warthmann, Rolf; Halliday, Alex N.

    2015-08-01

    A series of laboratory-controlled microbial experiments using gram-negative sulphate-reducing bacteria (Desulfovibrio brasiliensis) inoculated with natural uranium were performed to investigate 238U/235U fractionation during bacterially-mediated U reduction. Control experiments, without bacteria to drive U reduction, were conducted in parallel. Paired measurements of 238U/235U and U concentration for both the residual growth medium solution and the accumulated biologically-mediated precipitate were obtained using multiple-collector inductively coupled plasma mass spectrometry (MC-ICPMS). The control experiments show that only minor (<0.1‰), if any 238U/235U fractionation occurs during co-precipitation with calcite. This implies that carbonate sediments are capable of faithfully recording the signature of the global ocean during Earth's major climatic events, including oxygenation and de-oxygenation transitions in the marine environment. The results for the microbial experiments demonstrate that the 238U/235U composition of the unreacted growth medium containing U(VI) is isotopically lighter than the composition of the U(IV)-bearing precipitate as U(VI) is consumed, in agreement with field-based observations of microbially-mediated U reduction. Uranium isotopic shifts of up to 0.8‰ were observed between the liquid and solid phases. These observations can be modelled using a Rayleigh distillation approach describing kinetic uptake in a closed system, which yields a fractionation factor α of 0.99923 ± 0.00004 (ε = -0.77 ± 04‰) for U(VI)-U(IV) reduction mediated by the D. brasiliensis microbe. This fractionation behaviour is consistent with that observed in field-based redox environments, which give rise to similar α values. Competing processes such as U co-precipitation (e.g. adsorption) may act to lower the apparent value for α and possibly play a secondary role both in the microbial experiments of this study and in natural U reduction settings where

  3. An R matrix analysis of the 235U neutron-induced cross sections up to 500 eV

    In this paper a detailed evaluation of the R matrix resonance parameters describing the interaction of neutrons with 235U has been performed up to 500 eV using the most recent high-resolution measurements of the 235U neutron cross sections. The availability of 235U spin-separated neutron cross-section data, in conjunction with the use of the Δ3 statistics of Metha and Dyson, has made possible a detailed study of the statistical distribution of the resonance parameters and their average values. The present R matrix resonance parameters have been converted into equivalent sets of Adler- Adler parameters and multipole momentum space expansion parameters. Extensive validation of this evaluation has been performed by comparing self-shielded fission rates computed with these R matrix parameters with the measurements of Czirr; a test of the ENDF/B unresolved resonance formalism for the calculation of 235U of self-shielding factors is also presented

  4. Study of the origin of elements of the uranium-235 family observed in excess in the vicinity of the experimental nuclear EL4 reactor under dismantling. Lessons got at this day and conclusions; Etude de l'origine des elements de la famille de l'uranium-235 observes en exces dans les environs du reacteur nucleaire experimental EL4 en cours de demantelement. Enseignements retires a ce jour et conclusion

    NONE

    2007-07-01

    This study resumes the discovery of an excess of actinium 227 found around by EL4 nuclear reactor actually in dismantling. The search for the origin of this excess revealed a real inquiry of investigation during three years. Because a nuclear reactor existed in this area a particular attention will have concerned this region. The doubt became the line of conduct to find the answer to the human or natural origin of this excess. Finally and against any evidence, it appears that the origin of this phenomenon was natural, consequence of the particular local geology. The detail of the different investigations is given: search of a possible correlation with the composition of elevations constituent of lanes, search (and underlining) of new sites in the surroundings of the Rusquec pond and the Plouenez station, study of the atmospheric deposits under winds of the nuclear power plant and in the east direction, search of a possible relationship with the gaseous effluents of the nuclear power plant in the past, historical study of radioactive effluents releases in the fifty last years by the analysis of the sedimentary deposits in the Saint-Herbiot reservoir, search of a possible correlation between the excess of actinium 227 and the nuclear power plant activity; search of a possible correlation with a human activity without any relationship with the nuclear activities, search of a correlation with the underground waters, search of a correlation with the geological context, collect of information on the possible transfers in direction of the food chain, determination of the radiological composition of the underground waters ( not perturbed by human activity), search of the cause of an excess of actinium 227 in the old channel of liquid effluents release of the nuclear power plant. The results are given and discussed. And contrary to all expectations the origin of the excess of actinium 227 is completely natural. (N.C.)

  5. Neutron inelastic-scattering cross sections of 232Th, 233U, 235U, 238U, 239Pu and 240Pu

    Differential-neutron-emission cross sections of 232Th, 233U, 235U, 238U, 239Pu and 240Pu are measured between approx. = 1.0 and 3.5 MeV with the angle and magnitude detail needed to provide angle-integrated emission cross sections to approx. 232Th, 233U, 235U and 238U inelastic-scattering values, poor agreement is observed for 240Pu, and a serious discrepancy exists in the case of 239Pu

  6. Test spectra experimental construction for evaluating gamma-spectrometry computer codes for the 235U determination

    Karfopoulos Konstantinos L.

    2014-01-01

    Full Text Available The determination of 235U in environmental samples from its 185.72 keV photons may require the deconvolution of the multiplet photopeak at ~186 keV, due to the co-existence of the 186.25 keV photons of 226Ra in the spectrum. Successful deconvolution depends on many parameters, such as the detector characteristics, the activity concentration of the 235U and 226Ra in the sample, the background continuum in the 186 keV energy region and the gamma-spectrometry computer code used. In this work two sets of experimental test spectra were constructed for examining the deconvolution of the multiplet photopeak performed by different codes. For the construction of the test spectra, a high-resolution low energy germanium detector was used. The first series consists of 140 spectra and simulates environmental samples containing various activity concentration levels of 235U and 226Ra. The second series consists of 280 spectra and has been derived by adding 137Cs, corresponding to various activity concentration levels, to specific first series test spectra. As the 137Cs backscatter edge is detected in the energy region of the multiplet photopeak at ~186 keV, this second series of test spectra tests the analysis of the multiplet photopeak in high background continuum conditions. The analysis of the test spectra is performed by two different g-spectrometry analysis codes: (a spectrum unix analysis code, a computer code developed in-house and (b analysis of germanium detector spectra, a program freely available from the IAEA. The results obtained by the two programs are compared in terms of photopeak detection and photopeak area determination.

  7. Absolute measurement of $sup 235$U fission cross-section for 2200 m/sec neutrons

    Borcea, C.; Borza, A.; Buta, A.

    1973-12-31

    The results of an absolute fission cross-section measurement of /sup 235/ U are presented; the thermal neutrons were selected by the time-of-flight method. The principle of the method and the experimental apparatus are described. The method had the advantage of avoiding the use of an intermediate cross section in the neutron flux determination by choice of a B target thick enough to absorb all thermal neutrons. Target preparation, efficiency determination, corrections, etc., are reported. The value determined was 581.7 plus or minus 7.8 barns. (6 figures, 4 tables) (RWR)

  8. Measurement of reflect neutron for 252Cf in cement cylinder by method of 235U fission

    The experiment theory of Research of neutron reflected coefficient for 252Cf in cement reflector was introduced. The fission rate of 235U with reflector, without reflector and with background was measured. The neutron reflected coefficient with cement reflector was concluded from fission rate and the reflected coefficient for different neutron source in the same experiment model was compared. The relation of reflected coefficient with angle was analyzed. The technology of solid track was researched and the best etch condition was explored. The trend of discharge count with coders thickness and etch thickness was gained. Efficiency for spark auto counters was measured and the technology of solid track was developed. (authors)

  9. Neutron shielding verification measurements and simulations for a 235-MeV proton therapy center

    Newhauser, W D; Dexheimer, D; Yan, X; Nill, S

    2002-01-01

    The neutron shielding at the Massachusetts General Hospital's 235-MeV proton therapy facility was investigated with measurements, analytical calculations, and realistic three-dimensional Monte Carlo simulations. In 37 of 40 cases studied, the analytical calculations predicted higher neutron dose equivalent rates outside the shielding than the measured, typically by more than a factor of 10, and in some cases more than 100. Monte Carlo predictions of dose equivalent at three locations are, on average, 1.1 times the measured values. Except at one location, all of the analytical model predictions and Monte Carlo simulations overestimate neutron dose equivalent.

  10. Activity of HMR 3647 Compared to Those of Six Compounds against 235 Strains of Enterococcus faecalis

    Hoellman, Dianne B.; Lin, Gengrong; Jacobs, Michael R.; Appelbaum, Peter C.

    1999-01-01

    Agar dilution was used to test the activities of HMR 3647, erythromycin A, azithromycin, clarithromycin, roxithromycin, clindamycin, and quinupristin-dalfopristin against 235 strains of Enterococcus faecalis. HMR 3647 was the most active compound (MICs at which 50 and 90% of the isolates are inhibited [MIC50 and MIC90, respectively] of 0.06 and 4.0 μg/ml, respectively). The MIC50 and MIC90 (with the MIC50 given first and the MIC90 given second; both in micrograms per milliliter) for other com...

  11. Fission product yields from 22 MeV neutron-induced fission of 235U

    The chain yields of 28 product nuclides were determined for the fission of 235U induced by 22 MeV neutrons for the first time. Absolute fission rate was monitored with a double-fission chamber. Fission product activities were measured by HPGe γ-ray spectrometry. Time of flight technique was used to measure the neutron spectrum in order to estimate fission events induced by break-up neutrons and scattering neutrons. A mass distribution curve was obtained and the dependence of fission yield on neutron energy is discussed

  12. A `Water Spout' Maser Jet in S235AB-MIR

    Burns, Ross A.; Imai, Hiroshi; HANDA, Toshihiro; Omodaka, Toshihiro; Nakagawa, Akiharu; NAGAYAMA, Takumi; Ueno, Yuji

    2015-01-01

    We report on annual parallax and proper motion observations of H2O masers in S235AB-MIR, which is a massive young stellar object in the Perseus Arm. Using multi-epoch VLBI astrometry we measured a parallax of pi = 0.63 +- 0.03 mas, corresponding to a trigonometric distance of D = 1.56+-0.09 kpc, and source proper motion of ( u alpha cos d , u d) = (0.79 +- 0.12, -2.41 +- 0.14) mas/yr. Water masers trace a jet of diameter 15 au which exhibits a definite radial velocity gradient perpendicular t...

  13. New signposts of massive star formation in the S235A-B region

    Felli, M.; Massi, F.; Robberto, M.; Cesaroni, R.

    2006-07-01

    Aims.We report on new aspects of the star-forming region S235AB revealed through high-resolution observations at radio and mid-infrared wavelengths. Methods: .Using the Very Large Array, we carried out sensitive observations of S235AB in the cm continuum (6, 3.6, 1.3, and 0.7) and in the 22 GHz water maser line. These were complemented with Spitzer Space Telescope Infrared Array Camera archive data to clarify the correspondence between radio and IR sources. We made also use of newly presented data from the Medicina water maser patrol, started in 1987, to study the variability of the water masers found in the region. Results: .S235A is a classical HII region whose structure is now well resolved. To the south, no radio continuum emission is detected either from the compact molecular core or from the jet-like structure observed at 3.3 mm, suggesting emission from dust in both cases. We find two new compact radio continuum sources (VLA-1 and VLA-2) and three separate maser spots. VLA-1 coincides with one of the maser spots and with a previously identified IR source (M 1). VLA-2 lies towards S235B and represents the first radio detection from this peculiar nebula that may represent an ionized wind from a more evolved star. The two other maser spots coincide with an elongated structure previously observed within the molecular core in the C34S line. This structure is perpendicular to a bipolar molecular outflow observed in HCO+(1-0) and may trace the associated equatorial disk. The Spitzer images reveal a red object towards the molecular core. This is the most viable candidate for the embedded source originating the outflow and maser phenomenology. Conclusions: .The picture emerging from these and previous data shows the extreme complexity of a small (≤0.5 pc) star-forming region where widely different stages of stellar evolution are present.

  14. Critical experiments to determine amount of U-235 in research reactor fuel assemblies

    Four different critical core configurations of the IRR1 [Bettan, M., Hirshfeld H., Levine, S.H., 2002. Method to determine the burnup of the IRR1 fuel assemblies. In: Proceedings of the 21st Conference of the Nuclear Societies in Israel, p. 38-41], Cores 1, 2, 3, and 4, have been used to determine experimentally the reactivity changes caused by interchanging different fuel assemblies (FAs) in the same core position [Bettan, M., Hirshfeld H., Levine, S.H., 2002. Method to determine the burnup of the IRR1 fuel assemblies. In: Proceedings of the 21st Conference of the Nuclear Societies in Israel, p. 38-41; Levine, S.H., Kim, S.S., 1985. Development of an asymmetric multiple-position neutron source (AMPNS) method to monitor the criticality of a degraded reactor core. Ann. Nucl. Energy 12, 517; IAEA-TECDOC-633, 1992. Determination of research fuel burnup, January]. The different fuel assemblies varied in their burnup or loss in U-235 causing the core reactivity to change systematically with each FA interchange. The control blade height was altered to compensate for this change in the core reactivity to maintain the core critical. The control blade reactivity worth as a function of its height was measured by period measurements so that the reactivity change due to the interchange of an FA was determined. The WIMS/EXT2 [WIMS-D4: Winfrith Improved Multigroup Scheme (WIMS) code system, 1969. Computer Code Package CCC-576, RSICC/ORNL, Oak Ridge, TN; Fowler, T.B. et al., 1967. EXTERMINATOR-II: A FORTRAN IV Code for solving multigroup diffusion equations in two dimensions, ORNL-4078, ORNL, April] codes are used to evaluate the change in core reactivity as a function of FA U-235 or burnup. By relating the calculation of the reactivity change with the measured reactivity change, the burnup or U-235 mass in each FA is determined. The U-235 mass of the FAs gave good agreement between measurements made of the same FA in different cores and appears to bring better agreement between

  15. Neutron cross sections for uranium-235 (ENDF/B-IV Release 3)

    The resonance parameters in ENDF6 (Release 2) U235 were adjusted to make the average capture and fission cross sections below 900 eV agree with selected differential capture and fission measurements. The measurements chosen were the higher of the credible capture measurements and the lower of the fission results, yielding a higher epithermal alpha. In addition, the 2200 m/s cross sections were adjusted to obtain agreement with the integral value of K1. As a result, criticality calculations for thermal benchmarks, and agreement with a variety of integral parameters, are improved

  16. Test of the ENDF/B [Evaluated Nuclear Data File] unresolved resonance formalism for 235U

    It is common practice in ENDF/B [Evaluated Nuclear Data File] to represent neutron cross sections in the unresolved resonance region by specifying the average values and distribution laws of resonance parameters. This formalism allows the calculation of resonance self-shielding and of its variation with temperature. The purpose of this paper is to present a test of the validity of the formalism by comparing self-shielding factors computed with the ENDF/B unresolved formalism with values computed with the resolved resonance parameters recently evaluated for the neutron cross sections of 235U

  17. 235U fission product gamma spectra: a comparison between experiment and calculation

    Recent measurements of 235U fission product gamma spectra (ORNL), after reduction to a broad group structure, were compared with results of corresponding summation calculations which were made with the UKFPDD-1 fission product data base. In order to facilitate convenient integration of the summation results, weighted sums of decaying exponentials were accurately fitted to them using an iterative least-squares method described. The comparisons between experiment and calculation reveal significant deficiencies in data for short-lived nuclides which prevent the accurate calculation of short-term ( 5 MeV are also examined briefly and possible causes for them are discussed. (author)

  18. Beyond G-band : a 235 GHz InP MMIC amplifier

    Dawson, Douglas; Samoska, Lorene; Fung, A. K.; Lee, Karen; Lai, Richard; Grundbacher, Ronald; Liu, Po-Hsin; Raja, Rohit

    2005-01-01

    We present results on an InP monolithic millimeter- wave integrated circuit (MMIC) amplifier having 10-dB gain at 235 GHz. We designed this circuit and fabricated the chip in Northrop Grumman Space Technology's (NGST) 0.07- m InP high electron mobility transistor (HEMT) process. Using a WR3 (220-325 GHz) waveguide vector network analyzer system interfaced to waveguide wafer probes, we measured this chip on-wafer for -parameters. To our knowledge, this is the first time a WR3 waveguide on-wafer measurement system has been used to measure gain in a MMIC amplifier above 230 GHz.

  19. Are 0.1%-accurate gamma-ray assays possible for 235U solutions

    The factors influencing the accuracy of passive gamma-ray assay of uniform, homogeneous solution samples have been studied in some detail, particularly for the assay of 235U in uranium solutions. Factors considered are the overall long-term electronic stability, the information losses caused by the rate-related electronic processes of pulse pileup and dead-time, and the self-attenuation of gamma rays within the samples. Both experimental and computational studies indicate that gamma-ray assay procedures for solution samples of moderate size (from approx. 10 to perhaps a few hundred milliliters) are now capable of accuracies approaching 0.1% in many practical cases

  20. Comparison and validation of different 235U fast fission delayed neutron group parameters

    The differences between 235U fast fission delayed neutron group parameters in ENDF/B7, JEFF 3.1, JENDL 3.3, CENDL 2.2 and Keepin datum were analyzed. The delayed neutron group parameters were validated by experiments on CFBR-II. The Keepin delayed neutron group parameters are more accurate than delayed neutron group parameters in the primary nuclear databases. The eight-group delayed neutron parameters in JEEF 3.1 are better than six-group delayed neutron parameters in other databases. (authors)

  1. O polimorfismo AGT*M235T na disfunção cardíaca de etiologia isquêmica aguda: projeto gisca AGT*M235T polymorphism in acute ischemic cardiac dysfunction: the gisca project

    Claudia Guerra Murad Saud

    2010-08-01

    Full Text Available FUNDAMENTO: O polimorfismo AGT*M235T tem sido associado a elevados níveis séricos de angiotensinogênio (AGT, hipertensão arterial sistêmica e disfunção cardíaca (DC. OBJETIVO: Testar a hipótese de haver associação entre polimorfismo AGT*M235T e o risco de desenvolver disfunção cardíaca (insuficiência cardíaca ou disfunção sistólica ventricular esquerda assintomática pós-síndrome coronariana aguda (SCA, durante o período de internação hospitalar. MÉTODOS: Foram estudados 363 pacientes (idade média 62 ± 12 anos, sendo 233 (64% homens e 130 (36% mulheres, todos da mesma coorte, internados por SCA. Compararam-se dados clínicos e genéticos dos 117 (32,2% que evoluíram com disfunção cardíaca (grupo caso com os dos 246 (67,8%, que não desenvolveram tal condição (grupo controle. O polimorfismo AGT*M235T foi determinado por análise de sequenciamento e estava em equilíbrio de Hardy-Weinberg. RESULTADOS: Houve diferença significativa na distribuição dos genótipos nas mulheres, com predomínio do genótipo *235MM no grupo controle (p = 0,001 e do alelo *235T no grupo caso. Em ambos os sexos, nos modelos de regressão logística, o diagnóstico de infarto de parede anterior na admissão foi fator de incremento no risco de DC, enquanto angina instável na admissão, ausência do alelo *235T, glicemia 60 e BACKGROUND: AGT*M235T polymorphism has been associated with high serum angiotensinogen (AGT levels, systemic hypertension and cardiac dysfunction (CD. OBJECTIVE: To test the hypothesis of AGT*M235T polymorphism being associated with the risk of developing cardiac dysfunction (heart failure or asymptomatic left ventricular systolic dysfunction after acute coronary syndrome (ACS during hospitalization. METHODS: A total of 363 patients (mean age of 62 ± 12 years, of whom 233 (64% were men and 130 (36% were women, all from the same cohort and hospitalized for ACS, were studied. Clinical and genetic data from the 117

  2. Prompt Fission Neutron Experiments on 235U(n,f) and 252Cf(SF)

    Göök, A.; Hambsch, F.-J.; Oberstedt, S.; Vidali, M.

    For nuclear modeling and improved evaluation of nuclear data knowledge about fluctuations of the prompt neutron multiplicity as a function of incident neutron energy is requested for the major actinides 235U and 239Pu. Experimental investigations of the prompt fission neutron emission in resonance neutron induced fission on 235U are taking place at the GELINA facility of the IRMM. The experiment employs an array of neutron scintillation-detectors (SCINTIA) in conjunction with a newly designed 3D position sensitive twin Frisch-grid ionization chamber. A preparatory experiment on prompt fission neutron emission in 252Cf(SF) was undertaken to verify analysis procedures relevant for the implementation of the SCINTIA neutron detector array. The available literature data on the TKE dependence of the multiplicity show strong deviations. Therefore, effort was focused on investigating experimental factors in low efficiency neutron counting experiments that may lead to faulty determination of this dependence. Taking these factors into account a result that agree well with data from high efficiency neutron counting experiments is obtained.

  3. Propagation Channel Comparison between 23.5 and 45 GHz in Conference Scenario

    Jianwu Dou

    2016-01-01

    Full Text Available The characteristics of propagation channel at 23.5 and 45 GHz in an indoor conference room are studied based on hybrid approach. A ray-based simulator which includes the reflection, penetration, diffraction, and diffuse scattering is adopted to generate the massive channel realizations. This platform is well calibrated in path and power delay profile (PDP levels according to some specified measurements at different frequencies. Subsequently, according to the simulated channel samples, the statistical channel model for both the large and small scale characteristics is established based on the alpha-beta approach and extended Saleh-Valenzuela (S-V structure, respectively. Results show that the slope of fitted path loss (PL is less than free space due to the waveguide effect for both 23.5 and 45 GHz in indoor scenario and larger PL is experienced at higher frequency. Additionally, the cluster is more centralized with less spreads and decaying faster in delay domain at 45 GHz.

  4. New Precision Measurements of the U235(n,γ) Cross Section

    Jandel, M.; Bredeweg, T. A.; Bond, E. M.; Chadwick, M. B.; Couture, A.; O'Donnell, J. M.; Fowler, M.; Haight, R. C.; Kawano, T.; Reifarth, R.; Rundberg, R. S.; Ullmann, J. L.; Vieira, D. J.; Wouters, J. M.; Wilhelmy, J. B.; Wu, C. Y.; Becker, J. A.

    2012-11-01

    The neutron capture cross section of U235 was measured for the neutron incident energy region between 4 eV and 1 MeV at the DANCE facility at the Los Alamos Neutron Science Center with an unprecedented accuracy of 2-3% at 1 keV. The new methodology combined three independent measurements. In the main experiment, a thick actinide sample was used to determine neutron capture and neutron-induced fission rates simultaneously. In the second measurement, a fission tagging detector was used with a thin actinide sample and detailed characteristics of the prompt-fission gamma rays were obtained. In the third measurement, the neutron scattering background was characterized using a sample of Pb208. The relative capture cross section was obtained from the experiment with the thick U235 sample using a ratio method after the subtraction of the fission and neutron scattering backgrounds. Our result indicates errors that are as large as 30% in the 0.5-2.5 keV region, in the current knowledge of neutron capture as embodied in major nuclear data evaluations. Future modifications of these databases using the improved precision data given herein will have significant impacts in neutronics calculations for a variety of nuclear technologies.

  5. Fission-Neutron Spectra of U235, Pu239 And Cf252

    Measurements of the fission neutron spectra from the neutron-induced fission of U235 and Pu239, and the spontaneous fission of Cf252, have been made. The spectra were measured with a time-of-flight technique using a plastic scintillator as the fission-neutron detector. The low energy part of the Cf252 fission-neutron spectrum (below 0.3 MeV) was also measured with a Li6 -glass detector replacing the plastic scintillator. The fissile materials were mounted in xenon-gas scintillation cham-bers. The primary neutrons were produced by a 2.5-MeV Van de Graaff accelerator with top terminal pulsing. The resolving time of the time-of-flight equipment was better than 3 ns. Results fitted to Maxwellian distributions, √Ee-E/T, are presented for neutron-induced fissions of U235 at 40 keV and 1.5 MeV of incident neutron energy and for Pu239 at 40 keV. Results are also given for the fission-neutron energy spectrum of Cf252. (author)

  6. PC based manual and safety logic card test setup for 235 MWe PHWRs

    Fuel handling controls for 235 MWe PHWR make use of Manual and Logic cards (MLCs) for providing safety interlocks. These cards consist of various type of logic blocks. By connecting these logic blocks all the safety interlocks required for fuel handling controls have been provided. Previously trouble shooting of these cards was done by means of logic probe. Since the method was manual, it was laborious and time consuming. PC based test setup has overcome this drawback and detects the fault at the component level within few seconds. It also gives printout of status of faulty MLC cards. Here motherboard has been designed having slots for insertion of MLC cards. The input/output connection of these cards are coming to two 50 pin FRC connectors. PC communicates through 144 line digital input/output card with MLC card under test. Software is user friendly and outputs suitable input patterns to the card under test and checks for output pattern. It compares this output pattern with compare pattern and detects the fault and displays the symptoms. This system is currently in use at test facility for fuelling machine for 235 MWe PHWR reactor at Refuelling Technology Division, Hall-7. This test setup has been proposed for use at NAPP and future reactors. (author). 4 figs., 1 annexure

  7. Consistent Data Assimilation of Actinide Isotopes: 235U and 239Pu

    In this annual report we illustrate the methodology of the consistent data assimilation that allows to use the information coming from integral experiments for improving the basic nuclear parameters used in cross section evaluation. A series of integral experiments were analyzed using the EMPIRE evaluated files for 235U, 238U, and 239Pu. Inmost cases the results have shown quite large worse results with respect to the corresponding existing evaluations available for ENDF/B-VII. The observed discrepancies between calculated and experimental results were used in conjunction with the computed sensitivity coefficients and covariance matrix for nuclear parameters in a consistent data assimilation. Only the GODIVA and JEZEBEL experimental results were used, in order to exploit information relative to the isotope of interest that are, in this particular case: 235U and 239Pu. The results obtained by the consistent data assimilation indicate that with reasonable modifications (mostly within the initial standard deviation) it is possible to eliminate the original large discrepancies on the Keff of the two critical configurations. However, some residual discrepancy remains for a few fission spectral indices that are, most likely, to be attributed to the detector cross sections.

  8. A multi-wavelength study of star formation activity in the S235 complex

    Dewangan, L K; Luna, A; Anandarao, B G; Ninan, J P; Mallick, K K; Mayya, Y D

    2016-01-01

    We have carried out an extensive multi-wavelength study to investigate the star formation process in the S235 complex. The S235 complex has a sphere-like shell appearance at wavelengths longer than 2 $\\mu$m and harbors an O9.5V type star approximately at its center. Near-infrared extinction map traces eight subregions (having A$_{V}$ $>$ 8 mag), and five of them appear to be distributed in an almost regularly spaced manner along the sphere-like shell surrounding the ionized emission. This picture is also supported by the integrated $^{12}$CO and $^{13}$CO intensity maps and by Bolocam 1.1 mm continuum emission. The position-velocity analysis of CO reveals an almost semi-ring like structure, suggesting an expanding H\\,{\\sc ii} region. We find that the Bolocam clump masses increase as we move away from the location of the ionizing star. This correlation is seen only for those clumps which are distributed near the edges of the shell. Photometric analysis reveals 435 young stellar objects (YSOs), 59\\% of which ar...

  9. Molecular Emission in Dense Massive Clumps from the Star-Forming Regions S231-S235

    Ladeyschikov, D A; Tsivilev, A P; Sobolev, A M

    2016-01-01

    The article deals with observations of star-forming regions S231-S235 in 'quasi-thermal' lines of ammonia (NH$_3$), cyanoacetylene (HC$_3$N) and maser lines of methanol (CH$_3$OH) and water vapor (H$_2$O). S231-S235 regions is situated in the giant molecular cloud G174+2.5. We selected all massive molecular clumps in G174+2.5 using archive CO data. For the each clump we determined mass, size and CO column density. After that we performed observations of these clumps. We report about first detections of NH$_3$ and HC$_3$N lines toward the molecular clumps WB89 673 and WB89 668. This means that high-density gas is present there. Physical parameters of molecular gas in the clumps were estimated using the data on ammonia emission. We found that the gas temperature and the hydrogen number density are in the ranges 16-30 K and 2.8-7.2$\\times10^3$ cm$^{-3}$, respectively. The shock-tracing line of CH$_3$OH molecule at 36.2 GHz is newly detected toward WB89 673.

  10. Measuring the absorption mean cross section in 6Li relative to 235U fission

    Due to the fact that the neutron absorption cross section in 6Li is used as one of standards for determinaton of neutron-physical characteristics of fast reactors the ratio of mean cross sections for absorption by 6Li (A6) and 235U fission F25 are experimentalli investigated. The measurements have been performed in the KBR-8, KBR-10,BFS/39/1 bfs-44, BFS/45a-1 and BFS-46 critical assemblies which are characterized by various neutron spectra by means of a lithium counter with semiconductor detectors. Ratios A6/F25 for investigated assemblies constituted respectively 0.605+-0.009; 0.604+-0.004; 0.581+-0.009; 0.590+-0.574+-0.005. The values of 235U diffusion mean cross sections obtained on the base of these fata and calculated using the CRAB-1 program (given in brackets) are equal respectively 1.53+-0.005 (1.51) 2.38+-0.08 (2.42); 1.935+-0.060 (1.95); 1.89+-0.08 (1.95); 1.780+-0.11 (1.69); 1.90+-0.06 (1.89)

  11. 235 U consumption and 239 Pu formation on IPR-R1 reactor

    On the present world conjuncture it is necessary a rigorous storage and utilization control of nuclear materials under safeguard, specially those considered as strategic and those that could be used on the nuclear armaments fabrications as 235U and 239Pu. Brazil have signed and ratified many international pacts related to the peaceful utilization of the nuclear materials, making the compromise to attend nuclear safeguard procedures accorded with international regulatory organizations. The main goal of this work is the development of a simplified method for the estimation of the 239Pu productivity during the operation of the IPR-R1, TRIGA Mark-1 type, nuclear research reactor, that can achieve the maximum power of 100 KWt. A computational algorithm have been made to calculate the consumption of 235U on the fuel elements used on the reactor and the subsequent 239Pu formation (by the neutronic capture process), using the power generated by the reactor since the first criticality. The particular geometry of this kind of reactor allowed the calculation of the burn factors of the fuel elements discriminated by nuclear concentric rings, based on the thermal neutrons field distribution observed on experiments accomplished during a time period in similar reactors and on the IPR-R1. The simplified block diagram of the process, based on the calculation described above, is presented

  12. Studies of the Fission Integrals of U-235 and Pu-239 with Cadmium and Filters

    The resonance fissions in U235 and Pu239 have been studied using cadmium and boron filters. Fission chambers were used as detectors and the experiments were performed in beam geometry. The neutron energy distribution in the beams transmitted through the different filters was determined with a fast chopper. From the cadmium filter, measurements the fission resonance integrals were determined. The values obtained were 278±9 b for U235 and 301±10 b for Pu239; 0.5 eV 239 measurements were made in which the fission events were detected from the fission product activity in irradiated foils. Contrary to what has been reported elsewhere the value of the Pu239 resonance integral, found in this way, agreed well with that obtained from the fission chamber measurement. The experiments with the boron filters yielded results which, for the thin filter, agreed well with those calculated from the cross section data given in the Karlsruhe compilation. The discrepancy was larger for the thick filter but the values did not disagree outside the common limits of error

  13. Critical Experiments to Determine Amount of U-235 in Research Reactor Fuel Assemblies

    Seven different critical core configurations of the IRR1 have been used to determine experimentally the reactivity changes caused by interchanging different fuel assemblies in the same core position(1'2). The data obtained with the first four critical configurations, Cores 1, 2, 3, and 4, are analyzed in this report; the other three will be analyzed and reported in a later paper. The different fuel assemblies (highly enriched MTR type fuel assemblies) interchanged in these cores varied in their burnup or loss in U-235, thus changing the core keff w i t h each interchange. The k∞ of a fuel assembly is a function of its U-235 inventory. The fuel assemblies interchange forced the control blade to alter its height in order to compensate for the change in core reactivity. The control blade reactivity worth as a function of its height was measured by period measurements so the reactivity changes due to the fuel assemblies interchange could be determined. Several different fuel assemblies in each core were measured in this manner. This experimental data can be calculated using reactor physics codes

  14. R-matrix analysis of the 235U neutron cross sections

    The ENDFB-V representation of the 235U neutron cross sections in the resolved resonance region is unsatisfactory: below 1 eV the cross sections are given by ''smooth files'' (file 3) rather than by resonance parameters; above 1 eV the single-level formalism used by ENDFB-V necessitates a structured file 3 contribution consisting of more than 1300 energy points; furthermore, information on level-spins has not been included. Indeed the ENDFB-V 235U resonance region is based on an analysis done in 1970 for ENDFB-III and therefore does not include the results of high quality measurements done in the past 18 years. The present paper presents the result of an R-matrix multilevel analysis of recent measurements as well as older data. The analysis also extends the resolved resonance region from its ENDFB-V upper limit of 81 eV to 110 eV. 13 refs., 2 figs., 1 tab

  15. Calculation of 235U(n,n') cross sections for ENDF/B-VI

    Cross sections for neutron-induced reactions on 235U between 0.01 and 20 MeV have been calculated in a preliminary analysis for the ENDF/B-VI evaluation with particular emphasis on neutron inelastic scattering. A deformed optical model potential that fits total, elastic, inelastic, and low-energy average resonance data is used to calculate direct (n,n') cross sections and transmission coefficients for a Hauser-Feshbach statistical theory analysis using a multiple fission barrier representation. Direct cross sections for higher-lying vibrational states are provided from DWBA calculations, normalized using B(E/ital l/) values determined from (d,d') and Coulomb excitation data. Initial fission barrier parameters and transition state density enhancements appropriate to the compound systems involved were obtained from previous analyses, especially fits to charged-particle fission probability data. Further modifications to fit 235U(n,f) data were small, and the final fission parameters are generally consistent with published values. The results from this preliminary analysis are compared with the ENDF/B-V evaluation as well as with experimental data. 26 refs., 5 figs., 3 tabs

  16. Total kinetic energy release in the fast neutron-induced fission of $^{235}$U

    Yanez, R; King, J; Barrett, J S; Fotiades, N; Lee, H Y

    2015-01-01

    We have measured the total kinetic energy (TKE) release for the $^{235}$U(n,f) reaction for $E_{n}$=2-100 MeV using the 2E method with an array of Si PIN diode detectors. The neutron energies were determined by time of flight measurements using the white spectrum neutron beam at the LANSCE facility. (To calibrate the apparatus, the TKE release for $^{235}$U(n$_{th}$,f) was also measured using a thermal neutron beam from the OSU TRIGA reactor). The TKE decreases non-linearly from 169.0 MeV to 161.4 MeV for $E_{n}$=2-90 MeV. The standard deviation of the TKE distribution is constant from $E_{n}$=20-90 MeV. Comparison of the data with the multi-modal fission model of Brosa indicates the TKE decrease is a consequence of the growth of symmetric fission and the corresponding decrease of asymmetric fission with increasing neutron energy. The average TKE associated with the Brosa superlong, standard I and standard II modes for a given mass is independent of neutron energy.

  17. Prompt Gamma Radiation from Fragments in the Thermal Fission of 235U

    Measurements were made on the gamma radiation emitted from fission fragments in slow neutron induced fission of 235U. The fragments were detected with solid state detectors of the surface barrier type and the gamma radiation with a Nal(Tl) scintillator. Mass selection was used so that the gamma radiation could be measured as a function of fragment mass. Time discrimination between the fission gammas and the prompt neutrons released in the fission process was employed to reduce the background. The gamma radiation emitted during different time intervals after the fission event was studied with the help of a collimator, the position of which was changed along the path of the fission fragments. In this way a decay curve was obtained from which the life-time of one of the gamma-emitting states could be estimated. The relative yield of the gamma-rays was determined as a function of mass for different gamma-ray energy portions and two specific time intervals after the fission events. Comparisons were made with data obtained from 252 Cf-fission. Attention is drawn to some features which seem to be the same in 235U and 252 Cf-fission

  18. 238U/235U variations in meteorites: extant 247Cm and implications for Pb-Pb dating.

    Brennecka, G A; Weyer, S; Wadhwa, M; Janney, P E; Zipfel, J; Anbar, A D

    2010-01-22

    The 238U/235U isotope ratio has long been considered invariant in meteoritic materials (equal to 137.88). This assumption is a cornerstone of the high-precision lead-lead dates that define the absolute age of the solar system. Calcium-aluminum-rich inclusions (CAIs) of the Allende meteorite display variable 238U/235U ratios, ranging between 137.409 +/- 0.039 and 137.885 +/- 0.009. This range implies substantial uncertainties in the ages that were previously determined by lead-lead dating of CAIs, which may be overestimated by several million years. The correlation of uranium isotope ratios with proxies for curium/uranium (that is, thorium/uranium and neodymium/uranium) provides strong evidence that the observed variations of 238U/235U in CAIs were produced by the decay of extant curium-247 to uranium-235 in the early solar system, with an initial 247Cm/235U ratio of approximately 1.1 x 10(-4) to 2.4 x 10(-4). PMID:20044543

  19. High accuracy/high precision determination of 235U in nondestructive assay standards by gamma-ray spectroscopy

    High precision gamma spectrometry measurements have been made on five sets of five uranium isotope abundance reference materials for nondestructive assay (NDA). These sets are intended for international safeguards use as primary reference materials for the determination of the 235U abundance in homogeneous uranium bulk material by gamma spectrometry. The measurements are to determine the counting rate uniformity of the 235U 185.7 keV gamma as well as the 235U isotope abundance for each sample. Since the samples are packaged such that the U3O8 is infinitely thick for the 185.7 keV gamma, the measured counting rate is not dependent on the material density. In addition, the activity observed by the detector is colimated to simulate calibration conditions used to measure bulk material in the field. The results of this study indicate that accuracy of 235U determination via gamma spectrometry, in the range of few hundredths of a percent (2sigma), is achievable. The main requirement for achieving this level of accuracy is a set of standards whose 235U isotope abundance are known to within 0.01% (2sigma)

  20. Distribution of nanomole quantities of 235U in young and adult Japanese quail and in the F1 generation. Comparison with 153Gd

    Enriched uranium, 93.16% for 235U, served as a tracer of uranium deposition in an avian species, the Japanese quail. A second label, 153Gd, provided for monitoring of procedures and for estimation of the 235U content of live eggs. Depositions of 235U were greater than for 153Gd in all tissues except the yolk sac and the liver. Skeletal levels for 235U were age- and sex-dependent. Feathers contained only 0.11% of the 235U tracer in contrast to 50% of the endogenous uranium. The results show that 235U provides for tracing uranium metabolism in small animals, since in quail the tracer increased the uranium burden of the body by only 1-8%. (author)

  1. Comparison of {sup 235}U fission cross sections in JENDL-3.3 and ENDF/B-VI

    Kawano, Toshihiko [Kyushu Univ., Fukuoka (Japan); Carlson, Allan D. [National Institute of Standards and Technology (United States); Matsunobu, Hiroyuki [Data Engineering, Inc., Fujisawa, Kanagawa (Japan); Nakagawa, Tsuneo; Shibata, Keiichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Talou, Patrick; Young, Philip G.; Chadwick, Mark B. [Los Alamos National Laboratory, Los Alamos, NM (United States)

    2002-01-01

    Comparisons of evaluated fission cross sections for {sup 235}U in JENDL-3.3 and ENDF/B-VI are carried out. The comparisons are made for both the differential and integral data. The fission cross sections as well as the fission ratios are compared with the experimental data in detail. Spectrum averaged cross sections are calculated and compared with the measurements. The employed spectra are the {sup 235}U prompt fission neutron spectrum, the {sup 252}Cf spontaneous fission neutron spectrum, and the neutron spectrum produced by a {sup 9}Be(d, xn) reaction. For {sup 235}U prompt fission neutron spectrum, the ENDF/B-VI evaluation reproduces experimental averaged cross sections. For {sup 252}Cf and {sup 9}Be(d, xn) neutron spectra, the JENDL-3.3 evaluation gives better results than ENDF/B-VI. (author)

  2. Analysis of 235U enrichment by chemical exchange in U(IV) - U(VI) system on anionite

    Full text: A theoretical study about the 235U enrichment by chemical exchange method in U(IV)-U(VI) system on anion-exchange resins is presented. The 235U isotope concentration profiles along the band were numerically calculated using an accurate mathematical model and simulations were carried out for the situation of product and waste withdrawal and feed supply. By means of numerical simulation, an estimation of the migration time, necessary for a desired enrichment degree, was obtained. The required migration distance, the production of uranium 3 at.% 235U per year and the plant configuration are calculated for different operating conditions. An analysis of the process scale for various experimental conditions is also presented. (authors)

  3. Performance evaluation of indigenous thermal ionization mass spectrometer for determination of 235U/238U atom ratios

    A magnetic sector based Thermal Ionization Mass Spectrometer (TIMS) designed and developed at Technical Physics Division, B.A.R.C., was evaluated for its performance for the determination of 235U/238U atom ratios in uranium samples. This consisted of evaluating the precision and accuracy on the 235U/238U atom ratios in various isotopic reference materials as well as indigenously generated uranium samples. The results obtained by the indigenous TIMS were also compared with those obtained using a commercially available TIMS system. The internal and external precision were found to be around 0.1% for determining 235U/238U atom ratios close to those of natural uranium ( i.e. 0.00730). (author)

  4. EVALUATION OF BORATED ALUMINUM PRODUCTS FOR CRITICALITY CONTROL IN 235-F

    Duncan, A.; Sindelar, R.

    2003-05-06

    Plutonium-containing materials are destined for storage in the 235-F vault. The projected amount of stored materials will require the presence of neutron absorber materials. The leading design concept is for the neutron absorber materials to be in non-load-bearing borated aluminum plates lining the walls of the vault. A comprehensive evaluation of the borated aluminum plate materials was performed to identify a suitable material, and verify that these materials would remain effective as neutron absorbers under normal service conditions and for design-basis events, including the fire accident scenario, throughout a 20-year service life. Aluminum 1100 with boron additions is the recommended neutron absorber material for plutonium material storage in the 235-F vault based on boron loading capacity and durability in the storage environment. Borated aluminum 1100 is commercially available up to 4.5 wt. % boron. A detailed comparison was made of the physical, mechanical, and corrosion properties of borated aluminum alloy 1100 to standard alloy 1100-O (-O designating the fully annealed condition) to demonstrate near-equivalency in properties and to justify application of alloy 1100-O properties to the borated product as needed for the degradation analysis. The expected degradation of the borated aluminum is extremely low for storage conditions, including the bounding scenario of an aggressive atmospheric condition. A maximum loss of 0.00029 inches/year would be expected under potentially aggressive atmospheric conditions and would result in a fractional loss of only 0.42 wt. % of the boron present in a 7mm plate for a 20-year storage period. The fraction of Boron-10 consumption by spontaneous neutrons is expected to be less than 10{sup -8} for the 20-year storage in 235-F fully loaded with Pu materials. The borated aluminum alloy 1100 will be thermally stable and unaltered up to near-melt temperature (643°C). Mechanical testing data at elevated temperatures show that the

  5. 238U/235U determinations of some commonly used reference materials and U-bearing accessory minerals (Invited)

    Condon, D.; Noble, S.; McLean, N.; Bowring, S. A.

    2009-12-01

    We have determined 238U/235U ratios for a suite of commonly used natural (CRM 112a, SRM 950a, HU-1) and synthetic (IRMM 184 and CRM U500) uranium reference materials in addition to several U-bearing accessory phases (zircon and monazite) by thermal ionisation mass-spectrometry (TIMS) using the IRMM 3636 233U-236U double spike to accurately correct for mass fractionation. The 238U/235U values for the natural uranium reference materials differ, by up to 0.1%, from the widely used ‘consensus’ value (137.88) with all having 238U/235U values less than 137.88. Similarly, initial 238U/235U data from zircon and monazite yield 238U/235U values that are lower than the ‘consensus’ value. The data obtained from U-bearing minerals is used to assess how the uncertainty in the 238U/235U ratio contributes to the systematic discordance observed in 238U/206Pb and 235U/207Pb dates (Mattinson, 2000; Schoene et al., 2006) which has traditionally been wholly attributed to error in the U decay constants. The 238U/235U determinations made on the synthetic reference materials yield results that are considerably more precise and accurate than the certified values (0.02% vs. 0.1% for CRM U500). The calibration of isotopic tracers used for U-daughter geochronology that are partially based upon these reference materials, and the resultant age determinations, will benefit from increased accuracy and precision. Mattinson, J.M., 2000. Revising the “gold standard”—the uranium decay constants of Jaffey et al., 1971. Eos Trans. AGU, Spring Meet. Suppl., Abstract V61A-02. Schoene B., Crowley J.L., Condon D.C., Schmitz M.D., Bowring S.A., 2006, Reassessing the uranium decay constants for geochronology using ID-TIMS U-Pb data. Geochimica et Cosmochimica Acta 70: 426-445

  6. Study of Relationship Between Neutron Energy and Fission Yields of 95Zr, 140Ba and 147Nd From 235U

    2001-01-01

    This work measures fission yields of 235U induced by neutrons with energy of thermal, 3.0, 5.0, 5.5, 8.0 and 14.8 MeV. The main purpose is to study the relationship between neutron energy and fission fields of 95Zr,140Ba and 147Nd from 235U by measuring the radioactivity of foil with direct gamma spectrometry. The fission yields induced by fast neutrons are get by fast-thermal-ratio method which based on yields from thermal neutrons, yields by thermal neutron are come from absolute measurement. Since fast-thermal-ratio method eliminates uncertainties of gamma intensity, gamma

  7. Prompt γ-rays from the Fast Neutron Induced Fission on 235,238U and 232Th

    Lebois, M.; Wilson, J. N.; Halipré, P.; Leniau, B.; Matea, I.; Oberstedt, A.; Oberstedt, S.; Verney, D.

    Preliminary results from the first experiment using the LICORNE neutron source at the IPN Orsay are presented. Prompt fission gamma rays from fast-neutron induced fission of 238U, 232Th and 235U were detected. Thick samples of around 50 g of 238U and 232Th are used for the first part of the experiment. An ionisation chamber containing ∼ 10 mg samples of 238U and 235U to provide a fission trigger is used for the second part of the experiment. Gamma rays have been detected using 17 high efficiency BaF2 detectors and 6 LaBr3 scintillator detectors.

  8. Investigation of forming mechanism of instantaneous neutron spectrum of 235U, 239Pu, 252Cf nuclei fission

    Formation mechanism of prompt neutrons spectrum during the fission of the 235U, 239Pu nuclei by thermal and fast neutrons and spontaneous fission of 252Cf is investigated. The formation procedure for prompt neutrons spectrum during the fission of nuclei as superposition of three partial evaporation Weisskopf spectra with the mean energy of neutrons 0.4, 2.06 and 2.8 MeV is proposed. Formation mechanism of the spectrum just as during the fission of the 235U, 239Pu nuclei by thermal and fast neutrons, so spontaneous fission of the 252Cf nuclei is identical

  9. Quantitative determination of 235U and 238U by measuring the gamma radiation from short-lived fission products

    On the basis of two successive activations of the sample by neutrons of different energy distribution and of measuring the gamma radiation from the resulting short-lived fission products the masses of uranium 235 and 238, the enrichment and the uranium concentration have been determined. The procedure can only be used for unirradiated uranium. The analysis takes 50 min. The method has been tested with samples of 10 g and up to 90% enrichment. The minimum detectable amounts were 1 mg 235U and 1 g 238U, respectively, with the random error of measurement being 4%. (author)

  10. Reich-Moore and Adler-Adler representations of the 235U cross sections in the resolved resonance region

    In the first part of this paper, a reevaluation of the low-energy neutron cross sections of 235U is described. This reevaluation was motivated by the discrepancy between the measured and computed temperature coefficients of reactivity and is based on recent measurements of the fission cross section and of η in the thermal and subthermal neutron energy regions. In the second part of the paper, we discuss the conversion of the Reich-Moore resonance parameters, describing the neutron cross sections of 235U in the resolved resonance region, into equivalent Adler-Adler resonance parameters and into equivalent momentum space multipole resonance parameters

  11. Reich-Moore and Adler-Adler representations of the 235U cross sections in the resolved resonance region

    In the first part of this paper, a reevaluation of the low-energy neutron cross sections of 235U is described. This reevaluation was motivated by the discrepancy between the measured and computed temperature coefficients of reactivity and is based on recent measurements of the fission cross section and of η in the thermal and subthermal neutron energy regions. In the second part of the paper, we discuss the conversion of the Reich-Moore resonance parameters, describing the neutron cross sections of 235U in the resolved resonance region, into equivalent Adler-Adler resonance parameters and into equivalent momentum space multipole resonance parameters. 25 refs., 4 figs., 5 tabs

  12. Searching for U-235m produced by Nuclear Excitation by Electronic Transition

    Chodash, Perry; Norman, Eric; Burke, Jason; Wilks, Scott; Casperson, Robert

    2014-09-01

    Nuclear excitation by electronic transition (NEET) is a rare nuclear excitation that is predicted to occur in numerous isotopes, including U-235. When a nuclear transition matches the energy and the multipolarity of an electronic transition, there is a possibility that NEET will occur. If NEET were to occur in U-235, the nucleus would be excited to its 1/2 + isomeric state that subsequently decays by internal conversion with a decay energy of 77 eV and a half-life of 26 minutes. Theory predicts that NEET can occur in partially ionized uranium plasma with a charge state of 23 +. A pulsed Nd:YAG laser operating at 1064 nm with a pulse energy of 780 mJ and a pulse width of 9 ns was used to generate the uranium plasma. The laser was focused on small samples of both depleted uranium and highly enriched uranium. The plasma conditions created by the intense laser pulse were varied by changing the spot size of the laser on the target. The resulting plasma was collected on a plate and the internal conversion electrons were focused onto a microchannel plate detector by a series of electrostatic lenses. First results will be presented. Nuclear excitation by electronic transition (NEET) is a rare nuclear excitation that is predicted to occur in numerous isotopes, including U-235. When a nuclear transition matches the energy and the multipolarity of an electronic transition, there is a possibility that NEET will occur. If NEET were to occur in U-235, the nucleus would be excited to its 1/2 + isomeric state that subsequently decays by internal conversion with a decay energy of 77 eV and a half-life of 26 minutes. Theory predicts that NEET can occur in partially ionized uranium plasma with a charge state of 23 +. A pulsed Nd:YAG laser operating at 1064 nm with a pulse energy of 780 mJ and a pulse width of 9 ns was used to generate the uranium plasma. The laser was focused on small samples of both depleted uranium and highly enriched uranium. The plasma conditions created by the

  13. Standard specification for uranium metal enriched to more than 15 % and less Than 20 % 235U

    American Society for Testing and Materials. Philadelphia

    2000-01-01

    1.1 This specification covers nuclear grade uranium metal that has either been processed through an enrichment plant, or has been produced by the blending of highly enriched uranium with other uranium, to obtain uranium of any 235U concentration below 20 % (and greater than 15 %) and that is intended for research reactor fuel fabrication. The scope of this specification includes specifications for enriched uranium metal derived from commercial natural uranium, recovered uranium, or highly enriched uranium. Commercial natural uranium, recovered uranium and highly enriched uranium are defined in Section 3. The objectives of this specification are to define the impurity and uranium isotope limits for commercial grade enriched uranium metal. 1.2 This specification is intended to provide the nuclear industry with a standard for enriched uranium metal which is to be used in the production of research reactor fuel. In addition to this specification, the parties concerned may agree to other appropriate conditions. ...

  14. Investigating Prompt Fission Neutron Emission from 235U(n,f) in the Resolved Resonance Region

    Göök, Alf; Hambsch, Franz-Josef; Oberstedt, Stephan

    2016-03-01

    Investigations of prompt emission in fission is of importance in understanding the fission process in general and the sharing of excitation energy among the fission fragments in particular. Experimental activities at IRMM on prompt neutron emission from fission in response to OECD/NEA nuclear data requests is presented in this contribution. Main focus lies on currently on-going investigations of prompt neutron emission from the reaction 235U(n,f) in the region of the resolved resonances. For this reaction strong fluctuations of fission fragment mass distributions and mean total kinetic energy have been observed [Nucl. Phys. A 491, 56 (1989)] as a function of incident neutron energy in the resonance region. In addition fluctuations of prompt neutron multiplicities were also observed [Phys. Rev. C 13, 195 (1976)]. The goal of the present study is to verify the current knowledge of prompt neutron multiplicity fluctuations and to study correlations with fission fragment properties.

  15. Investigating Prompt Fission Neutron Emission from 235U(n,f in the Resolved Resonance Region

    Göök Alf

    2016-01-01

    Full Text Available Investigations of prompt emission in fission is of importance in understanding the fission process in general and the sharing of excitation energy among the fission fragments in particular. Experimental activities at IRMM on prompt neutron emission from fission in response to OECD/NEA nuclear data requests is presented in this contribution. Main focus lies on currently on-going investigations of prompt neutron emission from the reaction 235U(n,f in the region of the resolved resonances. For this reaction strong fluctuations of fission fragment mass distributions and mean total kinetic energy have been observed [Nucl. Phys. A 491, 56 (1989] as a function of incident neutron energy in the resonance region. In addition fluctuations of prompt neutron multiplicities were also observed [Phys. Rev. C 13, 195 (1976]. The goal of the present study is to verify the current knowledge of prompt neutron multiplicity fluctuations and to study correlations with fission fragment properties.

  16. Measurements of γ-ray Energy and Multiplicity from 235U(nthermal using STEFF

    Pollitt A.J.

    2015-01-01

    Full Text Available The amount of energy carried by γ-rays during the fission process is an important consideration when developing new reactor designs. Many studies of γ-ray energy and multiplicity, from a multitude of fissioning systems, were measured during the 1970s. However the data from such experiments largely underestimates the heating effect caused by γ-rays in the structure of a reactor. It is therefore essential to obtain more accurate measurements of the energy carried during γ-ray emission. As such, the OECD Nuclear Energy Agency has put out a high priority request [1] for measurements of the mean γ-ray energy and multiplicity to an accuracy better than 7.5 percent from several fissioning systems; including 235U(nthermal. Measurements of the rays from these fissioning nuclei were performed with the SpecTrometer for Exotic Fission Fagments (STEFF.

  17. The effect of temperature on the average volume of Barkhausen jump on Q235 carbon steel

    Guo, Lei; Shu, Di; Yin, Liang; Chen, Juan; Qi, Xin

    2016-06-01

    On the basis of the average volume of Barkhausen jump (AVBJ) vbar generated by irreversible displacement of magnetic domain wall under the effect of the incentive magnetic field on ferromagnetic materials, the functional relationship between saturation magnetization Ms and temperature T is employed in this paper to deduce the explicit mathematical expression among AVBJ vbar, stress σ, incentive magnetic field H and temperature T. Then the change law between AVBJ vbar and temperature T is researched according to the mathematical expression. Moreover, the tensile and compressive stress experiments are carried out on Q235 carbon steel specimens at different temperature to verify our theories. This paper offers a series of theoretical bases to solve the temperature compensation problem of Barkhausen testing method.

  18. A report on stress analysis of seal disc of 235 MWe PHWR

    The seal disc is an important component of pressurized heavy water reactor. When mounted, this becomes a part of the coolant channel and hence is a pressure boundary for the heavy water coolant inside the channel. Detailed stress analysis of seal disc of 235 MWe PHWR (MAPP) is done. Linear elastic analysis showed that stresses are more than the allowable values as per ASME code Section III, Division 1. This makes it necessary to invoke the special provision of MB-3228.1 (1986). An elasto-plastic analysis was done to find out the collapse load which showed that the seal disc is safe for all stages of loadings. (author). 2 tabs., 7 figs

  19. An indigenous system for in-service inspection of coolant channels of 235 MWe PHWRs

    In-service inspection of coolant channels of nuclear power plants is essential to provide information on ageing effects. A channel inspection system (BARCIS- BARC Channel Inspection System) for in-service inspection of coolant channels of 235 MWe PHWRs has been recently developed at BARC. The need for such a system was being felt for quite sometime. The system is designed with the aim to minimise radiation exposure to inspection personnel and to perform the inspection so as to minimise reactor downtime. Sixteen coolant channels of RAPS-2 and fourteen coolant channels of MAPS-2 have been inspected using BARCIS MARK-1 system. Details of the system developed and the results of inspection are presented. (author). 3 refs., 3 tabs., 5 figs

  20. High accuracy 235U(n,f data in the resonance energy region

    Paradela C.

    2016-01-01

    Full Text Available The 235U neutron-induced cross section is widely used as reference cross section for measuring other fission cross sections, but in the resonance region it is not considered as an IAEA standard because of the scarce experimental data covering the full region. In this work, we deal with a new analysis of the experimental data obtained with a detection setup based on parallel plate ionization chambers (PPACs at the CERN n_TOF facility in the range from 1 eV to 10 keV. The relative cross section has been normalised to the IAEA value in the region between 7.8 and 11 eV, which is claimed as well-known. Comparison with the ENDF/B-VII evaluation and the IAEA reference file from 100 eV to 10 keV are provided.

  1. The simultaneous determination of 235U and 239Pu using delayed neutron activation analysis

    Delayed neutron activation analysis (DNAA) remains one of the most sensitive methods of nondestructively determining fissile materials in a variety of sample matrices, provided that the samples contain only a single fissile component. This has historically been the limiting factor in many applications of DNAA, and often chemically destructive methods of analysis have needed to be utilized for many real-world samples. This work seeks to develop a method that will allow for DNAA to be utilized on samples containing multiple fissile components. Initial efforts, presented here, show that using a multivariate linear regression model to describe the delayed neutron emission profile of an irradiated sample allows for the concurrent determination of fissile nuclides in samples containing both 235U and 239Pu, without chemical separations and using only a single counting step. (author)

  2. Fission time for the {sup 235}U + {alpha} reaction measured by the crystal blocking technique

    Yuminov, O.A. [D.V. Skobeltsyn Institute of Nuclear Physics, M.V. Lomonosov Moscow State University, Vorobyevy Gory, Moscow 119991 (Russian Federation)], E-mail: yuminov@p5-lnr.sinp.msu.ru; Borisov, A.M.; Drozdov, V.A.; Eremenko, D.O.; Fotina, O.V. [D.V. Skobeltsyn Institute of Nuclear Physics, M.V. Lomonosov Moscow State University, Vorobyevy Gory, Moscow 119991 (Russian Federation); Malaguti, F. [Istituto Nazionale di Fisica Nucleare - Sezione di Bologna, Dipartimento di Fisica dell' Universita, Via Irnerio 46, Bologna (Italy); Olivo, P. [Dipartimento Matemates, Universita' di Bologna, Via Irnerio 46, Bologna (Italy); Platonov, S.Yu. [D.V. Skobeltsyn Institute of Nuclear Physics, M.V. Lomonosov Moscow State University, Vorobyevy Gory, Moscow 119991 (Russian Federation); Togo, V. [Istituto Nazionale di Fisica Nucleare - Sezione di Bologna, Dipartimento di Fisica dell' Universita, Via Irnerio 46, Bologna (Italy); Tulinov, A.F. [D.V. Skobeltsyn Institute of Nuclear Physics, M.V. Lomonosov Moscow State University, Vorobyevy Gory, Moscow 119991 (Russian Federation)

    2009-08-15

    The crystal blocking technique has been used to measure the total time of the induced fission process for the {sup 235}U + {alpha} reaction in the energy range of bombarding {alpha}-particles from 25.9 to 31.2 MeV. Experimental fission times observed in this reaction vary from 10{sup -17} to 10{sup -16} s, depending on the projectile energy. Together with the corresponding experimental data on angular anisotropy in the same reaction they were analyzed within the dynamic-statistical approach with allowance for the nuclear dissipation phenomenon and the double-humped fission barrier model. It was demonstrated that the time of induced fission at low excitation energies is sensitive to the nuclear dissipation magnitude.

  3. Fission time for the 235U + α reaction measured by the crystal blocking technique

    The crystal blocking technique has been used to measure the total time of the induced fission process for the 235U + α reaction in the energy range of bombarding α-particles from 25.9 to 31.2 MeV. Experimental fission times observed in this reaction vary from 10-17 to 10-16 s, depending on the projectile energy. Together with the corresponding experimental data on angular anisotropy in the same reaction they were analyzed within the dynamic-statistical approach with allowance for the nuclear dissipation phenomenon and the double-humped fission barrier model. It was demonstrated that the time of induced fission at low excitation energies is sensitive to the nuclear dissipation magnitude.

  4. Contribution to the study of the thermal fission process for uranium 235 (1964)

    This report deals with the study of the distribution of the masses of the fragments produced by the disintegration of the U-236 nucleus, formed when a U-235 nucleus captures a thermal neutron. The experimental method chosen consists in the simultaneous measurement using p-n silicon junction detectors of the energies of the two fragments emitted in coincidence. This measurement is first made by a conditioned analysis of the energy of one of the fragments and then by a two dimensional analysis of the energies of the two fragments. Systematic results, are obtained concerning the distribution of the masses for different values of the total kinetic energy. The five structures appearing both for the mass distributions and for the energies of the fragments are studied and discussed. Generally speaking, our results are in agreement with those obtained by the time-of-flight method. (author)

  5. Systematics study of the ZP model for the 235U + n fission

    The ZP model was studied to evaluate the independent fission yields for 235U induced by thermal, fission, and about 14 MeV energy neutrons. The parameters of ZP model were deduced based upon measured data, and were used to calculate the yields and their errors. The yields were compared with those from TALYS calculations, ENDF/B7-FPY, JEFF-3.0/FPY and JENDL-3.3/FPY, the result showed that the present yields as well as their errors were improved. Due to the lack of measured data, the results for fission neutrons and 14 MeV energy neutrons have larger uncertainties and discrepancies than those for thermal fission. So more measurements and advanced theories are needed

  6. Systematics study of the Z{sub P} model for the {sup 235}U + n fission

    Shu, N.C.; Liu, T.J.; Yua, H.W.; Chen, Y.J. [China Institute of Atomic Energy, Beijing, P.R. (China)

    2008-07-01

    The Z{sub P} model was studied to evaluate the independent fission yields for {sup 235}U induced by thermal, fission, and about 14 MeV energy neutrons. The parameters of Z{sub P} model were deduced based upon measured data, and were used to calculate the yields and their errors. The yields were compared with those from TALYS calculations, ENDF/B7-FPY, JEFF-3.0/FPY and JENDL-3.3/FPY, the result showed that the present yields as well as their errors were improved. Due to the lack of measured data, the results for fission neutrons and 14 MeV energy neutrons have larger uncertainties and discrepancies than those for thermal fission. So more measurements and advanced theories are needed.

  7. A new resonance-region evaluation of neutron cross sections for 235U

    This paper describes a new evaluation of the resolved resonance range for the neutron cross sections of 235U. Up to 110 eV the evaluation is based on an R-matrix analysis of several fission, capture and transmission measurements. Above 110 eV levels are not resolved anymore so that many resonances are missed; from 110 to 500 eV most of the important resonances can be identified and analyzed so that the cross section and transmission data are well represented by the proposed parameters. From 500 to 2,250 eV fictitious parameters are provided which describe fairly well the results of thick sample transmission measurements and recent fission cross-section data. We believe that such a parameterization is likely to yield a better approximation of resonance self-shielding than the current ENDF/B-V unresolved resonance treatment

  8. Bulgarian experience with the implementation of {sup 235}U enriched fuel in WWER-1000 units

    Dobrevski, Ivan; Zaharieva, Neili [Bulgarian Academy of Sciences, Sofia (Bulgaria). Inst. for Nuclear Research and Nuclear Energy

    2009-12-15

    This paper reports on the results of the implementation of TVSA fuel assemblies with up to 4.3 % {sup 235}U enrichment and an integrated burnable absorber (Gd) (U-Gd{sub 2}O{sub 3} fuel with 5 % Gd{sub 2}O{sub 3}) in WWER-1000 reactors at Kozloduy Nuclear Power Plant in Bulgaria. Data from the first cycle with 100 % TVSA assemblies show that plant staff was able to maintain the coolant water chemistry within the range demanded by the plant's primary circuit water chemistry requirements. Data indicate that the corrosion processes in the primary circuit remained on the same low level as during previous cycles. (orig.)

  9. Development and technical implementation of the separation nozzle process for enrichment of uranium 235

    The separation nozzle process for the enrichment of uranium-235 has been developed at the Karlsruhe Nuclear Research Center as an alternative to the gaseous diffusion and centrifuge process. The separation of uranium isotopes is achieved by the deflection of a jet of uranium hexafluoride mixed with hydrogen. Since 1970, the German company of STEAG, has been involved in the technological development and commercial implementation of the nozzle process. In 1975, the Brazilian company of NUCLEBRAS, and the German company of Interatom, joined the effort. The primary objective of the common activity is the construction of a separation nozzle demonstration plant with an annual capacity of about 200 000 SWU and the development of components of a commercial plant. The paper covers the most important steps in the development and the technical implementation of the process. (orig.)

  10. Thermal-Neutron-Induced Fission of U235, U233 and Pu239

    We have used solid-state detectors to measure the kinetic energies of the coincident fission fragments in the thermal-neutron-induced fission of U235, U233 and Pu239. Special care has been taken to eliminate spurious-events near symmetry to give an accurate measure of such quantities as the average total kinetic energy at symmetry. For each fissioning system over 106 events were recorded. As a result the statistics are good enough to see definite evidence for fine structure over a wide range of masses and energies. The data have been analysed to give mass yield curves, average kinetic energies as a function of mass, and other quantities of interest. For each fissioning system the average total kinetic energy goes through a maximum for a heavy fragment mass of about 132 and for the corresponding light fragment mass. There is a pronounced minimum at symmetry, although not as deep as that found in time-of-flight experiments. The difference between the maximum average kinetic energy and that at symmetry is about 32 MeV for U235, 18 MeV for U233 and 20 MeV for Pu239. The dispersion of kinetic energies at symmetry is also smaller than that found in time-of-flight experiments. Fine structure is apparent in two different representations of the data. The energy spectrum of heavy fragments in coincidence with light fragment energies is greater than the most probable value. This structure becomes more pronounced as the light fragment energy increases. The mass yield curves for a given total kinetic energy show a structure suggesting a preference for fission fragments with masses ∼134, ∼140 and ∼145 (and their light fragment partners). Much of the structure observed can be understood by considering a semi-empirical mass surface and a simple model for the nuclear configuration at the saddle point. (author)

  11. Our strategy in complication management of augmentation mammaplasty with polyacrylamide hydrogel injection in 235 patients.

    Luo, Sheng-Kang; Chen, Gunang-Ping; Sun, Zhong-Shen; Cheng, Ning-Xin

    2011-06-01

    Polyacrylamide hydrogel (PAAG) was once widely used in breast augmentation in China. Although it had been banned for augmentation mammaplasty in 2006, a large number of patients whose breasts were augmented with the gel injection have continued to seek medical advice because of its complications. The clinical management of these complications has never been standardised. The data of a total of 235 patients with complications following PAAG-injected breast augmentation have been summarised and the types and causations analysed. Magnetic resonance imaging (MRI) was undertaken in 228 patients with palpable masses, breast pain or tenderness, asymmetry or deformity and functional or psychological problems to eliminate neoplasm, infection and to delineate the diseases. The surgical gel evacuation via periareolar incisions was performed for all patients and immediate silicone breast prostheses were implanted in 108 patients and were delayed in 28 cases by 6 months. Most patients (214/235) of the group were satisfied with the treatment, and symptoms disappeared after removal of the gel. The gel distribution and involved tissue were well defined and neoplasm was ruled out by MRI. Postoperative MRI in 68 patients revealed that no obvious PAAG remaining. In either immediate or delayed reconstructive patients with silicone breast implants, good breast contour presented. A diagnosis and management strategy for these complications is proposed. In conclusion, the breast masses, pain and deformity are major complications after PAAG-injected breast augmentation. Psychological problems should be paid attention to. MRI is a sensitive and accurate method for diagnosis and treatment evaluation. Surgical removal of injected gel is the preferred method for complication management. The implantation of silicone prostheses for breast contour restoration after PAAG evacuation is effective for patients under strict selection. Our strategy for treating PAAG-related complications proved useful

  12. Measurement of U-235 Fission Neutron Spectra Using a Multiple Gamma Coincidence Technique

    Ji, Chuncheng; Kegel, G. H. R.; Egan, J. J.; DeSimone, D. J.; Alimeti, A.; Roldan, C. F.; McKittrick, T. M.; Kim, D.-S.; Chen, X.; Tremblay, S. E.

    2005-05-01

    The Los Alamos Model of Madland and Nix predicts the shape of the fission neutron energy spectrum for incident primary neutrons of different energies. Verifications of the model normally are limited to measurements of the fission neutron spectra for energies higher than that of the primary neutrons because the low-energy spectrum is distorted by the admixture of elastically and inelastically scattered neutrons. This situation can be remedied by using a measuring technique that separates fission from scattering events. One solution consists of using a fissile sample so thin that fission fragments can be observed indicating the occurrence of a fission event. A different approach is considered in this paper. It has been established that a fission event is accompanied by the emission of between seven and eight gamma rays, while in a scattering interaction, between zero and two gammas are emitted, so that a gamma multiplicity detector should supply a datum to distinguish a fission event from a scattering event. We proceed as follows: A subnanosecond pulsed and bunched proton beam from the UML Van de Graaff generates nearly mono-energetic neutrons by irradiating a thin metallic lithium target. The neutrons irradiate a 235U sample. Emerging neutron energies are measured with a time-of-flight spectrometer. A set of four BaF2 detectors is located close to the 235U sample. These detectors together with their electronic components identify five different events for each neutron detected, i.e., whether four, three, two, one, or none of the BaF2 detectors received one (or more) gamma rays. We present work, preliminary to the final measurements, involving feasibility considerations based on gamma-ray coincidence measurements with four BaF2 detectors, and the design of a Fission-Scattering Discriminator under construction.

  13. Nosocomial dissemination of VIM-2-producing ST235 Pseudomonas aeruginosa in Lithuania.

    Mikucionyte, G; Zamorano, L; Vitkauskiene, A; López-Causapé, C; Juan, C; Mulet, X; Oliver, A

    2016-02-01

    Pseudomonas aeruginosa multidrug resistance, and particularly the production of carbapenemases linked to international high-risk clones, is of growing concern. While high levels of carbapenem resistance (>60 %) have been reported in Lithuania, so far, there is no information on the underlying mechanisms. Thus, the aim of this work was to determine the molecular epidemiology and prevalence of acquired carbapenemases among 73 carbapenem-resistant P. aeruginosa isolates recovered in a hospital from Kaunas, Lithuania in 2011-2012. The presence of acquired carbapenemases was evaluated through phenotypic (modified Hodge test, cloxacillin inhibition test, double-disc synergy test) and genetic methods [polymerase chain reaction (PCR) and sequencing]. Clonal relatedness was assessed by pulsed-field gel electrophoresis (PFGE) and multilocus sequence typing (MLST). Acquired β-lactamases were detected in 19 (26 %) of the isolates, whereas resistance was exclusively chromosomal (OprD inactivation ± AmpC hyperproduction) in the remaining 54 (74 %) isolates. The acquired β-lactamases detected included 16 VIM-2, one PER-1 and two GES enzymes. PFGE revealed that 15 of the 16 VIM-2 isolates belonged to a single clone, identified as the international high-risk clone ST235 by MLST. bla VIM-2 was preceded by aacA7 in a class I integron, similar to epidemic ST235 isolates described in nearby countries. Additionally, sequencing of bla GES revealed the presence of the carbapenem-hydrolysing enzyme GES-5 in one of the isolates and a novel GES variant, designated GES-27, in the other. GES-27 differed from GES-5 by a single amino acid substitution, proline 167, that was replaced by glutamine. Increasing emergence and dissemination of concerning resistance mechanisms and international clones warrants global surveillance and control strategies. PMID:26638216

  14. Effect of laser cutting parameters on surface quality of low carbon steel (S235

    I. Miraoui

    2012-09-01

    Full Text Available Purpose: This work analysis surface roughness parameters as a function of Laser power and cutting speed. The surface roughness parameters are determined after statistical analysis (ANOVA and propose a simple mathematical model.Design/methodology/approach: Machining were carried out by Laser cutting (CO2 of sheet metal (low carbon steel, S235 produces different surface quality. The statistical processing of the experimental results enabled development of a mathematical model to calculate the cut surface quality according to the cutting parameters used in the present work.Findings: The prediction of surface roughness values according to the mathematical model are very precisely analysis and determining of surface roughness values is a very practical tool by the experimental design method. It enables a high quality range in analysing experiments and achieving optimal exact values. A rather small experimental data are required to generate useful information and thus develop the predictive equations for surface roughness values as Ra, Rt and Rz. Depending on the surface roughness data provided by the experimental design, a first-order predicting equation has been developed in this paper.Practical implications: A simple and practical tool was proposed with the experimental design for predicting the surface roughness values as a function of variables of Laser power and cutting speed for a low carbon steel (S235. This type of analysis gives detailed information on the effect of Laser cutting parameters on the surface roughness.Originality/value: Experimental data was compared with modelling data to verify the adequacy of the model prediction. As shown in this work, the factor of cutting speed the most important influence on the surface roughness.

  15. Evaluation of the neutron cross sections of 235U in the thermal energy region. Final report

    The objective of this work has been to improve the knowledge of the thermal cross sections of the fissile nuclei as a step toward providing a standard data base for the nuclear industry. The methodology uses a form of the Adler-Adler multilevel-fission theory and Breit-Wigner multilevel-scattering theory. It incorporates these theories in a general nonlinear least-squares (LSQ) fitting program SIGLEARNThe analysis methodology in this work was applied to the thermal data on 235U. A reference data file has been developed which includes most of the known data of interest. The first important result of this work is the assessment of the shape uncertainties of the partial cross sections. The results of our studies lead to the following values and error estimates for 235U g factors in a thermal (20.440C) energy spectrum: g/sub f/ = 0.97751 (+-0.11%); g/sub γ/ = 0.98230 (+-0.14%). A second important result of this study is the development of a recommended set of 2200 m/s (0.0253 eV) values of the parameters and the probable range of further adjustment which might be made. The analysis also provides the result of a common interpretation of energy-dependent absolute cross-section data of different measurements to yield a consistent set of experimental 0.0253 eV values with rigorous error estimates. It also provides normalization factors for relative fission and capture cross sections on a common basis with rigorous error estimates. The results of these analyses provide a basis for deciding what new measurements would be most beneficial. The most important of these would be improved direct capture data in the thermal region

  16. Quantification of {sup 235} U and {sup 226} Ra in soil samples by means of Gamma spectroscopy; Cuantificacion de {sup 235} U y {sup 226} Ra en muestras de suelo por medio de espectrometria gamma

    Quintero P, E.; Rojas M, V.P.; Montes M, F.R.; Gaso P, M.I.; Cervantes N, M.L. [Gerencia de Innovacion Tecnologica, A.P. 18-1027, C.P. 11801 Mexico D.F. (Mexico)

    2000-07-01

    In this work it is presented the Gamma Spectroscopy method which is realized in the Environmental Radiological Surveillance Laboratory using the option of deconvolution of a commercial software for the quantification of {sup 235} U and {sup 226} Ra; also is presented the method for the {sup 226} Ra correction activity. (Author)

  17. Measurement of cross section ratios of anti sigmasub(na)(sup(10)B)/ssigmasub(f)(sup(235)U) and anti sigmasub(n,a)(sup(6)Li)sup(235)U in fast neutron spectrum

    The method of measurements of cross section ratios of (n, d) reactions on 10B and 6Li isotopes and cross section of 235U fission in fast neutron spectrum with the help of solid state track detectors is proposed. The method is based on detection of d-particles produced in the reaction H1 H0B(N]7Li and 6Li(n, d)3H with the help of track detectors while artificial mica-fluorophlogopit has served as the detector of fission fragments. The conducted investigations have shown that the meanings of anti σsub(n, a) (6Li)/σsub(f)(sup(235U) and σsub(n5)) (sup(10)B/σsub(f) (sup(235)U) in the cells of fast reactors can be measured by the present methods with approximately 3% error. The attenuators of d-particle energy are needed to increase the accuracy of σsub(n, d)(Li)/σsub(f)(sup(235)U) measurement. The attenuators are placed between the source and the detector to shift the a-particle energy to the side of lower energies in the range where the efficiency of d-particle detection retains constant meaning

  18. Measurement of the fission cross-section ratio for 237Np/235U around 14 MeV neutron energies

    Fission cross-section ratio was determined for 237Np/235U around 14 MeV neutron energies with a back-to-back ionization chamber. Neutrons were produced by a 180 KV accelerator using T(d,n)4He reaction. No significant energy dependence was found in the cross section ratio

  19. Integral parameters for the Godiva benchmark calculated by using theoretical and adjusted fission spectra of 235U

    The theoretical and adjusted Watt spectrum representations for 235U are used as weighting functions to calculate Keff and θf28/θf25 for the benchmark Godiva. The results obtained show that the values of Keff and θf28/θf25 are not affected by spectrum form change. (author)

  20. Relative yields of U-235 fission products measured in a high level radioactive sludge at Savannah River Site

    This paper presents measurements of the concentrations of 42 of the long-lived U-235 fission products in a high-level radioactive waste sludge stored at Savannah River Site. The 42 fision products make up 98% of the waste sludge. We used inductively coupled plasma-mass spectroscopy for the analysis. The relative yields for most of the fission products are in complete agreement with the known relative yields for the beta decay chains of the two asymmetric branches of the slow neutron fission of U-235. Disagreements can be reconciled based on the chemistry of the fission products in the caustic waste sludges, the neutron fluences in SRS reactors, or interferences in the ICP-MS analyses. This paper presents measurements of the concentrations of 42 (98%) of the long-lived U-235 fission products in a high-level radioactive waste sludge stored at the Savannah River Site. We analyzed the sludge with inductively coupled plasma-mass spectroscopy. The relative yields for most of the fission products agree completely with the known relative vields for the beta decay chains of the two asymmetric: branches of the slow neutron fission of U-235. The chemistry of the fission products in the caustic waste sludges, the neutron fluences in SRS reactors, or interferences in the ICP-MS analyses explain the differences in the measured and calculated results

  1. 42 CFR 2.35 - Disclosures to elements of the criminal justice system which have referred patients.

    2010-10-01

    ... Disclosures With Patient's Consent § 2.35 Disclosures to elements of the criminal justice system which have... criminal justice system which have made participation in the program a condition of the disposition of any...) The disclosure is made only to those individuals within the criminal justice system who have a...

  2. 48 CFR 1552.235-77 - Data Security for Federal Insecticide, Fungicide and Rodenticide Act Confidential Business...

    2010-10-01

    ... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Data Security for Federal... SOLICITATION PROVISIONS AND CONTRACT CLAUSES Texts of Provisions and Clauses 1552.235-77 Data Security for... prescribed in 1535.007-70(d), insert the following clause: Data Security for Federal Insecticide,...

  3. 48 CFR 1552.235-78 - Data Security for Toxic Substances Control Act Confidential Business Information (DEC 1997).

    2010-10-01

    ... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Data Security for Toxic... CONTRACT CLAUSES Texts of Provisions and Clauses 1552.235-78 Data Security for Toxic Substances Control Act...: Data Security for Toxic Substances Control Act Confidential Business Information (DEC 1997)...

  4. Research on the determination of 235U fission number by delayed γ-rays absorbed dose rates

    Background: The determination method of 235U fission number by detecting fission products using HPGe detector has been established before. But in some special cases, we need to get the fission number in-time in high intensity radiation environment. HPGe detector has its limitation due to the complex y spectrum accompany with high flux. Purpose: To get rid of the limitation mentioned above, a new method is introduced by detecting the delayed γ-rays absorbed dose rates. Methods: By using independent fission yield together with radioactive decay dates from CENDL 3.0 and ENDF BVII.1, dynamic calculation for total absorbed dose rate in air 1 meter from the source whose compositions were thermal neutron-induced fission products of 235U has been done. Results: A set of absorbed dose rate data of 235U fission products irradiated through fast rabbit irradiation system on Xi'an pulse reactor was recorded. The deviation of the fission neutron number between method by γ-rays absorbed dose rates and method by HPGe detector is 7%. Conclusion: It's feasible to determine the fission neutron number of 235U using delayed γ-rays absorbed dose rates in a high intensity radiated environment. (authors)

  5. Reactor physics studies leading to a fuel cost survey for an HTR system with low U235 enrichment

    Reactor physics studies have been carried out on an HTR system with low U235 enrichment. The work reported establishes the total fuel cost as approximately Pound28/kW and provides sufficient information for an overall plant optimisation. (author)

  6. 78 FR 66330 - Foreign-Trade Zone (FTZ) 235-Lakewood, New Jersey, Notification of Proposed Production Activity...

    2013-11-05

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF COMMERCE Foreign-Trade Zones Board Foreign-Trade Zone (FTZ) 235--Lakewood, New Jersey, Notification of Proposed Production Activity, Cosmetic Essence Innovations, LLC, (Fragrance Bottling), Holmdel, New Jersey...

  7. 77 FR 33253 - Regulatory Guide 8.24, Revision 2, Health Physics Surveys During Enriched Uranium-235 Processing...

    2012-06-05

    ...- 8040 on March 22, 2010 (75 FR 13599). This guide specifies the types and frequencies of surveys that... March 22, 2010, DG-8040 was published with a request for public comments (75 FR 13599). The public... COMMISSION Regulatory Guide 8.24, Revision 2, Health Physics Surveys During Enriched Uranium-235...

  8. Uranium isotope analyses of soil samples collected from Nisshoen, Hiroshima. Implication on the fate of U-235 discharged from the Hiroshima A-bomb

    In the previous study, we detected excess U-235 and Cs-137 from a plastered wall tainted with the streaks of black rain from the Hiroshima A-bomb (Little Boy), thus proving that at least part of unexpended 235U that was contained in the bomb fell with the black rain. In the present work, we tried to detect excess 235U discharged from Little Boy into the nearby environment by measurement of 235U/238U ratio using ICP-MS in soil core samples collected from dried-up ponds in Nissyoen (Nishi-ku, Hiroshima, Japan), a private garden. Depth profile of 235U/238U ratio in one of the core samples showed slightly higher 235U/238U ratio in the deeper layer where the concentrations of fallout Cs-137 from atmospheric nuclear test were smaller. Black rain reportedly fell in Nissyoen after the detonation, but apparently the amount of 235U that should have fell with the rain was not high enough to significantly increase natural 235U/238U ratio there. (author)

  9. Reevaluation of the Correlation between Angiotensinogen Gene M235T Polymorphism and Familial Essential Hypertension Using MS-PCR Technique

    2001-01-01

    Objective Using mutagenically separated allele-specific polymerase-chain-reaction (MS-PCR) technique to determine the correlation between angiotensinogen gene M235T (Ag TM235T) polymorphism and the onset of familial essential hypertension in the population from Jiangsu and Anhui Provinces. Methods (1) Establish and compare the optimal reaction system of PCR-RFLP and MS-PCR technique to detect AgTM235T polymorphism. (2) All subjects were divided into four groups: 62 patients with both hypertension and familial background (FH), 32 normal persons who had familial background (FNH), 26 persons in control group (N) and 10 patients with hypertension but without familial background (NFH group). The genotype of all subjects was determined by MS-PCR technique.Results (1) The frequency of T allele in PCR-RFLP was 0.5, much lower than 0.95 in MS-PCR, which was demonstrated by DNA sequencing. (2) The TT-genotype and the frequency of T allele (TT/T) in FH and FNH groups were much higher than those in N and NFH groups (0.581/0.766 and 0.563/0.766 vs 0.346/0.577 and 0.40/0.550, P<0.005). (3) Persons developing hypertension in FNH group were much younger than other three groups (28.07±9.72 , P<0.025). Conclusion (1) Compared with PCR-RFLP, MS-PCR is a rapid, simple and reliable technique for detection gene polymorphism of Ag TM25T. (2) In Jiangsu and Anhui area, the present study confirms the observation of a higher frequency of the 235T allele of the angiotensinogen gene in hypertension and identifies individuals with family history. Concerning of the age, we might speculate that the AgTM235T polymorphism is only associated with familial essential hypertension.

  10. High Accuracy U-235 Enrichment Verification Station for Low Enriched Uranium Alloys

    The Y-12 National Security Complex is playing a role in the U.S. High Performance Research Reactor (USHPRR) Conversion program sponsored by the U.S. National Nuclear Security Administration's Office of Global Threat Reduction. The USHPRR program has a goal of converting remaining U.S. reactors that continue to use highly enriched uranium (HEU) fuel to low enriched uranium (LEU) fuel. The USHPRR program is currently developing a LEU Uranium-Molybdenum (U-Mo) monolithic fuel for use in the U.S. high performance research reactors.Y-12 is supporting both the fuel development and fuel fabrication efforts by fabricating low enriched U-Mo foils from its own source material for irradiation experiments and for optimizing the fabrication process in support of scaling up the process to a commercial production scale. Once the new fuel is qualified, Y-12 will produce and ship U-Mo coupons with verified 19.75% +0.2% - 0.3% U-235 enrichment to be fabricated into fuel elements for the USHPRRs. Considering this small enrichment tolerance and the transition into HEU being set strictly at 20% U-235, a characterization system with a measurement uncertainty of less than or equal to 0.1% in enrichment is desired to support customer requirements and minimize production costs. Typical uncertainty for most available characterization systems today is approximately 1-5%; therefore, a specialized system must be developed which results in a reduced measurement uncertainty. A potential system using a High-Purity Germanium (HPGe) detector has been procured, and tests have been conducted to verify its capabilities with regards to the requirements. Using four U-Mo enrichment standards fabricated with complete isotopic and chemical characterization, infinite thickness and peak-ratio enrichment measurement methods have been considered for use. As a result of inhomogeneity within the U-Mo samples, FRAM, an isotopic analysis software, has been selected for initial testing. A systematic approach

  11. Assaying of 235U fission layers for nuclear measurements with a gridded ionization chamber

    An ionization chamber with a Frisch grid is used to determine both the energy (E) of the charged particles emitted from the sample positioned coplanar with the cathode, and the cosine of the emission angle (theta) with respect to the normal of the cathode. Using the combined information on cos theta and E, problems in particle counting due to sample absorption and scattering effects can be circumvented and sample source strengths are readily determined to an accuracy of 0.3%. However, it is emphasized that the source strength can be determined from the particles emitted in a large solid angle close to 2π steradian, which means a considerable higher efficiency than for the conventional low geometry counting techniques. Moreover the present method, within reasonable limits is insensitive to source shape and thickness homogeneity. The technique will be illustrated by measurements of alpha particles and fission fragments emitted from a set of four vacuum evaporated UF4, three electrodeposited and one suspension-sprayed 235U3O8 layers. (author)

  12. Sealing Treatment of Aluminum Coating on S235 Steel with Thermal Diffusion of Zinc

    Wang, Yong; Zhang, Timing; Zhao, Weimin; Tang, Xiuyan

    2015-08-01

    The study introduced a thermal diffusion sealing treatment for arc-sprayed aluminum coating on S235 carbon steel. The sprayed aluminum-zinc duplex coating was heated to 420 °C, so that the low-melting-point zinc could diffuse into the pores of the aluminum coating. Optical microscope, microhardness, electron probe microanalysis, and x-ray diffraction were used to evaluate the sealing treatment. The calculated diffusion coefficient for zinc in the arc-sprayed aluminum coating was approximately 7.735 × 10-9 cm2/s. The diffused zinc could increase the compactness and microhardness of the aluminum coating. Nevertheless, adverse interface reactions could destroy the coating if the zinc made contact with the steel substrate. FeZn10 could form initially, and then the heat from the exothermic reactions between zinc and iron would initiate the reactions among iron, aluminum, and zinc. FeAl-Zn x , FeAl2-Zn x , and Fe2Al5-Zn x were generated following FeZn10. The defected structures were mainly composed of Fe2Al5-Zn x and FeZn10. All of these formed tough, brittle, intermetallics that have a negative effect on the coating performance. Thus, the contact between zinc and the steel substrate should be avoided, and the holding time should be restricted to 8.16 × 106 L 2 to prevent the generation of intermetallics.

  13. 2,3,5-Triphenyl-2H-tetrazol-3-ium iodide

    Hoong-Kun Fun

    2012-09-01

    Full Text Available The asymmetric unit of the title molecular salt, C19H15N4+·I−, contains four 2,3,5-triphenyl-2H-tetrazol-3-ium cations and five iodide anions, with two of the latter lying on crystallographic inversion centres. In each cation, the tetrazole ring is essentially planar (r.m.s. deviations = 0.004–0.007 Å. The dihedral angles between the tetrazole ring and its three attached benzene rings in the four independent cations are: 12.9 (4, 67.0 (4, 48.1 (4; 20.8 (4, 51.1 (4, 62.3 (4; 11.4 (4, 52.3 (4, 47.3 (4 and 6.0 (4, 85.7 (4, 43.5 (4°. A C—H...I hydrogen bond and C—H...π interactions are observed in the crystal.

  14. Standard specification for uranium hexafluoride enriched to less than 5 % 235U

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This specification covers nuclear grade uranium hexafluoride (UF6) that either has been processed through an enrichment plant, or has been produced by the blending of Highly Enriched Uranium with other uranium to obtain uranium of any 235U concentration below 5 % and that is intended for fuel fabrication. The objectives of this specification are twofold: (1) To define the impurity and uranium isotope limits for Enriched Commercial Grade UF6 so that, with respect to fuel design and manufacture, it is essentially equivalent to enriched uranium made from natural UF6; and (2) To define limits for Enriched Reprocessed UF6 to be expected if Reprocessed UF6 is to be enriched without dilution with Commercial Natural UF6. For such UF6, special provisions, not defined herein, may be needed to ensure fuel performance and to protect the work force, process equipment, and the environment. 1.2 This specification is intended to provide the nuclear industry with a standard for enriched UF6 that is to be used in the pro...

  15. Fission fragment distributions in resolved resonances of 235U(n,f)

    Fission fragment energies and emission angles with respect to the incident neutron beam were measured for 235U(n,f) using a twin Frisch-gridded ionization chamber. The neutron energy range from 0.006 eV to 0.5 MeV was covered in a time-of-flight experiment at the Geel Electron Linear Accelerator (GELINA). Fission fragment mass-, and total kinetic energy distributions were evaluated for thermal neutrons, for resolved resonances below 40 eV, and in certain energy bins at higher neutron energy. Fluctuations in the average total kinetic energy with respect to the thermal value of up to ∼450 keV are observed for resonances below 40 eV. The variations of from resonance to resonance can be related to changes in the population of the three fission exit channels. Also the symmetric fission yields or valley to peak ratios of the mass distributions fluctuate from resonance to resonance up to a factor 2. Both fluctuations are not correlated with the resonance spin of the compound nucleus. An explanation for the fluctuations is proposed. (author)

  16. Adsorption and corrosion inhibiting effect of riboflavin on Q235 mild steel corrosion in acidic environments

    Chidiebere, Maduabuchi A. [Institute of Metal Research, Chinese Academy of Sciences, 62 Wencui Rd, Shenyang 110016 (China); Electrochemistry and Materials Science Research Laboratory, Department of Chemistry, Federal University of Technology Owerri, PMB 1526 Owerri (Nigeria); Oguzie, Emeka E. [Electrochemistry and Materials Science Research Laboratory, Department of Chemistry, Federal University of Technology Owerri, PMB 1526 Owerri (Nigeria); Liu, Li [Institute of Metal Research, Chinese Academy of Sciences, 62 Wencui Rd, Shenyang 110016 (China); Li, Ying, E-mail: liying@imr.ac.cn [Institute of Metal Research, Chinese Academy of Sciences, 62 Wencui Rd, Shenyang 110016 (China); Wang, Fuhui [Institute of Metal Research, Chinese Academy of Sciences, 62 Wencui Rd, Shenyang 110016 (China)

    2015-04-15

    The inhibiting effect of Riboflavin (RF) on Q235 mild steel corrosion in 1 M HCl and 0.5 M H{sub 2}SO{sub 4} at 30 °C temperature was investigated using electrochemical techniques (electrochemical impedance spectroscopy and potentiodynamic polarization). The obtained results revealed that RF inhibited the corrosion reaction in both acidic solutions. Maximum inhibition efficiency values in 1 M HCl and 0.5 M H{sub 2}SO{sub 4} were 83.9% and 71.4%, respectively, obtained for 0.0012 M RF. Polarization data showed RF to be a mixed-type inhibitor, while EIS results revealed that the RF species adsorbed on the metal surface. The adsorption of RF followed Langmuir adsorption isotherm. Atomic force microscopy (AFM), Fourier transform infrared spectroscopy (FTIR) and scanning electron microscopy (SEM) studies confirmed the formation of a protective layer adsorbed on the steel surface. Quantum chemical calculations were used to correlate the inhibition ability of RF with its electronic structural parameters. - Highlights: • The inhibitory mechanism was influenced by the nature of acid anions. • RF has reasonable inhibition effect especially in 1 M HCl solution. • Polarization studies showed that RF functioned as a mixed type inhibitor. • Improved surface morphology was observed in the presence of RF.

  17. Measurement of 235U enrichment in UF6 by passive gamma spectrometry

    For the assay of UF6, a single-channel analyzer (SCA) system of a passive gamma spectrometer has been developed. Basic measuring conditions were studied: such as the effects of sample density and heterogeneity and the effects of cylinder material and wall thickness. Called ''enrichment analyzer'', the system is operated to carry out the measurement and calculation of 235U enrichment by a directive of the program in a calculator. The resulting data are available in real time output. Measurements were carried out in two modes: ''all way'' mode which measured in the rotation of the cylinder and the up-and-down motion of the detector, and ''spot'' mode which measured at one point on the cylinder. The average accuracy was about 1.8% in case of the former, and 3.2% in case of the latter. It was shown that the ''all way'' mode is preferable, but the ''spot'' mode is also necessary for the assay of large cylinders such as 30 A type. (J.P.N.)

  18. Determination of the isotopic ratio 235U/238U in UF6 using quadrupole mass spectrometry

    In this work measurements of isotope ratios 235U / 23'8U in uranium hexafluoride are carried out using a quadrupole mass spectrometer. The operational parameters, which affect the final precision of the results, are standardized. Optimized procedures for the preparation of uranium hexafluoride samples by fluorination of uranium oxides using cobalt trifluoride method are established. Careful attention is given to the process of purification of uranium hexafluoride samples by fractional distillation. Adequate statistical methods for analysing the results obtained for single ratio measurements as well as the ratio ' of isotopic ratios of sample and standard ar.e developed. A precision of about 10-4 for single ratio measurements and accuracy of about 0,3% for the ratio of sample and standard ratios are obtained. These results agree with the values which have been obtained using magnetic mass spectrometers. The procedures and methods established in this work can be employed in the systematic uranium isotope analysis in UF6 form. (author)

  19. The Criticality Calculation Of Fission Yield Of U-235 Solution And Its Radiation Dose

    The calculation assesment of fission yield of U-235 solution in the extraction and evaporation units has been performed for the prediction of that when the criticality accident occurs in the production of fuel element for the research reactor. The Grover Tuck and fission distribution probability methods are used in this case. The calculation result using the fission distribution probability methods show the fission of 2,7 x 1018 for the uranium concentration of 200 grams/litre and that of 2,5 x 1018 fissions for U of 40 grams/litre in the extraction unit. The calculation results from the evaporation unit revealed the fission of 3,1 x 1018 for 400 grams/litre uranium and 1,77 x 1018 fissions for 80 grams/litre uranium. Using the Grover Tuck calculation method give results that 8,267 x 1017 fissions and 2,878 x 1017 fissions respectively. Radiation dose of 200 gram/litre solution is about 1450,29 Rad for neutron and 4785,96 Rad for gamma ray

  20. Numbers of prompt neutrons per fission for U233, U235, Pu239, and Cf252

    An absolute measurement of #-v#, the average number of prompt neutrons emitted per fission, is being made for the spontaneous fission of Cf262. The relative values of #-v# are being measured for neutron-induced fission of U233, U235, and Pu239, and are being compared with the spontaneous fission #-v# of Cf252. Neutrons with energies between thermal and 15 MeV are used. Particular emphasis is put on studying the dependence of #-v# on the incident neutron energy. A fission counter containing the appropriate isotope is placed in the centre of a large cadmium-loade d liquid scintillator. Through the fissionable isotope is passed a collimated beam of neutrons. Fission events, identified by pulses from the fission counter, open an electronic gate between the large liquid scintillator and a scaler. Scintillator pulses due to capture in the scintillating solution of thermalized fission neutrons are counted during the gate. The fission neutrons are detected almost independently of energy and with very high efficiency. With this technique values of #-v# to an accuracy of 1 % are expected. (author)

  1. Burnup determination of silicide MTR fuel elements (20% 235U) in the LFR laboratory

    The LFR facility is a radiochemical laboratory designed and constructed with a hot-cells line, a glove-box and a fume hood, all of them suited to work radioactive materials. At the beginning of the LFR operation a series of dissolutions of MTR irradiated silicide fuel elements was performed, and determined its isotopic composition of 235U, 239Pu and 148Nd (the last one as burn up monitor), by the thermal ionization mass spectrometry (TIMS). These assays are linked to the IAEA RLA/4/018 Regional Project 'Management of Spent Fuel from Research Reactors'. It is concluded that this technique of burn up measurement is powerful and accurate when properly applied, and permit to validate the calculation codes when isotopic dilution is performed. It is worth noticed the LFR capacity to carry on different research and development programs in the nuclear fuel cycle field, such as the previously mentioned absolute burn up measurements, or the evaluation of radioactive waste immobilization processes and researches on burnable poisons. (author)

  2. A `water spout' maser jet in S235AB-MIR

    Burns, R. A.; Imai, H.; Handa, T.; Omodaka, T.; Nakagawa, A.; Nagayama, T.; Ueno, Y.

    2015-11-01

    We report on annual parallax and proper motion observations of H2O masers in S235AB-MIR, which is a massive young stellar object in the Perseus Arm. Using multi-epoch VLBI (very long baseline interferometry) astrometry we measured a parallax of π = 0.63 ± 0.03 mas, corresponding to a trigonometric distance of D= 1.56^{+0.09}_{-0.08} kpc, and source proper motion of (μαcos δ, μδ) = (0.79 ± 0.12, -2.41 ± 0.14) mas yr-1. Water masers trace a jet of diameter 15 au which exhibits a definite radial velocity gradient perpendicular to its axis. 3D maser kinematics were well modelled by a rotating cylinder with physical parameters: vout = 45 ± 2 km s-1, vrot = 22 ± 3 km s-1, i = 12° ± 2°, which are the outflow velocity, tangential rotation velocity and line-of-sight inclination, respectively. One maser feature exhibited steady acceleration which may be related to the jet rotation. During our 15-month VLBI programme there were three `maser burst' events caught `in the act' which were caused by the overlapping of masers along the line of sight.

  3. system design and making of a system for 235U enrichment by laser

    Since the conventional nuclear fuel production techniques were expensive and hard to implement, starting from 1974 new production techniques had been developed. Among them, the laser isotope separation (LIS) was the most important one that a substantial amount of work have been paid on it. Although it hasn't been commercially applied to industry yet, it is much simpler and cheaper compared with nozzle and diffusion techniques. The system based on the laser induced florescence (LIRF) technique, developed in the Physics Department of METU, was planned to be modified for the use of U235 enrichment.In the frame of work the vacuum chambers were redesigned. In the atomic beam system implemented with LIRF, K (potasium) is evaporated, atomic beam and calibration parameters were measured. Single induced florescence experiments were performed and the focus was made on the frequency and intensity stability of lasers. As to compatibility with the available lasers, with the constraints on some promising spectrum lines a complete system was elaborately designed

  4. Textile UV detector with 2,3,5-triphenyltetrazolium chloride as an active compound

    In this paper, results on the construction of a new flat textile-based UV light dosimeter are reported. As a textile support polyamide woven fabric was chosen, which was surface-modified with 2,3,5-triphenyltetrazolium chloride (TTC). At first, spectrophotometric and dynamic laser light scattering results on the steady-state UV irradiation of aqueous TTC solutions in the presence of oxygen are discussed. If irradiated, TTC converts to the corresponding formazan molecules of red colour. The size and size distribution of the particles is related to the absorbed radiation and pH of the solution. When TTC molecules reside on polyamide textile, UV irradiation causes a colour change from white to deep red. The tinge intensity depends on the absorbed energy per unit surface area. On this basis, the calibration parameters of the detectors, such as dose sensitivity, dose range, quasi-linear dose range, were calculated. Furthermore, the improvement of the dosimeters' resistance to atmospheric conditions was achieved and assessed through washing fastness tests. Finally, the detectors were proved to be adequate for measurements of the 2D distribution of absorbed UV energy. A simple method of UV dose distribution measurements was proposed. The textile-based systems show promise as dosimeters.

  5. Adsorption and corrosion inhibiting effect of riboflavin on Q235 mild steel corrosion in acidic environments

    The inhibiting effect of Riboflavin (RF) on Q235 mild steel corrosion in 1 M HCl and 0.5 M H2SO4 at 30 °C temperature was investigated using electrochemical techniques (electrochemical impedance spectroscopy and potentiodynamic polarization). The obtained results revealed that RF inhibited the corrosion reaction in both acidic solutions. Maximum inhibition efficiency values in 1 M HCl and 0.5 M H2SO4 were 83.9% and 71.4%, respectively, obtained for 0.0012 M RF. Polarization data showed RF to be a mixed-type inhibitor, while EIS results revealed that the RF species adsorbed on the metal surface. The adsorption of RF followed Langmuir adsorption isotherm. Atomic force microscopy (AFM), Fourier transform infrared spectroscopy (FTIR) and scanning electron microscopy (SEM) studies confirmed the formation of a protective layer adsorbed on the steel surface. Quantum chemical calculations were used to correlate the inhibition ability of RF with its electronic structural parameters. - Highlights: • The inhibitory mechanism was influenced by the nature of acid anions. • RF has reasonable inhibition effect especially in 1 M HCl solution. • Polarization studies showed that RF functioned as a mixed type inhibitor. • Improved surface morphology was observed in the presence of RF

  6. Streptomyces lunalinharesii Strain 235 Shows the Potential to Inhibit Bacteria Involved in Biocorrosion Processes

    Juliana Pacheco da Rosa

    2013-01-01

    Full Text Available Four actinomycete strains previously isolated from Brazilian soils were tested for their antimicrobial activity against Bacillus pumilus LF-4 and Desulfovibrio alaskensis NCIMB 13491, bacteria that are well known to be involved in biofilm formation and biocorrosion. Strain 235, belonging to the species Streptomyces lunalinharesii, inhibited the growth of both bacteria. The antimicrobial activity was seen over a wide range of pH, and after treatment with several chemicals and heat but not with proteinase K and trypsin. The antimicrobial substances present in the concentrated supernatant from growth media were partially characterized by SDS-PAGE and extracellular polypeptides were seen. Bands in the size range of 12 to 14.4 kDa caused antimicrobial activity. Transmission electron microscopy of D. alaskensis cells treated with the concentrated supernatant containing the antimicrobial substances revealed the formation of prominent bubbles, the spherical double-layered structures on the cell membrane, and the periplasmic space completely filled with electron-dense material. This is the first report on the production of antimicrobial substances by actinomycetes against bacteria involved in biocorrosion processes, and these findings may be of great relevance as an alternative source of biocides to those currently employed in the petroleum industry.

  7. Spectroscopic investigation of plasma electrolytic borocarburizing on q235 low-carbon steel

    Highlights: • The plasma discharge behaviors for PEB/C on steels were evaluated by OES. • Electron temperature, concentration, atomic ionization degree were calculated. • The decomposition mechanism of electrolyte and was analyzed. - Abstract: A plasma electrolytic borocarburizing process (PEB/C) in borax electrolyte with glycerin additive was employed to fabricate a hardening layer on Q235 low-carbon steel. Optical emission spectroscopy (OES) was utilized to investigate the spectroscopy characteristics of plasma discharge around the steel during PEB/C process. Some plasma parameters were calculated in terms of OES. The electron temperature and electron concentration in plasma discharge zone is about 3000–12,000 K and 2 × 1022 m−3–1.4 × 1023 m−3. The atomic ionization degrees of iron, carbon and boron are 10−16–10−3, and 10−23–10−6, 10−19–10−4, respectively, which depend on discharge time. The surface morphology and cross-sectional microstructure of PEB/C hardening layer were observed, and the electrolyte decomposition and plasma discharge behaviors were discussed

  8. A `Water Spout' Maser Jet in S235AB-MIR

    Burns, Ross A; Handa, Toshihiro; Omodaka, Toshihiro; Nakagawa, Akiharu; Nagayama, Takumi; Ueno, Yuji

    2015-01-01

    We report on annual parallax and proper motion observations of H2O masers in S235AB-MIR, which is a massive young stellar object in the Perseus Arm. Using multi-epoch VLBI astrometry we measured a parallax of pi = 0.63 +- 0.03 mas, corresponding to a trigonometric distance of D = 1.56+-0.09 kpc, and source proper motion of ( u alpha cos d , u d) = (0.79 +- 0.12, -2.41 +- 0.14) mas/yr. Water masers trace a jet of diameter 15 au which exhibits a definite radial velocity gradient perpendicular to its axis. 3D maser kinematics were well modelled by a rotating cylinder with physical parameters: v_out = 45+-2 km/s, v_rot = 22+-3 km/s, i = 12+-2 degrees, which are the outflow velocity, tangential rotation velocity and line-of-sight inclination, respectively. One maser feature exhibited steady acceleration which may be related to the jet rotation. During our 15 month VLBI programme there were three `maser burst' events caught `in the act' which were caused by the overlapping of masers along the line of sight.

  9. Measurement of prompt neutrons from fission fragments for {sup 235}U(n{sub th}, f)

    Nishio, Katsuhisa; Yamamoto, Hideki; Jinno, Ikuo; Kimura, Itsuro; Nakagome, Yoshihiro [Kyoto Univ. (Japan)

    1997-03-01

    When the level density parameter is obtained from neutron resonance experiment and so forth, its value depends upon its model. In particular, the value forms 1.5 times difference by if the level increase due to collective motion is considered or not. The measuring method shown in this report has a characteristics capable of obtain an absolute value of the level density parameter. Then, in this paper, a consideration using Iljinov`s empirical equation on shell effect and collective motion of the fission fragment was conducted and a investigation on shell effect and collective motion of the fission fragment was executed. as a result, the level density parameter of the fission fragment obtained by the {sup 235}U(n{sub th},f) showed a distribution of a sawtooth wave shape, which is resemble to that of {sup 252}Cf(sf). And, it was found that this distribution can be explained by an empirical equation considering shell effect of fission fragment dependency and collective motion, and so forth. (G.K.)

  10. 235例410个周期夫精人工授精分析

    卢艳梅; 张朝晖; 李凤艳; 王志芳; 梁辉

    2009-01-01

    目的 探讨影响宫腔内人工授精(intra-uterine insemination,IUI)治疗成功的临床因素.方法 通过对我院235例共410个周期接受IUI治疗妇女的促排卵方案、IUI的时机、IUI的周期数进行统计,分析其与妊娠的关系.结果 ①IUI治疗结局与促排卵方案有关.②1~4个周期IUI治疗的妊娠率分别为12.67%、13.01%、18.75%、6.67%,5~6周期IUI治疗的妊娠率均为0,前4周期IUI治疗的妊娠率明显高于4个以上周期(P<0.05). 结论 1~4个周期IUI治疗的妊娠率明显高于4个以上的周期,增加IUI周期数不能提高成功率.

  11. Characterization of 235U targets for the development of a secondary neutron fluence standard

    The MetroFission project, a Joint Research Project within the European Metrology Research Program, aims at addressing a number of metrological problems involved in the design of proposed Generation IV nuclear reactors. As part of this project a secondary neutron fluence standard is being developed and tested at the neutron time-of-flight facility GELINA of the JRCs Institute for Reference Materials and Measurements. Such a secondary standard will help to arrive at the neutron cross section measurement uncertainties required for the design and safety assessment of new generation power plants and fuel cycles. Such a neutron fluence device contains targets for which the neutron induced cross section is considered to be a standard. A careful preparation and characterization of these samples is an essential part of the development of the secondary standard. In this framework a set of 235U targets has been produced by vapour deposition of UF4 on aluminium backings by IRMMs target preparation laboratory. These targets have been characterized for both their total mass and mass distribution over the sample area. (author)

  12. O polimorfismo AGT*M235T na disfunção cardíaca de etiologia isquêmica aguda: projeto gisca AGT*M235T polymorphism in acute ischemic cardiac dysfunction: the gisca project

    Claudia Guerra Murad Saud; Amália Faria dos Reis; Arlisa Monteiro de Castro Dias; Rosemery Nunes Cardoso; Ana Cristina Klem Vargas Carneiro; Leandro Pereira de Souza; Ana Beatriz Monteiro Fonseca; Georgina Severo Ribeiro; Carlos Augusto Cardozo de Faria

    2010-01-01

    FUNDAMENTO: O polimorfismo AGT*M235T tem sido associado a elevados níveis séricos de angiotensinogênio (AGT), hipertensão arterial sistêmica e disfunção cardíaca (DC). OBJETIVO: Testar a hipótese de haver associação entre polimorfismo AGT*M235T e o risco de desenvolver disfunção cardíaca (insuficiência cardíaca ou disfunção sistólica ventricular esquerda assintomática) pós-síndrome coronariana aguda (SCA), durante o período de internação hospitalar. MÉTODOS: Foram estudados 363 pacientes (ida...

  13. Derivation of decay heat benchmarks for U235 and Pu239 by a least squares fit to measured data

    A least squares technique used by previous authors has been applied to an extended set of available decay heat measurements for both U235 and Pu239 to yield simultaneous fits to the corresponding beta, gamma and total decay heat. The analysis takes account of both systematic and statistical uncertainties, including correlations, via calculations which use covariance matrices constructed for the measured data. The results of the analysis are given in the form of beta, gamma and total decay heat estimates following fission pulses and a range of irradiation times in both U235 and Pu239. These decay heat estimates are considered to form a consistent set of benchmarks for use in the assessment of summation calculations. (author)

  14. Measurement of multiplicity and total energy of gamma radiation following the U-235 fission induced by resonance neutrons

    The spectroscopy of γ-radiation following the fission of U-235 induced by resonance neutrons with energies from 0.7 eV to 36 eV from the IBR-30 pulsed source was studied. The ionization chamber containing 10 g of uranium enriched to 90% with U-235 and the Ge(Li) detector abour 30 cm3 in volume having an energy resolution of 2.8 keV at 1333 keV energy were operating in coincidence. The results were analysed within the multidimensional procedure. After reconstructing the measured spectrum the γ-spectrum in the energy range from 0.1 to 1.6 MeV has been obtained. The following integral characteristics have been calculated: multiplicity, total and average energies. The average energies for the 3- and 4- resonances are reported

  15. 235Uranium isotope abundance certified reference material for gamma spectrometry EC nuclear reference material 171 certification report

    This certification report contains the information necessary for the final certification of EC nuclear reference material 171. It is also intended to inform the user of the reference material concerned on technical/scientific details which are not given in the certificate. The report describes the reference material which consists of sets of U3O8 samples with five different 235U/U abundances, filled in cylindrical aluminium cans. The can bottom serves as window for emitted gamma radiation. The report describes how the 235U/U abundances were characterized, how the other properties relevant for gamma measurements were determined and gives all connected results as well as those from the verification measurements. Appendix A represents the draft certificate. 32 refs

  16. $\\gamma$-ray energy spectra and multiplicities from the neutron-induced fission of $^{235}$U using STEFF

    An experiment is proposed to use the STEFF spectrometer at n_TOF to study fragment $\\gamma$-correlations following the neutron-induced fission of $^{235}$U. The STEFF array of 12 NaI detectors will allow measurements of the single $\\gamma$-energy, the $\\gamma$ multiplicity, and the summed $\\gamma$energy distributions as a function of the mass and charge split, and deduced excitation energy in the fission event. These data will be used to study the origin of fission-fragment angular momenta, examining angular distribution eects as a function of incident neutron energy. The principal application of this work is in meeting the NEA high-priority request for improved $\\gamma$ray data from $^{235}$U(n; F). To improve the detection rate and expand the range of detection angles, STEFF will be modied to include two new ssion-fragment detectors each at 45 to the beam direction.

  17. Development of a rapid radiochemical procedure for the separation of /sup 235m/U from 239Pu

    We have developed a rapid radiochemical procedure for the isolation and purification of /sup 235m/U (t/sub 1/2/ = 26 minutes) from 239Pu samples up to 250 mg. Purpose of developing the procedure was to measure the thermal neutron fission cross section of the isomeric meta state of 235U. We used rapid small-scale anion exchange columns that absorbed uranium in concentrated HBr but did not absorb plutonium. Uranium was easily eluted with very dilute HF. The separation time required 25 to 35 minutes. We were able to attain a separation factor of uranium from plutonium of approximately 1 x 1010 with samples ranging from 1 x 1010 to 3 x 1011. The ratio of the fission cross sections for the meta to ground state was measured to be 1.42. 4 figs., 1 tab

  18. Cross sections and neutron yields for U233, U235 and Pu239 at 2200 m/sec

    The experimental information on the 2200 m/sec values for σabs, σf, α, ν and η for 233U , 235U and 23 been collected and discussed. The values will later be used in an evaluation of a 'best' set of data. In appendix the isotopic abundances of the uranium isotopes are discussed and also the alpha activities of the uranium isotopes and Pu-239

  19. Biochemical indices of blood serum of cows with acute radiation sickness due to nuclear fission products. [/sup 235/U

    Yakovleva, V.P.; Burov, N.I

    1977-01-01

    Fission products of /sup 235/U were given to cows daily for 4 days. The animals developed the intestinal form of acute radiation sickness and did not survive longer than 20 days. Blood samples were taken at intervals and determinations were made on activity of transaminases and alkaline phosphatase, serum carbohydrates, cholesterol, lecithin, total lipids, K, Na, and Fe. Results showed an increase in enzyme activity, increase in carbohydrate levels, decrease in lipids and electrolytes, and weight loss. (HLW)

  20. Fission Fragment Angular Distribution measurements of 235U and 238U at CERN n_TOF facility

    Leal-Cidoncha E.

    2016-01-01

    In order to measure the FFAD of neutron-induced reactions, a fission detection setup based on parallel-plate avalanche counters (PPACs has been developed and successfully used at the CERN-n_TOF facility. In this work, we present the preliminary results on the analysis of new 235U(n,f and 238U(n,f data in the extended energy range up to 200 MeV compared to the existing experimental data.

  1. Bulgarian Experience with the Implementation of 235U Higher Enriched Fuel in WWER-1000 (Water Chemistry Aspects)

    Water chemistry and radiochemistry plant data from the WWER-1000 Units in NPP Kozloduy confirm that a realistic way for satisfactory implementation of 235U high enriched (up to 4.3%) fuel has been found. The main requirements are: implementation of solid neutron burnable absorbers; application of corrosion resistant fuel cladding; and the maintenance of suitable coolant water chemistry. The implementation at NPP Kozloduy is described. (author)

  2. Comparison of evaluations for 235U, 239Pu, 240Pu, 241Pu and 242Pu with integral measurements

    The evaluations for 235U, 239Pu, 240Pu, 241Pu and 242Pu are considered. Intercomparison is made of the neutron cross section data from INDL/A, ENDL-84, ENDF/B-5 and ENDF/B-6 (where applicable). Integral measurements of the spectrum averaged cross sections are compared to the values derived from evaluated data libraries. (author). 40 refs, 49 figs, 11 tabs

  3. Investigation on Wear Resistance of Fe-based Alloy Coating Prepared by Argon Arc Cladding on Q235%Q235钢氩弧熔覆铁基合金涂层的耐磨性研究

    郭国林; 张娜; 王俊杰; 李刚

    2012-01-01

    和用氩弧熔覆技术,选择合适的工艺参数,在Q235钢材表面熔覆了铁基合金耐磨涂层.通过金相显微镜和SEM分析了熔覆涂层的显微组织,并测试了涂层的显微硬度和耐磨性.结果表明,在Q235钢表面制备了以马氏体组织和γ-(Fe-Cr-Ni-C)合金固溶体为基体,以(Cr,Fe)7C3、Fe3C、Fe2B等化合物为增强相的合金涂层;涂层的显微硬度可达600 HV;涂层的耐磨性较基体提高近8倍.在低碳钢表面熔覆一层耐磨材料,既保留了低碳钢较高的塑、韧性,又提高了表面层的硬度和耐磨性.%By plasma cladding technology,a wear resistant coating with Fe-based alloy was prepared on the surface of Q235 steel. The microstructure of the bonding coating was investigated by optical microscope and scanning electron microscope. The microhardness and wear resistance performance of the coating was tested. The results show that the alloy coating on the surface of Q235 is conposed of the matrix of martensitic structure and y- (Fe-Cr-Ni-C) alloy solid solution ,and the reinforcing phases of (Cr, Fe)7Cγ/Fe3C/Fe2B and other compounds. The microhardness of the coating can reach 600 HV and the wear resistance is about 8 times higher than that of Q235 steel substrate. When deposited a wear-resistant layei on the surface of mild steel, the high plasticity and ductility of mild steel can be preserved, and the hardness and wear resistance of the cladding layer can also be improved greatly.

  4. Measurement of trace uranium-235 and plutonium-239, 240 in waste tank material at the Savannah River Site

    Mahannah, F.N.; Maxwell, S.L. III.

    1992-01-01

    At the Savannah River Site (SRS), large quantities of radioactive liquid waste are evaporated to reduce volume before eventual processing through the In-Tank Precipitation process. Actinides in the liquid waste are only slightly soluble in the highly alkaline waste solution. Since some of the actinide isotopes are fissionable, the quantities being processed through the evaporator system are of interest. To better quantify the concentration and mass of fissionable material entering the evaporator system and eventually deposited as salt, analysis of the actinide elements were necessary. The predominant fissionable actinide isotopes of interest are U{sup 235} and Pu{sup 239}. To enable the reliable measurement of these radionuclides, the Central Laboratory has developed high speed separation techniques to measure U{sup 235} content by Isotope Dilution Mass Spectrometry and Pu{sup 239,240} by alpha spectrometry. Due to the high radioactivity levels in the samples all separations are performed in shielded analytical cells. Uranium is purified and concentrated using a high speed extraction chromatography technique that employs applied vacuum and columns containing tri (2-ethylene) phosphate solvent coated on a small particle inert support. The uranium method enables measurement of U{sup 235} concentrations to 1 {times} 10{sup {minus}4} g/L. Plutonium is purified and concentrated using a high speed anion exchange technique. The Pu method enables measurements of Pu{sup 239,240} to 2 {times} 10{sup {minus}6} g/L.

  5. Measurement of trace uranium-235 and plutonium-239, 240 in waste tank material at the Savannah River Site

    Mahannah, F.N.; Maxwell, S.L. III

    1992-08-01

    At the Savannah River Site (SRS), large quantities of radioactive liquid waste are evaporated to reduce volume before eventual processing through the In-Tank Precipitation process. Actinides in the liquid waste are only slightly soluble in the highly alkaline waste solution. Since some of the actinide isotopes are fissionable, the quantities being processed through the evaporator system are of interest. To better quantify the concentration and mass of fissionable material entering the evaporator system and eventually deposited as salt, analysis of the actinide elements were necessary. The predominant fissionable actinide isotopes of interest are U{sup 235} and Pu{sup 239}. To enable the reliable measurement of these radionuclides, the Central Laboratory has developed high speed separation techniques to measure U{sup 235} content by Isotope Dilution Mass Spectrometry and Pu{sup 239,240} by alpha spectrometry. Due to the high radioactivity levels in the samples all separations are performed in shielded analytical cells. Uranium is purified and concentrated using a high speed extraction chromatography technique that employs applied vacuum and columns containing tri (2-ethylene) phosphate solvent coated on a small particle inert support. The uranium method enables measurement of U{sup 235} concentrations to 1 {times} 10{sup {minus}4} g/L. Plutonium is purified and concentrated using a high speed anion exchange technique. The Pu method enables measurements of Pu{sup 239,240} to 2 {times} 10{sup {minus}6} g/L.

  6. Measurement of trace uranium-235 and plutonium-239, 240 in waste tank material at the Savannah River Site

    At the Savannah River Site (SRS), large quantities of radioactive liquid waste are evaporated to reduce volume before eventual processing through the In-Tank Precipitation process. Actinides in the liquid waste are only slightly soluble in the highly alkaline waste solution. Since some of the actinide isotopes are fissionable, the quantities being processed through the evaporator system are of interest. To better quantify the concentration and mass of fissionable material entering the evaporator system and eventually deposited as salt, analysis of the actinide elements were necessary. The predominant fissionable actinide isotopes of interest are U235 and Pu239. To enable the reliable measurement of these radionuclides, the Central Laboratory has developed high speed separation techniques to measure U235 content by Isotope Dilution Mass Spectrometry and Pu239,240 by alpha spectrometry. Due to the high radioactivity levels in the samples all separations are performed in shielded analytical cells. Uranium is purified and concentrated using a high speed extraction chromatography technique that employs applied vacuum and columns containing tri (2-ethylene) phosphate solvent coated on a small particle inert support. The uranium method enables measurement of U235 concentrations to 1 x 10-4 g/L. Plutonium is purified and concentrated using a high speed anion exchange technique. The Pu method enables measurements of Pu239,240 to 2 x 10-6 g/L

  7. Investigation of resonance structure of neutron cross-sections and α-value of 235U for different temperatures

    The time-of-flight spectra for γ-ray multiplicities from 1 to 15 were measured on the 122 m flight path of the IBR-30 pulsed neutron booster using the 16-section liquid scintillation detector with the 80 l total volume for thin metallic 235U radiator-sample (0.25 mm) with and without 0.5 mm thickness 235U filter-sample at two temperatures (100 deg. and 293 deg.). Multiplicity spectra and alpha values α=σγ/σf were obtained from time-of-flight spectra after subtracting background components for the energy groups over the range of 2.15-2150 eV with and without filter samples of 235U. The self-indication functions in capture and fission cross-sections for these two temperatures and the Doppler-coefficient for the alpha values were determined from the time-of-flight spectra of 3-rd and sum of the 6 to 9-th multiplicities. (author)

  8. 235U Determination using In-Beam Delayed Neutron Counting Technique at the NRU Reactor

    Andrews, M. T. [Los Alamos National Laboratory; Bentoumi, G. [Canadian Nuclear Laboratories; Corcoran, E. C. [Royal Military College of Canada; Dimayuga, I. [Canadian Nuclear Laboratories; Kelly, D. G. [Royal Military College of Canada; Li, L. [Canadian Nuclear Laboratories; Sur, B. [Canadian Nuclear Laboratories; Rogge, R. B. [Canadian Nuclear Laboratories

    2015-11-17

    This paper describes a collaborative effort that saw the Royal Military College of Canada (RMC)’s delayed neutron and gamma counting apparatus transported to Canadian Nuclear Laboratories (CNL) for use in the neutron beamline at the National Research Universal (NRU) reactor. Samples containing mg quantities of fissile material were re-interrogated, and their delayed neutron emissions measured. This collaboration offers significant advantages to previous delayed neutron research at both CNL and RMC. This paper details the determination of 235U content in enriched uranium via the assay of in-beam delayed neutron magnitudes and temporal behavior. 235U mass was determined with an average absolute error of ± 2.7 %. This error is lower than that obtained at RMCC for the assay of 235U content in aqueous solutions (3.6 %) using delayed neutron counting. Delayed neutron counting has been demonstrated to be a rapid, accurate, and precise method for special nuclear material detection and identification.

  9. Calculation of resonance self-shielding for {sup 235}U from 0 to 2250 eV

    Leal, L.C.; Larson, N.M.; Derrien, H. [Oak Ridge National Lab., TN (United States); Santos, G.R. [Cidade Univ., Rio de Janeiro (Brazil). Inst. de Engenharia Nuclear

    1998-08-01

    Over the years, the evaluated {sup 235}U cross sections in the resolved energy range have been extensively revised. A major accomplishment was the first evaluation released to the ENDF/B-VI library. In that evaluation, the low energy range bound was lowered to 10{sup {minus}5} eV, and the upper limit raised to 2,250 eV. Several high-resolution measurements in conjunction with the Bayesian computer code SAMMY were used to perform the analysis of the {sup 235}U resonance parameters. SAMMY uses the Reich-Moore formalism, which is adequate for representing neutron cross sections of fissile isotopes, and a generalized least-squares (Bayes) technique for determining the energy-dependence of the neutron cross sections. Recently a re-evaluation of the {sup 235}U cross section in the resolved resonance region was completed. This evaluation has undergone integral tests in various laboratories throughout the USA and abroad. The evaluation has been accepted for inclusion in ENDF/B-VI release 5. The intent of this work is to present results of calculations of self-shielded fission rates carried out with these resonance parameters and to compare those fission rates with experimental data. Results of this comparison study provide an assessment of the resonance parameters with respect to the calculation of self-shielded group cross sections.

  10. Strong correlation of elastin deletions, detected by FISH, with Williams syndrome: Evaluation of 235 patients

    Lowery, M.C.; Brothman, L.J.; Leonard, C.O. [Univ. of Utah Health Sciences Center, Salt Lake City, UT (United States)] [and others

    1995-07-01

    Williams syndrome (WS) is generally characterized by mental deficiency, gregarious personality, dysmorphic facies, supravalvular aortic stenosis, and idiopathic infantile hypercalcemia. Patients with WS show allelic loss of elastin (ELN), exhibiting a submicroscopic deletion, at 7q11.23, detectable by FISH. Hemizygosity is likely the cause of vascular abnormalities in WS patients. A series of 235 patients was studied, and molecular cytogenetic deletions were seen in 96% of patients with classic WS. Patients included 195 solicited through the Williams Syndrome Association (WSA), plus 40 clinical cytogenetics cases referred by primary-care physicians. Photographs and medical records of most WSA subjects were reviewed, and patients were identified as {open_quotes}classic{open_quotes} (n = 114) or{open_quotes}uncertain{close_quotes} (n = 39). An additional 42 WSA patients were evaluated without clinical information. FISH was performed with biotinylated ELN cosmids on metaphase cells from immortalized lymphoblastoid lines from WSA patients and after high-resolution banding analysis on clinical referral patients. An alpha-satellite probe for chromosome 7 was included in hybridizations, as an internal control. Ninety-six percent of the patients with classic WS showed a deletion in one ELN allele; four of these did not show a deletion. Of the uncertain WS patients, only 3 of 39 showed a deletion. Of the 42 who were not classified phenotypically, because of lack of clinical information, 25 patients (60%) showed a deletion. Thirty-eight percent (15/40) of clinical cytogenetics cases showed an ELN deletion and no cytogenetic deletion by banded analysis. These results support the usefulness of FISH for the detection of elastin deletions as an initial diagnostic assay for WS. 14 refs., 2 figs., 4 tabs.

  11. PROPERTIES AND BEHAVIOR OF 238PU RELEVANT TO DECONTAMINATION OF BUILDING 235-F

    Duncan, A.; Kane, M.

    2009-11-24

    This report was prepared to document the physical, chemical and radiological properties of plutonium oxide materials that were processed in the Plutonium Fuel Form Facility (PuFF) in building 235-F at the Savannah River Plant (now known as the Savannah River Site) in the late 1970s and early 1980s. An understanding of these properties is needed to support current project planning for the safe and effective decontamination and deactivation (D&D) of PuFF. The PuFF mission was production of heat sources to power Radioisotope Thermoelectric Generators (RTGs) used in space craft. The specification for the PuO{sub 2} used to fabricate the heat sources required that the isotopic content of the plutonium be 83 {+-} 1% Pu-238 due to its high decay heat of 0.57 W/g. The high specific activity of Pu-238 (17.1 Ci/g) due to alpha decay makes this material very difficult to manage. The production process produced micron-sized particles which proved difficult to contain during operations, creating personnel contamination concerns and resulting in the expenditure of significant resources to decontaminate spaces after loss of material containment. This report examines high {sup 238}Pu-content material properties relevant to the D&D of PuFF. These relevant properties are those that contribute to the mobility of the material. Physical properties which produce or maintain small particle size work to increase particle mobility. Early workers with {sup 238}PuO{sub 2} felt that, unlike most small particles, Pu-238 oxide particles would not naturally agglomerate to form larger, less mobile particles. It was thought that the heat generated by the particles would prevent water molecules from binding to the particle surface. Particles covered with bound water tend to agglomerate more easily. However, it is now understood that the self-heating effect is not sufficient to prevent adsorption of water on particle surfaces and thus would not prevent agglomeration of particles. Operational

  12. BEZ235 (PIK3/mTOR inhibitor Overcomes Pazopanib Resistance in Patient-Derived Refractory Soft Tissue Sarcoma Cells

    Hee Kyung Kim

    2016-06-01

    Full Text Available BACKGROUND: Although pazopanib treatment has become the standard chemotherapy in salvage setting for metastatic sarcoma patients, most patients progress after pazopanib treatment in 4 to 6 months. After failure to pazopanib, patients have limited options for treatment. Therefore, subsequent therapy in patients who failed to pazopanib is urgently needed and the use of patient derived cells or patient derived tumors for accompanying testing with various pharmacological inhibitors could offer additional treatment options for these patients. METHODS: Patient derived tumor cells were collected from ascites at the time of progression to pazopanib and a 13-drug panel was tested for drug sensitivity. We confirmed the results using in vitro cell viability assay and immunoblot assay. We also performed the genomic profiling of PDX model. RESULTS: The growth of patient derived tumor cells was significantly reduced by exposure to 1.0 μM AZD2014 compared with control (control versus AZD2014, mean growth = 100.0% vs 16.04%, difference = 83.96%, 95% CI = 70.01% to 97.92%, P = .0435. Similarly, 1.0 μM BEZ235 profoundly inhibited tumor cell growth in vitro when compared to control (control versus BEZ235, mean growth = 100.0% vs 7.308%, difference = 92.69%, 95% CI = 78.87% to 106.5%, P < .0001. Despite the presence of CDK4 amplification in the patient-derived tumor cells, LEE011 did not considerably inhibit cell proliferation when compared with control (control vs LEE011, mean growth = 100.0% vs 80.23%, difference = 19.77%, 95% CI = 1.828% to 37.72%, P = .0377. The immunoblot analysis showed that BEZ235 treatment decreased pAKT, pmTOR and pERK whereas AZD2014 decreased only pmTOR. CONCLUSION: Taken together, upregulation of mTOR/AKT pathway in sarcoma patient derived cells was considerably inhibited by the treatment of AZD2014 and BEZ235 with downregulation of AKT pathway (greater extent for BEZ235. These molecules may be considered as treatment option in STS

  13. On uncertainties and fluctuations of averaged neutron cross sections in unresolved resonance energy region for 235U, 238U, 239Pu

    This paper analyses the reasons for the differences which exist between group-averaged evaluated cross-section data from different evaluated data files for U235, U238 and Pu239 in the unresolved resonance energy region. (author)

  14. Micro-image analysis in the diffusion-bonded zone of Fe3Al/Q235 carbon steel dissimilar materials

    Wang Juan; Li Yajiang; Wu Huiqiang; Ren Jiangwei

    2002-10-01

    The chemical composition of the second phase precipitation in the vacuum diffusion-bonded zone of Fe3Al intermetallic compound and Q235 carbon steel was analysed by means of electron probe microanalyser (EPMA). The relative content of the second phase precipitation and grain size was evaluated through a micro-image analyser. The percentage of Fe and Al content in the diffusion zone was measured by EPMA. The results indicated that the relative content of the second phase precipitation rich in carbon and chromium at the Fe3Al/Q235 interface was much higher. With the transition from Fe3Al intermetallic compound to Q235 carbon steel across Fe3Al/Q235 interface, the grain diameter decreased from 250 m to 112 m, Al atom content decreased from 27% to 15%, while Fe atom content increased from 76% to 96%.

  15. Determination of percentage 235U in depleted uranium by combination of gamma spectrometry and potentiometry and comparison with thermal ionisation mass spectrometry

    A gamma ray spectrometric method has been developed for the determination of percentage 235U in the depleted uranium samples. The concentration of 235U was determined by gamma spectrometry while that of total uranium by potentiometry. The values compared well with those obtained by thermal ionisation mass spectrometry. A value of 0.614± 0.006 and 0.617 ± 005 were obtained by gamma spectrometry and thermal ionisation mass spectrometry respectively for a set of ten measurements. (author)

  16. Observation of hyperfine structure on 235U levels by step-wise laser photoionization using a natural uranium pulsed hollow cathode lamp

    This paper presents the hyperfine structure and isotope shift measured between the 238U line and the center of gravity of the 235U components in a natural uranium pulsed hollow cathode lamp illuminated by a tunable pulsed dye laser pumped by copper vapour laser. With the laser tuned near the single photon transition around 5915 A, a single-frequency, multi-photon ionization signal for 235U has been observed (author)

  17. 我国某地沥青铀矿中U235相对富集的初步研究

    秦俊法; 张广元

    1982-01-01

    The discovery of the gamma spectrum abnomal is reported for the uranium ore sample No. 15, In comparison with a parallel investigation on a reference natural uranium saraple the relative abundance of U235 is obtained and the U233 content of sample No. 15 turns out to be 5 percent higher than that of the reference natural sample, Discussion is given to the mechanism by which U235 is enriched in the ore.

  18. Measurement of the 238U to 235U fission cross-section ratio for neutron energies between 0.1 and 25 MeV

    The 238U to 235U fission cross-section ratio was measured for incident neutrons from 0.1 to 25.0 MeV. A ratio shape measurement was normalized by the threshold cross-section method. A fission cross-section ratio of 0.436 +- 0.004 was found averaged over neutron energies from 2.35 to 2.95 MeV. 8 figures, 12 tables

  19. Discovery of Self-Sustained 235-U Fission Causing Sunlight by Padmanabha Rao Effect

    Rao, M. A. Padmanabha

    2013-07-01

    For the first time in solar physics, this paper reports a comprehensive study how 235Uranium fission causes Sunlight by the atomic phenomenon, Padmanabha Rao Effect against the theory of fusion. The first major breakthrough lies in identifying as many as 153 solar lines in the Bharat Radiation range from 12.87 to 31 nm reported by various researchers since 1960s. The Sunlight phenomenon is explained as follows. For example, the energy equivalence 72.48 eV of the most intense 17.107 nm emission in the middle of solar spectrum is the energy lost by β, γ, or X-ray energy of a fission product while passing through core-Coulomb space. This energy loss is the Bharat Radiation energy that cause EUV, UV, visible, and near infrared emissions on valence excitation. From vast data of emissions and energies of various fission products, 606.31 keV β (Eβmax) energy of 131I was chosen as the source of 17.107 nm emission. For the first time a typical Bharat Radiation spectrum was observed when plotted energy loss against β, γ, or X-ray energies of fission products supposedly present in solar flare and atmosphere : 113Xe, 131I, 137Cs, 95Zr, 144Cs, 134I, 140Ba, 133I, 140La, 133In etc that caused solar lines. Consistent presence of a sharp line for four months in AIA spectral EUV band at 335A exemplifies self-sustained uranium fission from a small site appeared in SDO/AIA image at 304A. Sun's dark spot is explained as a large crater formed on Sun's core surface as a result of fission reaction that does not show any emission since fission products would be thrown away from the site during fission. Purely the same Sun's core material left over at the site after fission reaction devoid of fission products and any emission seems to be the familiar dark Matter. This could be the first report on the existence of Sun's Dark Matter.

  20. Structural architecture and interplay of the nucleotide- and erythrocyte binding domain of the reticulocyte binding protein Py235 from Plasmodium yoelii.

    Grüber, Ardina; Manimekalai, Malathy S S; Preiser, Peter R; Grüber, Gerhard

    2012-11-01

    Human malaria is caused by the cyclical invasion of the host's red blood cells (RBCs) by the invasive form of the parasite, the merozoite. The invasion of the RBC involves a range of parasite ligand receptor interactions, a process which is under intensive investigation. Two protein families are known to be important in the recognition and invasion of the human erythrocyte, the erythrocyte-binding like (EBL) proteins and the reticulocyte binding like proteins, of which the Py235 family in Plasmodium yoelii is a member. Recently the nucleotide binding domain (NBD94), that plays a role in ATP sensing, and the erythrocyte binding domain (EBD) of Py235, called EBD(1-194), have been identified. Binding of ATP leads to conformational changes within Py235 from P. yoelli and results in enhanced binding of the protein to the RBC. Structural features of these domains have been obtained, providing the platform to discuss how the structural architecture creates the basis for an interplay of the sensing NBD and the EBD domain in Py235. In analogy to the receptor-mediated ligand-dimerization model of the EBL proteins PvDBP and PfEBA-175 from Plasmodium vivax and Plasmodium falciparum, respectively, we hypothesise that Py235 of P. yoelii binds via its EBD(1-194) domain to the RBC receptor, thereby inducing dimerization of the Py235-receptor complex. PMID:22878128

  1. Q235钢在海水淡化一级反渗透产水中的腐蚀行为%CORROSION BEHAVIOR OF Q235 CARBON STEEL IN SEAWATER REVERSE OSMOSIS PERMEATE

    梁沁沁; 曹顺安; 尹力; 肖丽

    2012-01-01

    The corrosion behavior of Q235 steel in seawater reverse osmosis permeate(RO) was investigated by rotation coupon method, SEM, IR and XRD, and electrochemical tests were used for studying the control step and electrode process of corrosion reaction. Experimental results showed that the corrosion rate was speeded up in first 48 h and maintained at 1.4 mm/a afterwards. Initial rust layer was formed by a thin layer of γ-FeOOH, and with time passing by, it transformed to a double-layer structure with inner thick Fe3O4 layer and outer a-FeOOH/γ-FeOOH layer. Corrosion process was controlled by cathodic reaction, resistance of which reached peak in initial stage, then reduced rapidly because of conversion of γ-FeOOH to Fe3O4, which provided no inhibition of corrosion and caused high corrosion rate of Q235 steel. As the generation and conversion of γ-FeOOH reached equilibrium on the surface of Q235 steel, corrosion resistance and corrosion rate kept steady.%采用旋转挂片和SEM,EDS及IR分析研究Q235钢在海水淡化一级反渗透产水中(RO)的腐蚀速度和腐蚀产物变化规律,并利用动电位扫描、电化学阻抗法研究腐蚀过程及腐蚀反应控制步骤。结果表明,Q235钢在海水淡化一级反渗透产水中腐蚀速度在48h内迅速增大至1.4mm/a,其后保持稳定。锈层初期为,γ—FeOOH薄层,随时间延长逐渐转为由Fe304构成的内锈层及由γ-FeOOH和Q-FeOOH构成的外锈层。腐蚀过程受阴极控制,初期腐蚀阻力达到最大,其后由于大量γ-FeOOH在酸性条件下极易转化为对腐蚀反应没有阻滞作用的Fe304,腐蚀阻力迅速减小,腐蚀速度迅速增大,当Q235钢表面γ-FeOOH生成和转化达到平衡后,腐蚀阻力保持稳定,腐蚀速度也不再发生变化。

  2. Routine Isotopic Analysis of 235U by Emission Spectrometry. 1. Interferometry using electrode-less discharge lamps 2. determination of the 235U/238U ratio using a spectrograph and electrode-less lamps

    I. A 'HYPEAC' interferometric apparatus has been used for routine determination of uranium 235. In order to facilitate the examination of non-metallic samples and to reduce the time required for analysis it has been necessary to replace the hollow-cathode light sources usually used by electrode-less discharge lamps. The preparation outside the apparatus of such lamps containing uranium tetrachloride is described; the process is simple and rapid: about ninety minutes for each, and several lamps can be built simultaneously, thus reducing still further the total time required for each analysis. The amount of sample required is about a few milligrams. In order to counteract any spontaneous optical dis-adjustment which could prevent the application of the usual isotopic abundance method, it is necessary to compare the sample spectra with those of standards, all these spectra being recorded successively and alternately. A series of examples of determinations involving over 150 measurements is presented and discussed. For samples with abundances similar to that of natural uranium and up to 5 per cent of the 235 isotope., the reproducibility is of the order of 2 per cent, the relative accuracy being ± 2 to 3 per cent; for samples enriched in uranium 235 (5 to 93 per cent) the relative accuracy can attain ± 0.5 per cent. II. In spite of the large amount of research into the improvement of the accuracy of uranium isotope analyses using optical methods, it has not been possible up to the present to develop a method as good as mass spectrometry. When it is not necessary to have a high accuracy, however, emission spectroscopy which has no memory effect can constitute a complementary method of analysis if it is sufficiently fast and economical; for this to happen it seems to us that it should be possible to apply such a method in laboratories equipped with all the usual spectrochemical analysis equipment. In the present work we have therefore set out to obtain an acceptable

  3. Investigation of neutronic behavior in a CANDU reactor with different (Am, Th, 235U)O2 fuel matrixes

    Recently thorium-based fuel matrixes are taken into consideration for nuclear waste incineration because of thorium proliferation resistance feature moreover its breeding or convertor ability in both thermal and fast reactors. In this work, neutronic influences of adding Am to (Th-235U)O2 on effective delayed neutron fraction, reactivity coefficients and burn up of a fed CANDU core has been studied using MCNPX 2.6.0 computational code. Different atom fractions of Am have been introduced in the fuel matrix to evaluate its effects on neutronic parameters of the modeled core. The computational data show that adding 2% atom fraction of Am to thorium-based fuel matrix won't noticeably change reactivity coefficients in comparison with the fuel matrix containing 1% atom fraction of Am. The use of 2% atom fraction of Am resulted in a higher delayed neutron fraction. According to the obtained data, 32.85 GWd burn up of the higher Americium-containing fuel matrix resulted in 55.2%, 26.5%, 41.9% and 2.14% depletion of 241Am, 243Am, 235U and 232Th respectively. 132.8 kg of 233U fissile element is produced after the burn up time and the nuclear core multiplication factor increases in rate of 2390 pcm. The less americium-containing fuel matrix resulted in higher depletion of 241/243Am, 235U and 232Th while the nuclear core effective multiplication factor increases in rate of 5630 pcm after the burn up time with 9.8 kg additional 233U production.

  4. Population structure of Pseudomonas aeruginosa from five Mediterranean countries: evidence for frequent recombination and epidemic occurrence of CC235.

    Makaoui Maatallah

    Full Text Available Several studies in recent years have provided evidence that Pseudomonas aeruginosa has a non-clonal population structure punctuated by highly successful epidemic clones or clonal complexes. The role of recombination in the diversification of P. aeruginosa clones has been suggested, but not yet demonstrated using multi-locus sequence typing (MLST. Isolates of P. aeruginosa from five Mediterranean countries (n = 141 were subjected to pulsed-field gel electrophoresis (PFGE, serotyping and PCR targeting the virulence genes exoS and exoU. The occurrence of multi-resistance (≥ 3 antipseudomonal drugs was analyzed with disk diffusion according to EUCAST. MLST was performed on a subset of strains (n = 110 most of them had a distinct PFGE variant. MLST data were analyzed with Bionumerics 6.0, using minimal spanning tree (MST as well as eBURST. Measurement of clonality was assessed by the standardized index of association (I(A (S. Evidence of recombination was estimated by ClonalFrame as well as SplitsTree4.0. The MST analysis connected 70 sequence types, among which ST235 was by far the most common. ST235 was very frequently associated with the O11 serotype, and frequently displayed multi-resistance and the virulence genotype exoS⁻/exoU⁺. ClonalFrame linked several groups previously identified by eBURST and MST, and provided insight to the evolutionary events occurring in the population; the recombination/mutation ratio was found to be 8.4. A Neighbor-Net analysis based on the concatenated sequences revealed a complex network, providing evidence of frequent recombination. The index of association when all the strains were considered indicated a freely recombining population. P. aeruginosa isolates from the Mediterranean countries display an epidemic population structure, particularly dominated by ST235-O11, which has earlier also been coupled to the spread of ß-lactamases in many countries.

  5. Evaluation of covariances for resolved resonance parameters of 235U, 238U, and 239Pu in JENDL-3.2

    Evaluation of covariances for resolved resonance parameters of 235U, 238U, and 239Pu was carried out. Although a large number of resolved resonances are observed for major actinides, uncertainties in averaged cross sections are more important than those in resonance parameters in reactor calculations. We developed a simple method which derives a covariance matrix for the resolved resonance parameters from uncertainties in the averaged cross sections. The method was adopted to evaluate the covariance data for some important actinides, and the results were compiled in the JENDL-3.2 covariance file. (author)

  6. Monte-Carlo simulation for fragment mass and kinetic energy distributions from neutron induced fission of 235U

    Montoya, M; Rojas, J

    2007-01-01

    The mass and kinetic energy distribution of nuclear fragments from thermal neutron induced fission of 235U have been studied using a Monte-Carlo simulation. Besides reproducing the pronounced broadening on the standard deviation of the final fragment kinetic energy distribution $\\sigma_{e}(m)$ around the mass number m = 109, our simulation also produces a second broadening around m = 125, that is in agreement with the experimental data obtained by Belhafaf et al. These results are consequence of the characteristics of the neutron emission, the variation in the primary fragment mean kinetic energy and the yield as a function of the mass.

  7. Monte-carlo simulation for fragment mass and kinetic energy distributions from neutron induced fission of 235U

    Mass and kinetic energy distribution of nuclear fragments after neutron induced fission of 235U have been studied using a Monte-Carlo simulation. Besides that the pronounced peak in the standard deviation of the kinetic energy σE(m) at the mass number around m = 110 was reproduced, a second peak was found at m = 126. These results are in good agreement with experimental data obtained by Belhafaf et. al. We have concluded that the obtained results are consequence of the characteristics of neutron evaporation for the fragments and sharp variation on primary mass yield curve. (authors)

  8. Monte-Carlo simulation for fragment mass and kinetic energy distributions from neutron-induce fission of 235U

    The mass and kinetic energy distribution of nuclear fragments after neutron-induced fission of 235U have been studied using a Monte-Carlo simulation. Besides reproducing the pronounced peak in the standard deviation of the kinetic energy σE(m) at the fragment mass number around m=109, our simulation also produces a second peak at about m=126. These results are in good agreement with experimental data obtained by Belhafaf et.al. We conclude that the obtained results are consequence of the characteristics of the fragments' neutron evaporation and of the sharp variation on the primary mass yield curve. (orig.)

  9. Electrochemical behavior of Q235 steel in saltwater saturated with carbon dioxide based on new imidazoline derivative inhibitor

    Liu, F.G. [Key Laboratory of Marine Chemistry Theory and Technology, Ministry of Education, College of Chemistry and Chemical Engineering, Ocean University of China, 238 Songling Road, Qing dao 266100 (China)], E-mail: fuguoliu@gmail.com; Du, M.; Zhang, J.; Qiu, M. [Key Laboratory of Marine Chemistry Theory and Technology, Ministry of Education, College of Chemistry and Chemical Engineering, Ocean University of China, 238 Songling Road, Qing dao 266100 (China)

    2009-01-15

    The electrochemical behavior of carbon steel in saltwater saturated with CO{sub 2} with/without an new synthesized imidazoline inhibitor was studied using polarization and electrochemical impedance spectrum (EIS), and the inhibitive ability of the inhibitor was evaluated by weight-loss method in 298-328 K temperature range. Results showed that the inhibition efficiency is up to above 80%, and imidazoline is a kind of mixed-type inhibitor. It was seen that the adsorption of imidazoline on Q235 steel can be fitted to Frumkin isotherm equation. Quantum chemistry calculation results show that the imidazoline ring and heteroatoms are the active sites of the inhibitors.

  10. Study of delayed neutron decay curves from thermal neutron induced fission of 235U and 239Pu

    The results of measurements of decay curves for delayed neutrons, obtained in the thermal neutron induced fission of 235U and 239Pu, are presented. The data were obtained by the periodical irradiation method on the IBR-2 pulsed reactor in the time interval from 5 to 730 msec after the end of irradiation. The comparison of the measured curves with the curves calculated with using several known from literature parameter sets (relative weights and half-lives of 6 or 8 exponents) was carried out. The new 7-group parameter set, which describes experimental data better, is proposed. (author)

  11. Statistical Tests for the Detection of Intermediate Structures in the Fission Cross-Sections of 235U and 239Pu

    The existence of intermediate structures in the neutron-induced fission cross sections of 235U and 239Pu was pointed out in 1957 by Egelstaff. An interpretation, recently proposed by Cao et al. and Blons et al., was based on the Strutinsky calculations of the deformation energies of the compound nucleus when shell effects are included in the liquid-drop model. The theoretical interpretation in terms of current reaction theories has been given by Weigmann and Lynn. The purpose of this paper is to develop and evaluate various statistical tests intended for the detection and interpretation of these narrow intermediate fission structures. A fission cross-section was computed in the interval 0-5 keV using randomly generated parameters with distributions chosen to mock up the 235U nucleus. The Jπ = 4- state fission width was ''modulated'' in the manner suggested by Weigmann's work. Auto-correlation and cumulative average tests were done on these mock-up cross-sections to determine if the correct average spacing of the shape isomer levels could be obtained by such tests. It is shown that the usual correlation tests tend to overestimate the spacing between structures. A proposed technique is based on the direct analysis of the averaged cross-section which affords a method of correcting for peaks of the intermediate structure below the detectability limit of the usual statistical tests. The techniques developed on the basis of the mock-up cross-sections were used to analyse the fission cross-sections of 235U and 239Pu. Average spacings of 227 and 312 eV were found for those two nuclei, respectively. These values are somewhat lower than the ones reported by Cao and Blons, which were based only on the auto-correlation analysis. The energy of the second minimum in the fission barrier was found to be 3.1 MeV for 235U and 2.9 for 239Pu. Both values are in close agreement with the values of 3 MeV predicted by Strutinsky. (author)

  12. Gain-guided broad area quantum cascade lasers emitting 23.5 W peak power at room temperature.

    Sergachev, Ilia; Maulini, Richard; Bismuto, Alfredo; Blaser, Stephane; Gresch, Tobias; Muller, Antoine

    2016-08-22

    We report gain-guided broad area quantum cascade lasers at 4.55 μm. The devices were processed in a buried heterostructure configuration with a current injector section much narrower than the active region. They demonstrate 23.5 W peak power at a temperature of 20°C and duty cycle of 1%, while their far field consists of a single symmetric lobe centered on the optical axis. These experimental results are supported well by 2D numerical simulations of electric currents and optical fields in a device cross-section. PMID:27557186

  13. Preliminary study for the transport of the fuel rods of U235 enriched to 1.8 per cent

    Transport of 1,8% U235 enriched fuel rods needs both the evaluation of the radiological risk and considerations about criticality aspects. Issues as diverse production characteristics, storage facilities in the source of origin an economical aspects have to be added to the radiological and nuclear considerations. Transport of those rods through national territory must comply with the Argentine Regulatory authority's regulations, based on the Safety Series No. 6, (ed. 1985) -as amended 1990- IAEA. Safety criteria are exposed, taking into account the amount of material to be transported, container characteristics, packaging type and expedition conditions. (author)

  14. Calculation of the end-rolling strength in Q235 strip steel by the alloying electron structure parameters

    LIU Zhilin; LIN Cheng; LIU Yan; GUO Yanchang

    2005-01-01

    Combined with the phase transformations in rolling, the phase configuration, the tensile strength, and the yield strength with different terminal rolling grain sizes in Q235 strip steel have been theoretically calculated using the covalent electron number (nA) of the strongest bond in phase cells and the interface electron density difference (Ap) in alloys. The calculated results agree well with the results of real production. Therefore, the calculation method of terminal rolling tensile and yield strength in the non-quenched-tempered steel containing pearlite is given by the alloying electron structure parameters.

  15. Uranium contents and 235U/238U atom ratios in soil and earthworms in western Kosovo after the 1999 war

    The uranium content and 235U/238U atom ratio were determined in soils and earthworms of an area of Kosovo (Djakovica garrison), heavily shelled with depleted uranium (DU) ammunition during the 1999 war. The aim of the study was to reconstruct the small-scale distribution of uranium and assess the influence of the DU added to the surface environment. The total uranium concentration and the 235U/238U ratio of topsoils showed great variability and were inversely correlated. The highest uranium levels (up to 31.47 mg kg-1) and lowest 235U/238U ratios (minimum 0.002147) were measured in topsoils collected inside, or very close to, the clusters of DU penetrator holes. Regarding the fractionation of uranium in the surface soils, the uranium concentrations in the soluble and exchangeable fractions increased as the total uranium concentration of the topsoils increased. High and rather uniform percentage contents of uranium (24-36%) were associated with the poorly crystalline iron oxide phases of soils. In the U-enriched soils the elevated levels of the element were probably due to the presence of very small, unevenly distributed oxidized DU particles. The total uranium concentration in earthworms was in the range 0.142-0.656 mg kg-1, with the highest concentrations in Lumbricus terrestris. The juveniles of all three studied species seemed to accumulate uranium more than adults, probably due to age-related differences in metabolism. The 235U/238U ratio in the earthworms was variable (0.005241-0.007266) and independent of both the total uranium contents in soils and the absolute uranium levels in the animals. Bioconcentration was greater at lower U concentrations in soil, probably due to an increasing rate of elimination of uranium by the earthworms as the soil contents of the element increase. The results of this study clearly indicate that DU was added to the soil of the study area. Nevertheless, the phenomenon was very limited spatially and the total uranium concentrations

  16. Energy dependence of mass, charge, isotopic, and energy distributions in neutron-induced fission of 235U and 239Pu

    Pasca, H.; Andreev, A. V.; Adamian, G. G.; Antonenko, N. V.; Kim, Y.

    2016-05-01

    The mass, charge, isotopic, and kinetic-energy distributions of fission fragments are studied within an improved scission-point statistical model in the reactions 235U+n and 239Pu+n at different energies of the incident neutron. The charge and mass distributions of the electromagnetic- and neutron-induced fission of 214,218Ra, 230,232,238U are also shown. The available experimental data are well reproduced and the energy-dependencies of the observable characteristics of fission are predicted for future experiments.

  17. Measurement of energy dependence of fission fragment angular anisotropy for resonance neutron induced fission of 235U aligned target

    The results of the experiment on measuring the energy dependence of fission fragment angular anisotropy in resonance neutron induced fission of 235U aligned target in energy region up to 42 eV are presented. The agreement with the data of Pattenden and Postma in resonances is good enough, while the theoretical curve, calculated using the R-matrix multilevel two fission channel approach, does not seem to describe the energy dependence of fission fragment angular anisotropy property. The necessity of taking into account the interference between levels with different spins is discussed. 11 refs., 2 figs

  18. Effect of iron content on permeability and power loss characteristics of Li0.35Cd0.3Fe2.35O4 and Li0.35Zn0.3Fe2.35O4

    Vivek Verma; Prachi Sharma; Adarsh Singh

    2014-06-01

    Substituted lithium ferrites having the chemical formula, Li0.35Cd0.3Fe2.35O4 and Li0.35Zn0.3Fe2.35O4, with different iron (metal) contents (2, 4, 6, 8 and 10) in wt% have been prepared by solid-state technique. Complex permeability and power loss of all samples have been measured by network analyser in the frequency range of 50–5000 kHz. Magnetic properties like saturation magnetization, coercivity, retentivity have been measured by vibrating sample magnetometer (VSM). The permeability of cadmium doped lithium ferrites exhibited higher values than zinc doped lithium ferrites. The power loss of cadmium doped lithium ferrites is lesser as compared to zinc doped lithium ferrites in the frequency range of 50–5000 kHz and at flux density of 10 mT. The behaviour of power loss with flux density has been found near about same for both series. Magnetic and power loss behaviour of the samples suggest that a small amount of Fe content can improve the properties of ferrite samples for microwave devices.

  19. The novel orally bioavailable inhibitor of phosphoinositol-3-kinase and mammalian target of rapamycin, NVP-BEZ235, inhibits growth and proliferation in multiple myeloma

    NVP-BEZ235 is a new inhibitor of phosphoinositol-3-kinase (PI3 kinase) and mammalian target of rapamycin (mTOR) whose efficacy in advanced solid tumours is currently being evaluated in a phase I/II clinical trial. Here we show that NVP-BEZ235 inhibits growth in common myeloma cell lines as well as primary myeloma cells at nanomolar concentrations in a time and dose dependent fashion. Further experiments revealed induction of apoptosis in three of four cell lines. Inhibition of cell growth was mainly due to inhibition of myeloma cell proliferation, as shown by the BrdU assay. Cell cycle analysis revealed induction of cell cycle arrest in the G1 phase, which was due to downregulation of cyclin D1, pRb and cdc25a. NVP-BEZ235 inhibited phosphorylation of protein kinase B (Akt), P70S6k and 4E-BP-1. Furthermore we show that the stimulatory effect of CD40-ligand (CD40L), insulin-like growth factor 1 (IGF-1), interleukin-6 (IL-6) and conditioned medium of HS-5 stromal cells on myeloma cell growth is completely abrogated by NVP-BEZ235. In addition, synergism studies revealed synergistic and additive activity of NVP-BEZ235 together with melphalan, doxorubicin and bortezomib. Taken together, inhibition of PI3 kinase/mTOR by NVP-BEZ235 is highly effective and NVP-BEZ235 represents a potential new candidate for targeted therapy in multiple myeloma

  20. Synergistic inhibition of colon cancer cell growth with nanoemulsion-loaded paclitaxel and PI3K/mTOR dual inhibitor BEZ235 through apoptosis

    Zou, Hong; Li, Li; Garcia Carcedo, Ines; Xu, Zhi Ping; Monteiro, Michael; Gu, Wenyi

    2016-01-01

    Colon cancer is the third most common cancer in the world, with drug resistance and metastasis being the major challenges to effective treatments. To overcome this, combination therapy with different chemotherapeutics is a common practice. In this study, we demonstrated that paclitaxel (PTX) together with BEZ235 exhibited a synergetic inhibition effect on colon cancer cell growth. Furthermore, nanoemulsion (NE)-loaded PTX and BEZ235 were more effective than the free drug, and a combination treatment of both NE drugs increased the efficiency of the treatments. BEZ235 pretreatment before adding PTX sensitized the cancer cells further, suggesting a synergistic inhibition effect through the phosphatidylinositol-3-kinases/protein kinase B/mammalian target of rapamycin pathway. The 50% inhibitory concentrations for BEZ235 were 127.1 nM and 145.0 nM and for PTX 9.7 nM and 9.5 nM for HCT-116 and HT-29 cells, respectively. When loaded with NE the 50% inhibitory concentrations for BEZ235 decreased to 52.6 nM and 55.6 nM and for PTX to 1.9 nM and 2.3 nM for HCT-116 and HT-29 cells, respectively. Combination treatment with 10 nM NE-BEZ235 and 0.6 nM and 1.78 nM NE-PTX could kill 50% of HCT-116 and HT-29, respectively. The cell death caused by the treatment was through apoptotic cell death, which coincided with decreased expression of anti-apoptotic protein B-cell lymphoma 2. Our data indicate that the combination therapy of PTX with the phosphatidylinositol-3-kinases/protein kinase B/mammalian target of rapamycin dual inhibitor BEZ235 using NE delivery may hold promise for a more effective approach for colon cancer treatment. PMID:27226714

  1. Uranium isotopic ratio measurements (235U/238U) by laser ablation high resolution inductively coupled plasma mass spectrometry for environmental radioactivity monitoring - 235U/238U isotope ratio analysis by LA-ICP-MS-HR for environmental radioactivity monitoring

    The protection of the aquatic and terrestrial environments from a broad range of contaminants spread by nuclear activities (nuclear plants, weapon tests or mining) require continuous monitoring of long-lives radionuclides that were released into the environment. The precise determination of uranium isotope ratios in both natural and potential contaminated samples is of primary concern for the nuclear safeguards and the control of environmental contamination. As an example, analysis of environmental samples around nuclear plants are carried out to detect the traces in the environment originating from nuclear technology activities. This study deals with the direct analysis of 235U/238U isotope ratios in real environmental solid samples performed with laser ablation (LA)-HR-ICP-MS. A similar technique has already been reported for the analysis of biological samples or uranium oxide particles [1,2] but to our knowledge, this was never applied on real environmental samples. The high sensitivity, rapid acquisition time and low detection limits are the main advantages of high resolution ICP-MS for accurate and precise isotope ratio measurements of uranium at trace and ultra-trace levels. In addition, the use of laser ablation allows the analysis of solid samples with minimal preparation. A a consequence, this technique is very attractive for conducting rapid direct 235U/238U isotope ratio analysis on a large set of various matrix samples likely to be encountered in environmental monitoring such as corals, soils, sands, sediments, terrestrial and marine bio-indicators. For the present study, LA-ICP-MS-HR analyses are performed using a New Wave UP213 nano-second Nd:YAG laser coupled to a Thermo Element-XR high resolution mass spectrometer. Powdered samples are compacted with an hydraulic press (5 tons) in order to obtain disk-shaped pellet (10-13 mm in diameter and 2 mm in thickness). The NIST612 reference glass is used for LA-ICP-MS-HR tuning and as standard control during

  2. Variation of Kinetic Energy of Fragments in Fission of 235U with 0.006 - 20ev Neutrons

    Utilizing the LNF ONYal neutron spectrometer working in the energy range between 0.006 and 20 eV, the variation in fragments' kinetic energy (EK) was studied, applying the method of relative yields (W) measurements, in the thermal neutron region and at 11 resonances of 235U. It was found that the resonances at 0.29, 2.04, 3.14, 4.84, and 7.09 eV can be sorted in a group of resonances with small values of W and EK . The resonances at 1.14, 3.60, 6.40, 8.78, 12.4, and 19.3 eV form a group with big values of W and EK. Comparison of W with radiochemical data on fragments' yield at thermal and resonance region of 235U showed that EK is larger at more asymmetrical fission. From the values W ( I ) and W(II) for the two groups of resonances, the change in the average kinetic energy of fragments 2ΔEK = 0.74 ± 0. 32 MeV was determined. (author)

  3. Mass Yields and Average Total Kinetic Energy Release in Fission for 235U, 238U, and 239Pu

    Duke, Dana

    2015-10-01

    Mass yield distributions and average total kinetic energy (TKE) in neutron induced fission of 235U, 238U, and 239Pu targets were measured with a gridded ionization chamber. Despite decades of fission research, our understanding of how fragment mass yields and TKE depend on incident neutron energy is limited, especially at higher energies (above 5-10 MeV). Improved accuracy in these quantities is important for nuclear technology as it enhances our simulation capabilities and increases the confidence in diagnostic tools. The data can also guide and validate theoretical fission models where the correlation between the fragment mass and TKE is of particular value for constraining models. The Los Alamos Neutron Science Center - Weapons Neutron Research (LANSCE - WNR) provides a neutron beam with energies from thermal to hundreds of MeV, well-suited for filling in the gaps in existing data and exploring fission behavior in the fast neutron region. The results of the studies on target nuclei 235U, 238U, and 239Pu will be presented with a focus on exploring data trends as a function of neutron energy from thermal through 30 MeV. Results indicate clear evidence of structure due to multi-chance fission in the TKE . LA-UR-15-24761.

  4. Fission Fragment Angular Distribution measurements of 235U and 238U at CERN n_TOF facility

    Leal-Cidoncha, E.; Durán, I.; Paradela, C.; Tarrío, D.; Leong, L. S.; Tassan-Got, L.; Audouin, L.; Altstadt, S.; Andrzejewski, J.; Barbagallo, M.; Bécares, V.; Bečvář, F.; Belloni, F.; Berthoumieux, E.; Billowes, J.; Boccone, V.; Bosnar, D.; Brugger, M.; Calviani, M.; Calviño, F.; Cano-Ott, D.; Carrapiço, C.; Cerutti, F.; Chiaveri, E.; Chin, M.; Colonna, N.; Cortés, G.; Cortés-Giraldo, M. A.; Diakaki, M.; Domingo-Pardo, C.; Dressler, R.; Dzysiuk, N.; Eleftheriadis, C.; Ferrari, A.; Fraval, K.; Ganesan, S.; García, A. R.; Giubrone, G.; Gómez-Hornillos, M. B.; Gonçalves, I. F.; González-Romero, E.; Griesmayer, E.; Guerrero, C.; Gunsing, F.; Gurusamy, P.; Hernández-Prieto, A.; Jenkins, D. G.; Jericha, E.; Kadi, Y.; Käppeler, F.; Karadimos, D.; Kivel, N.; Koehler, P.; Kokkoris, M.; Krtička, M.; Kroll, J.; Lampoudis, C.; Langer, C.; Lederer, C.; Leeb, H.; Lo Meo, S.; Losito, R.; Mallick, A.; Manousos, A.; Marganiec, J.; Martínez, T.; Massimi, C.; Mastinu, P. F.; Mastromarco, M.; Meaze, M.; Mendoza, E.; Mengoni, A.; Milazzo, P. M.; Mingrone, F.; Mirea, M.; Mondelaers, W.; Pavlik, A.; Perkowski, J.; Plompen, A.; Praena, J.; Quesada, J. M.; Rauscher, T.; Reifarth, R.; Riego, A.; Robles, M. S.; Roman, F.; Rubbia, C.; Sabaté-Gilarte, M.; Sarmento, R.; Saxena, A.; Schillebeeckx, P.; Schmidt, S.; Schumann, D.; Tagliente, G.; Tain, J. L.; Tsinganis, A.; Valenta, S.; Vannini, G.; Variale, V.; Vaz, P.; Ventura, A.; Versaci, R.; Vermeulen, M. J.; Vlachoudis, V.; Vlastou, R.; Wallner, A.; Ware, T.; Weigand, M.; Weiß, C.; Wright, T.; Žugec, P.

    2016-03-01

    Neutron-induced fission cross sections of 238U and 235U are used as standards in the fast neutron region up to 200 MeV. A high accuracy of the standards is relevant to experimentally determine other neutron reaction cross sections. Therefore, the detection effciency should be corrected by using the angular distribution of the fission fragments (FFAD), which are barely known above 20 MeV. In addition, the angular distribution of the fragments produced in the fission of highly excited and deformed nuclei is an important observable to investigate the nuclear fission process. In order to measure the FFAD of neutron-induced reactions, a fission detection setup based on parallel-plate avalanche counters (PPACs) has been developed and successfully used at the CERN-n_TOF facility. In this work, we present the preliminary results on the analysis of new 235U(n,f) and 238U(n,f) data in the extended energy range up to 200 MeV compared to the existing experimental data.

  5. Investigation of resonance structure and Doppler-effect of cross sections for 232 Th, 235 U and 239 Pu

    The results of measuring the neutron transmissions for 232 Th, 235 U and 239 Pu metal samples carried out at the 60 m, 123 m and 1006 m flight paths of the Dubna IBR-30 booster in the neutron energy range of 2 eV - 200 keV are given and discussed. The measurements were made at the room and liquid nitrogen temperatures. The batteries of 3 boron and 26 helium counters were used as detectors. The results of the calculations of analogous transmissions realized on the base of the evaluated data libraries BROND-2, ENDF/B-6 and JENDL-3 by means of the GRUCON computer program package are also given. It is concluded that the 235 U Doppler coefficients and effective total cross sections taken from measured transmissions are in a good agreement with calculation results based on the ENDF/B-6 library at energies of 2.15 eV - 200 keV. The BROND-2 and JENDL-3 parameters give the Doppler coefficients and effective cross sections which are 10-30% higher than the experimental and ENDF/B-6 ones at the resonance energies of 46.5 - 465 eV. For 239 Pu there is agreement of the experimental and calculational results within the experimental error limits. For 232 Th experimental values for the Doppler coefficients and effective cross sections are 10-15% higher than the calculated ones with all libraries in resonance energy region. 9 refs., 2 tabs., 1 fig

  6. Evaluation of the thermal-neutron constants for 233U, 235U, 239Pu and 241Pu

    A consistent set of best values of the 2200 meter/second neutron cross sections, Westcott g-factors, and fission neutron yields for 233U, 235U, 239Pu and 241Pu are presented. A least squares fitting program, LSF, is used to obtain the best fit and to estimate the sensitivity of these fissile parameters to the quoted uncertainties in experimental data. The half-lives of the uranium and plutonium nuclides have been evaluated and these have been used to reassess the significant experimental data. The latest revision of the spontaneous fission neutron yield anti nu, of 252Cf and the foil thickness corrections to the fission neutron yield ratios of fissile nuclei to 252Cf are included. These lead to greater consistency in the data used for anti nu (252Cf). Similarly, the 234U half-life as revised leads to improved consistency in the 235U fission cross section. Comparison is made with the values from ENDF/B-V and other evaluations

  7. Novel Method to Study Neutron Capture of U235 and U238 Simultaneously at keV Energies

    Wallner, A.; Belgya, T.; Bichler, M.; Buczak, K.; Dillmann, I.; Käppeler, F.; Lederer, C.; Mengoni, A.; Quinto, F.; Steier, P.; Szentmiklosi, L.

    2014-05-01

    The neutron capture cross sections of the main uranium isotopes, U235 and U238, were measured simultaneously for keV energies, for the first time by combining activation technique and atom counting of the reaction products using accelerator mass spectrometry. New data, with a precision of 3%-5%, were obtained from mg-sized natural uranium samples for neutron energies with an equivalent Maxwell-Boltzmann distribution of kT ˜25 keV and for a broad energy distribution peaking at 426 keV. The cross-section ratio of U235(n ,γ)/U238(n ,γ) can be deduced in accelerator mass spectrometry directly from the atom ratio of the reaction products U236/U239, independent of any fluence normalization. Our results confirm the values at the lower band of existing data. They serve as important anchor points to resolve present discrepancies in nuclear data libraries as well as for the normalization of cross-section data used in the nuclear astrophysics community for s-process studies.

  8. Comparative measurement of prompt fission γ -ray emission from fast-neutron-induced fission of 235U and 238U

    Lebois, M.; Wilson, J. N.; Halipré, P.; Oberstedt, A.; Oberstedt, S.; Marini, P.; Schmitt, C.; Rose, S. J.; Siem, S.; Fallot, M.; Porta, A.; Zakari, A.-A.

    2015-09-01

    Prompt fission γ -ray (PFG) spectra have been measured in a recent experiment with the novel directional fast-neutron source LICORNE at the ALTO facility of the IPN Orsay. These first results from the facility involve the comparative measurement of prompt γ emission in fast-neutron-induced fission of 235U and 238U . Characteristics such as γ multiplicity and total and average radiation energy are determined in terms of ratios between the two systems. Additionally, the average photon energies were determined and compared with recent data on thermal-neutron-induced fission of 235U . PFG spectra are shown to be similar within the precision of the present measurement, suggesting that the extra incident energy does not significantly impact the energy released by prompt γ rays. The origins of some small differences, depending on either the incident energy or the target mass, are discussed. This study demonstrates the potential of the present approach, combining an innovative neutron source and new-generation detectors, for fundamental and applied research on fission in the near future.

  9. A feasibility study on the production of 235mU by nuclear excitation by electronic transition

    Chodash, Perry; Norman, Eric; Swanberg, Erik; Burke, Jason; Chen, Mau; Foord, Mark

    2011-10-01

    Nuclear excitation by electronic transition (NEET) is predicted to occur in nuclei where a nuclear transition closely matches the energy and multipolarity of an electronic transition. NEET is considered to be the inverse of bound internal conversion. This rare form of excitation is predicted to occur in many nuclei. In 235U, the 1/2+ isomeric state decays to the 7/2- ground state with a transition energy of 77 eV and a half life of 26 minutes. This decay proceeds by internal conversion emitting a low energy electron. In order for NEET to occur in uranium, it must be partially ionized to create an electronic configuration that has a transition that matches the nuclear transition. Numerous experiments have been performed to search for this excitation mechanism in 235U by creating a plasma using either a laser or an electron beam. The difficulty in finding this excitation is due to the low excitation rates, 10-9 s-1 to 1 s-1, as well as the ability to detect the low energy internal conversion electrons. The results of previous experiments as well as the current experimental plan will be discussed. This work was performed under the auspices of the U.S. DOE under contract No. DE-AC52-07NA27344 and is supported in part by the NNIS Graduate Fellowship from the U.S. DOE.

  10. Fission Product Yields for 14 MeV Neutrons on 235U, 238U and 239Pu

    Mac Innes, M.; Chadwick, M. B.; Kawano, T.

    2011-12-01

    We report cumulative fission product yields (FPY) measured at Los Alamos for 14 MeV neutrons on 235U, 238U and 239Pu. The results are from historical measurements made in the 1950s-1970s, not previously available in the peer reviewed literature, although an early version of the data was reported in the Ford and Norris review. The results are compared with other measurements and with the ENDF/B-VI England and Rider evaluation. Compared to the Laurec (CEA) data and to ENDF/B-VI evaluation, good agreement is seen for 235U and 238U, but our FPYs are generally higher for 239Pu. The reason for the higher plutonium FPYs compared to earlier Los Alamos assessments reported by Ford and Norris is that we update the measured values to use modern nuclear data, and in particular the 14 MeV 239Pu fission cross section is now known to be 15-20% lower than the value assumed in the 1950s, and therefore our assessed number of fissions in the plutonium sample is correspondingly lower. Our results are in excellent agreement with absolute FPY measurements by Nethaway (1971), although Nethaway later renormalized his data down by 9% having hypothesized that he had a normalization error. The new ENDF/B-VII.1 14 MeV FPY evaluation is in good agreement with our data.

  11. Fission Product Yields for 14 MeV Neutrons on 235U, 238U and 239Pu

    We report cumulative fission product yields (FPY) measured at Los Alamos for 14 MeV neutrons on 235U, 238U and 239Pu. The results are from historical measurements made in the 1950s–1970s, not previously available in the peer reviewed literature, although an early version of the data was reported in the Ford and Norris review. The results are compared with other measurements and with the ENDF/B-VI England and Rider evaluation. Compared to the Laurec (CEA) data and to ENDF/B-VI evaluation, good agreement is seen for 235U and 238U, but our FPYs are generally higher for 239Pu. The reason for the higher plutonium FPYs compared to earlier Los Alamos assessments reported by Ford and Norris is that we update the measured values to use modern nuclear data, and in particular the 14 MeV 239Pu fission cross section is now known to be 15–20% lower than the value assumed in the 1950s, and therefore our assessed number of fissions in the plutonium sample is correspondingly lower. Our results are in excellent agreement with absolute FPY measurements by Nethaway (1971), although Nethaway later renormalized his data down by 9% having hypothesized that he had a normalization error. The new ENDF/B-VII.1 14 MeV FPY evaluation is in good agreement with our data.

  12. Study of α and triton particles emission in Uranium 235, Uranium 238, Plutonium 239 fast neutron fission

    Fast neutrons up to 2.5 MeV have been used to induce light particle accompanied fission in 235U, 238U and 239Pu targets. The energy spectra and relative intensities of 3H and 4He have been measured with a ΔE-E telescope. Absolute particle yields were derived from the number of 4He particle per 1000 binary fissions of 235U and 239Pu induced by thermal neutrons measured under the same geometrical conditions. We observe that all the energy distributions are well reproduced by gaussian lineshape, the mean energies of which remain constant while varying the neutron incident energy. (For all nuclei, the 4He mean energies lie close to 16 MeV and the corresponding energies for 3H particle at about 8-9 MeV). The production rates of 3H and 4He show a decrease of about 30% between thermal energy and En = 2 MeV with a small maximum at En = 1 MeV. Conversely the 3H and 4He particle yields obtained in fast neutron fission of 239U remain constant between En = 1.5 MeV and En = 2.5 MeV. Some possible explanation for these observations are briefly and qualitatively explored

  13. A Neutronic Analysis of TRU Recycling in PWRs Loaded with MOX-UE Fuel (MOX with U-235 Enriched U Support)

    G. Youinou; S. Bays

    2009-05-01

    This report presents the results of a study dealing with the homogeneous recycling of either Pu or Pu+Np or Pu+Np+Am or Pu+Np+Am+Cm in PWRs using MOX-UE fuel, i.e. standard MOX fuel with a U235 enriched uranium support instead of the standard tail uranium (0.25%) for standard MOX fuel. This approach allows to multirecycle Pu or TRU (Pu+MA) as long as U235 is available, by keeping the Pu or TRU content in the fuel constant and at a value ensuring a negative moderator void coefficient (i.e. the loss of the coolant brings imperatively the reactor to a subcritical state). Once this value is determined, the U235 enrichment of the MOX-UE fuel is adjusted in order to reach the target burnup (51 GWd/t in this study).

  14. Efficiency of the low energy detection system for the measurement of 235 U in lung of the Nuclear Regulatory Authority

    This work presents the results of the calibration process of the detection system of 235 U in lung of the Nuclear Regulatory Authority. The phantom used in the calibration is the denominated Lawrence Livermore Realistic Phantom, provided of lungs and active nodules and of 4 thoracic covers that its simulate muscular tissue with thickness that vary between 1.638 and 3.871 cm. The spectra are acquired by four detecting of denominated LEGe ACTII Canberra marks, each one with an active area of 3800 mm2, a diameter of 70 mm and a thickness of 20 mm, the sign is processed by a SYSTEM100 multichannel and the spectra are analyzed with the GENIE2K program. The detectors are suspended by mobile structures that allow to vary the position with regard to a horizontal stretcher that defines the measurement geometry. The whole system is located in the interior of an armored enclosure of 200 x 150 x 200 cm3 of steel of 15 cm thickness, inside recovered with layers of 0.5 cm lead and 0.05 cm cadmium. The total weight of the enclosure is 40 ton. For the described system the efficiency curves versus muscular thoracic tissue thickness (ETM) corresponding to the energy of 143.76, 163.358 and 185.72 keV of the 235 U radioisotope were obtained. Its were also practiced displacements of those detectors of approximately 1 cm with respect to the reference position and its were analyzed the corresponding changes of magnitude in the efficiencies. The obtained variations oscillate, for vertical displacements, between 5% and 7.8% for the smallest value in ETM (1.638 cm) and between 4.2% to 6.7% for the ETM 3.871 cm. While for the practiced lateral displacements, the variations go from 4% to 15%. The detection limits corresponding to each energy and thickness were determined. The results showed for the photopeak of 185.72 keV, the more outstanding in the evaluations that saying limit it oscillates between 3.7 and 6.4 Bq 235 U inside the considered thickness range. (Author)

  15. Study on uranium recovery from tungsten residue. Separation of U from Fe, Mn, Zr, Ti, Th, and Sc with mixture of N235 and TBP

    Mixture of N235 and TBP was applied for the separation of UFe/MnZrTiThSc by extracting U and Fe from hydrochloric acid medium. Then, acetic acid was utilized to scrub impurities from the loaded organic phase. The extraction was investigated at different concentrations of TBP, N235, hydrochloric acid, metal ions and extraction times. And the scrubbing of metal impurities was studied at different concentrations of acetic acid and scrubbing times. Finally, a process for uranium recovery from tungsten residue has been developed, generating with a final product U3O8 of 99.7 % purity and an overall uranium recovery of 91.8 %. (author)

  16. An energy dependent partial wave analysis of π+ p→ K+ σ+ between threshold and 2.35 GeV

    An energy dependent partial wave analysis of the reaction π+ p → K+ Σ+ has been carried out between threshold and 2.35 GeV centre of mass energy using recently published, high statistical precision data. A single solution giving a satisfactory fit to the data has been found. In the region below 2 GeV the resonant features of the solution are compared with the QCD based model of Koniuk and Isgur. Above 2 GeV the states listed in the Particle Data group tables with two or more stars are observed but none of the dubious one star states is confirmed Significant SU(3) breaking is observed in some amplitudes. (author)

  17. Seismic analysis of two 1050 mm diameter heavy water upgrading towers for 235 MWe Kaiga Atomic Power Plant Site

    This report deals with the analysis carried out for the evaluation of earthquake induced stresses and deflections in two 1050 mm diameter heavy water upgrading towers for Kaiga Atomic Power Plant Site. The analysis of upgrading tower has been carried out for two mutually perpendicular horizontal excitations and one vertical excitation applied simultaneously. The upgrading towers have been analysed using beam model taking into account soil-structure interaction. Response spectrum analysis has been carried out using site spectra for 235 MWe Kaiga reactor site. The seismic analysis has been performed for both the towers with supporting structure along with concrete pedestals and raft foundation. The towers have been checked for its stability due to compressive stresses to avoid buckling so that the nearby safety related structures are not geopardised in the event of safe shutdown earthquake (SSE) loading. (author). 14 refs., 12 figs., 18 tabs

  18. Seismic analysis of two 1050 mm diameter heavy water upgrading towers for 235 MWe Kakrapar Atomic Power Plant Site

    This report deals with the analysis carried out for the evaluation of earthquake induced stresses and deflections in two 1050 mm diameter heavy water upgrading towers for Kakrapar Atomic Power Plant Site. The analysis of upgrading tower has been carried out for two mutually perpendicular horizontal excitations and the vertical excitation. The upgrading towers have been analysed using beam model taking into account soil-structure interaction. response spectrum analysis has been carried out using site spectra for 235 MWe KAPP site. The seismic analysis has been carried out for both the towers with supporting structure along with concrete pedestals and raft foundation. The towers have been checked for their stability due to compressive stresses to avoid buckling so that the nearby safety related structures are not damaged in the event of SSE loading. (author). 13 refs., 11 figs., 14 tabs

  19. VizieR Online Data Catalog: VLA and IR observations of the S235A-B region (Felli+, 2006)

    Felli, M.; Massi, F.; Robberto, M.; Cesaroni, R.

    2007-01-01

    The observations carried out with the VLA of the National Radio Astronomy Observatory (NRAO) were made with the VLA in the C configuration on February 26 and on March 7, 2004. The single-dish Medicina radio telescope (HPBW 1.9') observations are part of a monitoring project of a large sample of water masers. Spitzer-IRAC observations of a large area around the S235A-B region in the four wavelengths (3.6, 4.5, 5.8, and 8{mu}m) were extracted from the Spitzer public archive. The observations are part of the GTO program 201 "The Role of Photodissociation Regions in High Mass Star Formation" (Principal Investigator G. Fazio). (1 data file).

  20. Effects of Neutron Emission on Fragment Mass and Kinetic Energy Distribution from Thermal Neutron-Induced Fission of 235U

    The mass and kinetic energy distribution of nuclear fragments from thermal neutron-induced fission of 235U(nth,f) have been studied using a Monte-Carlo simulation. Besides reproducing the pronounced broadening in the standard deviation of the kinetic energy at the final fragment mass number around m = 109, our simulation also produces a second broadening around m = 125. These results are in good agreement with the experimental data obtained by Belhafaf et al. and other results on yield of mass. We conclude that the obtained results are a consequence of the characteristics of the neutron emission, the sharp variation in the primary fragment kinetic energy and mass yield curves. We show that because neutron emission is hazardous to make any conclusion on primary quantities distribution of fragments from experimental results on final quantities distributions

  1. Monte Carlo simulation for fragment mass and kinetic energy distributions from the neutron-induced fission of 235U

    Montoya, M.; E. Saettone; Rojas, J.

    2007-01-01

    Mediante la simulación con el método Monte Carlo, fue estudiada la distribución de masas y energía cinética de los fragmentos de la fisión inducida por neutrones térmicos del 235U. Además de reproducir el ensanchamiento pronunciado en la desviación estándar de la distribución de la energía cinética de los fragmentos finales (¾e(m)) alrededor del número másico m = 109, nuestra simulación también produce un segundo ensanchamiento alrededor de m = 125, en concordancia con los datos expe...

  2. Contributions in the Preparation and Processing of Composite Material Type Silumin 3 - Reinforced Matrix with S235JR Steel Mesh

    Remus Belu-Nica

    2015-07-01

    Full Text Available In the paper are presented concrete data on developing technological batches of metal composite material (MCM type Silumin 3-reinforced matrix with steel mesh S235JR, with the indicating of the parameter and of the distinct stages of work. The samples from prepared batches were cut along and across by water jet abrasive process and were subjected to a destructive testing program and microstructural examination, obtaining results in concordance with the desired quality. The abrasive material used for cut was GMA granite with the average mesh of 80, the particle size ranging between 150-300 µm, density 2300 kg/m3 and melting point 1240°C.

  3. Study of Photon Strength Functions of Actinides: the case of U-235, Np-238 and Pu-241

    Guerrero, C; Cano-Ott, D; Martinez, T; Mendoza, E; Villamarin, D; Colonna, N; Meaze, M H; Marrone, S; Tagliente, G; Terlizzi, R; Belloni, F; Abbondanno, U; Fujii, K; Milazzo, P M; Moreau, C; Aerts, G; Berthoumieux, E; Dridi, W; Gunsing, F; Pancin, J; Perrot, L; Plukis, A; Alvarez, H; Duran, I; Paradela, C; Andriamonje, S; Calviani, M; Chiaveri, E; Gonzalez-Romero, E; Kadi, Y; Vicente, M C; Vlachoudis, V; Andrzejewski, J; Marganiec, J; Assimakopoulos, P; Karadimos, D; Karamanis, D; Papachristodoulou, C; Patronis, N; Audouin, L; David, S; Ferrant, L; Isaev, S; Stephan, C; Tassan-Got, L; Badurek, G; Jericha, E; Leeb, H; Oberhummer, H; Pigni, M T; Baumann, P; Kerveno, M; Lukic, S; Rudolf, G; Becvar, F; Krticka, M; Calvino, F; Capote, R; Carrillo De Albornoz, A; Marques, L; Salgado, J; Tavora, L; Vaz, P; Cennini, P; Dahlfors, M; Ferrari, A; Gramegna, F; Herrera-Martinez, A; Mastinu, P; Praena, J; Sarchiapone, L; Wendler, H; Chepel, V; Ferreira-Marques, R; Goncalves, I; Lindote, A; Lopes, I; Neves, F; Cortes, G; Poch, A; Pretel, C; Couture, A; Cox, J; O'brien, S; Wiescher, M; Dillman, I; Kappeler, F; Mosconi, M; Plag, R; Voss, F; Walter, S; Wisshak, K; Dolfini, R; Rubbia, C; Domingo-Pardo, C; Tain, J L; Eleftheriadis, C; Savvidis, I; Frais-Koelbl, H; Griesmayer, E; Furman, W; Konovalov, V; Goverdovski, A; Ketlerov, V; Haas, B; Haight, R; Reifarth, R; Heil, M; Igashira, M; Koehler, P; Kossionides, E; Lampoudis, C; Lozano, M; Quesada, J; Massimi, C; Vannini, G; Mengoni, A; Oshima, M; Papadopoulos, C; Vlastou, R; Pavlik, A; Pavlopoulos, P; Plompen, A; Rullhusen, P; Rauscher, T; Rosetti, M; Ventura, A

    2011-01-01

    The decay from excited levels in medium and heavy nuclei can be described in a statistical approach by means of Photon Strength Functions and Level Density distributions combined with the theory of the compound. The study of electromagnetic cascades following neutron capture by means of high efficiency detectors has been shown to be well suited for probing the properties of the Photon Strength Function of heavy (high level density) and/or radioactive (high background) nuclei. In this work we have investigated for the first time the validity of the recommended PSF for actinides, in particular 235U, 238Np and 241Pu. Our study includes the search for resonance structures in the PSF below Sn and draws conclusions regarding their existence and their characteristics in terms of energy, width and electromagnetic nature.

  4. Final results of the international 235U sample intercomparison and the half-life of 234U

    Finalized values were received from all laboratories which contributed samples to the 235U mass intercomparison carried out at Argonne National Laboratory. A least-squares fit was made which included the quoted masses and the absolute low-geometry and relative 2π-geometry alpha data as well as the relative fission ratios measured at ANL. Correlations between the measured values were taken into account. The values quoted by the contributing laboratories were found to be within +-0.35% of the values obtained from the LS fit. Very precise values for the isotopic composition were known for two of the sample materials which permitted a determination of the half-life of 234U. The value obtained is Tsub(1/2)=(2.457+-0.005)x105 years. Including this value in the present data base results in a current best value of Tsub(1/2)=(2.4566+-0.0044)x105 years. (author)

  5. Measurement of the fast neutron capture cross section of 238U relative to 235U(n,f)

    The capture cross section of 238U was measured using the activation technique and 235U(n,f) as a reference cross section. Capture events were measured by detection of two prominent γ-transitions in the decay of the 239U daughter nuclide, 239Np, employing a high resolution Ge(Li) detector. The system was calibrated with samples activated in a thermal neutron flux relative to the capture cross section of gold, and with an absolutely calibrated α-emitter, 243Am, which decays to 239Np. Cross section measurements were carried out in the neutron energy range from 30 keV to 3 MeV. Emphasis was on absolute values between 150 keV and 1 MeV where the 238U(n,γ) cross section and its cross section is small. Background from fission products was found to restrict the accuracy of the measured data at energies > 1.5 MeV

  6. Simultaneous measurement of fission fragments and prompt neutrons for thermal neutron-induced fission of U-235

    Nishio, Katsuhisa; Yamamoto, Hideki; Kimura, Itsuro; Nakagome, Yoshihiro [Kyoto Univ. (Japan)

    1997-03-01

    Simultaneous measurement of fission fragments and prompt neutrons following the thermal neutron induced fission of U-235 has been performed in order to obtain the neutron multiplicity (v) and its emission energy ({eta}) against the specified mass (m{sup *}) and the total kinetic energy (TKE). The obtained value of -dv/dTKE(m{sup *}) showed a saw-tooth distribution. The average neutron energy <{eta}>(m{sup *}) had a distribution with a reflection symmetry around the half mass division. The measurement also gave the level density parameters of the specified fragment, a(m{sup *}), and this parameters showed a saw-tooth trend too. The analysis by a phenomenological description of this parameters including the shell and collective effects suggested the existence of a collective motion of the fission fragments. (author)

  7. The Significance of Minimally Invasive Core Needle Biopsy and Immunohistochemistry Analysis in 235 Cases with Breast Lesions

    Yun Niu; Tieju Liu; Xuchen Cao; Xiumin Ding; Li Wei; Yuxia Gao; Jun Liu

    2009-01-01

    OBJECTIVE To evaluate core needle biopsy (CNB) as a mini-mally invasive method to examine breast lesions and discuss the clinical significance of subsequent immunohistochemistry (IHC)analysis.METHODS The clinical data and pathological results of 235 pa-tients with breast lesions, who Received CNB before surgery, were analyzed and compared. Based on the results of CNB done before surgery, 87 out of 204 patients diagnosed as invasive carcinoma were subjected to immunodetection for p53, c-erbB-2, ER and PR.The morphological change of cancer tissues in response to chemo-therapy was also evaluated.RESULTS In total of 235 cases receiving CNB examination, 204 were diagnosed as invasive carcinoma, reaching a 100% consistent rate with the surgical diagnosis. Sixty percent of the cases diag-nosed as non-invasive carcinoma by CNB was identified to have the presence of invading elements in surgical specimens, and simi-larly, 50% of the cases diagnosed as atypical ductal hyperplasia by CNB was confirmed to be carcinoma by the subsequent result of excision biopsy. There was no significant difference between the CNB biopsy and regular surgical samples in positive rate of im-munohistochemistry analysis (p53, c-erbB-2, ER and PR; P > 0.05).However, there was significant difference in the expression rate of p53 and c-erbB-2 between the cases with and without morphologi-cal change in response to chemotherapy (P < 0.05). In most cases with p53 and c-erbB-2 positive, there was no obvious morphologi-cal change after chemotherapy. CONCLUSION CNB is a cost-effective diagnostic method with minimal invasion for breast lesions, although it still has some limi-tations. Immunodetection on CNB tissue is expected to have great significance in clinical applications.

  8. V-bar in Neutron-Induced Fission of U235 and Th232, and in Photofission of U238

    The average number of prompt neutrons (v) emitted in the neutron-induced fission of U235 and Th232 and in the photofission of U238 has been measured with a large liquid scintillator as the fission neutron detector. The measurements were made relative to v for the spontaneous fission of Cf252. The v-values of U235 were measured at some different incident energies between 30 keV and 15 MeV, and the results are in agreement with measurements by Moat et al., and Hopkins and Diven. The measurements of Th232 were made for several incident neutron energies from the fission threshold at about 1.4 MeV to 15 MeV. Special interest was concentrated on the energy region near the fission threshold where the fission cross-section and the fragment angular distribution show strong variations with neutron energy. The measurements indicate that the energy dependence of b in this region may be non-linear. A measurement of v in the photofission of U238 at a gamma-ray energy of 7 MeV has been made. The result is not in agreement with measurements by Prokohorova et al. arid Lazareva et al. The spontaneous fission of Pu245 and the thermal-neutron-induced fission of Pu239 give a difference in v corresponding to 0.10 n/MeV. The result of the present investigation combined with the D-value for the spontaneous fission of U238 gives 0.10 ± 0.02 in agreement with the data obtained for the compound nucleus of Pu240. (author)

  9. Reactive transport of uranium in a groundwater bioreduction study: Insights from high-temporal resolution 238U/235U data

    Shiel, A. E.; Johnson, T. M.; Lundstrom, C. C.; Laubach, P. G.; Long, P. E.; Williams, K. H.

    2016-08-01

    We conducted a detailed investigation of U isotopes in conjunction with a broad geochemical investigation during field-scale biostimulation and desorption experiments. This investigation was carried out in the uranium-contaminated alluvial aquifer of the Rifle field research site. In this well-characterized setting, a more comprehensive understanding of U isotope geochemistry is possible. Our results indicate that U isotope fractionation is consistently observed across multiple experiments at the Rifle site. Microbially-mediated reduction is suggested to account for most or all of the observed fractionation as abiotic reduction has been demonstrated to impart much smaller, often near-zero, isotopic fractionation or isotopic fractionation in the opposite direction. Data from some time intervals are consistent with a simple model for transport and U(VI) reduction, where the fractionation factor (ε = +0.65‰ to +0.85‰) is consistent with experimental studies. However, during other time intervals the observed patterns in our data indicate the importance of other processes in governing U concentrations and 238U/235U ratios. For instance, we demonstrate that departures from Rayleigh behavior in groundwater systems arise from the presence of adsorbed species. We also show that isotope data are sensitive to the onset of oxidation after biostimulation ends, even in the case where reduction continues to remove contaminant uranium downstream. Our study and the described conceptual model support the use of 238U/235U ratios as a tool for evaluating the efficacy of biostimulation and potentially other remedial strategies employed at Rifle and other uranium-contaminated sites.

  10. Research on Prompt Neutron Multiplicity Distribution for the Neutron-Induced Fission of 235U at 14 MeV Neutrons

    2008-01-01

    <正>The prompt neutron multiplicity distribution ν(A) for the n+ 235U fission system at 14 MeV was studied using the distribution mode of the excitation energy and the averaged γ-ray energy in the two

  11. Nuclear data and measurements series: Ratio of the prompt-fission-neutron spectrum of plutonium 239 to that of uranium 235

    The prompt-fission-neutron spectrum resulting from 239Pu fission induced by 0.55 MeV incident neutrons is measured from 1.0 to 10.0 MeV relative to that of 235U fission induced by the same incident-energy neutrons. The measurements employ the time-of-flight technique. Energy-dependent ratios of the two spectra are deduced from the measured values over the energy range 1.0 to 10.0 MeV. The experimentally-derived ratio results are compared with those calculated from ENDF/B-V, revision-2, and with results of recent microscopic measurements. Using the ENDF/B-V 235U Watt parameters for the 235U spectrum, the experimental measurements imply a ratio of average fission-spectrum energies of 239Pu/235U = 1.045 +- 0.003, compared to the value 1.046 calculated from ENDF/B-V, revision 2. 12 refs., 2 figs., 2 tabs

  12. Towards A Modern Calibration Of The 238U/235U Paleoredox Proxy: Apparent Uranium Isotope Fractionation Factor During U(VI)-U(IV) Reduction In The Black Sea

    Rolison, J. M.; Stirling, C. H.; Middag, R.; Rijkenberg, M. J. A.; De Baar, H. J. W.

    2015-12-01

    The isotopic compositions of redox-sensitive metals, including uranium (U), in marine sediments have recently emerged as powerful diagnostic tracers of the redox state of the ancient ocean-atmosphere system. Interpretation of sedimentary isotopic information requires a thorough understating of the environmental controls on isotopic fractionation in modern anoxic environments before being applied to the paleo-record. In this study, the relationship between ocean anoxia and the isotopic fractionation of U was investigated in the water column and sediments of the Black Sea. The Black Sea is the world's largest anoxic basin and significant removal of U from the water column and high U accumulation rates in modern underlying sediments have been documented. Removal of U from the water column occurs during the redox transition of soluble U(VI) to relatively insoluble U(IV). The primary results of this study are two-fold. First, significant 238U/235U fractionation was observed in the water column of the Black Sea, suggesting the reduction of U induces 238U/235U fractionation with the preferential removal of 238U from the aqueous phase. Second, the 238U/235U of underlying sediments is related to the water column through the isotope fractionation factor of the reduction reaction but is influenced by mass transport processes. These results provide important constraints on the use of 238U/235U as a proxy of the redox state of ancient oceans.

  13. SAS2H input for computing core activities of 4.5, 5.0, and 5.5 weight % 235U fuel for Sequoyah Nuclear Plant

    Sequoyah Nuclear Plant core activities at initial fuel enrichments of 4.5, 5.0, and 5.5 wt% 235U, required in nuclear safety evaluations, were computed by the SAS2H analysis sequence and the ORIGEN-S code within the SCALE-4.2 code system

  14. Fission Cross Sections of {209}Bi, {232}Th, {235}U, {238}U and {237}Np for Intermediate Energy Protons and Deuterons

    Yurevich, V I; Yakovlev, R M; Sosnin, A N

    2001-01-01

    Fission cross sections of {209}Bi, {232}Th, {235}U, {238}U and {237}Np have been measured with 1.0-3.7 GeV protons and 1.0 GeV deuterons. The results are compared with other experimental data, available evaluations and predictions of the theoretical model.

  15. Synergistic inhibition of colon cancer cell growth with nanoemulsion-loaded paclitaxel and PI3K/mTOR dual inhibitor BEZ235 through apoptosis

    Zou H

    2016-05-01

    Full Text Available Hong Zou,1,2 Li Li,1 Ines Garcia Carcedo,1 Zhi Ping Xu,1 Michael Monteiro,1 Wenyi Gu1 1Australian Institute for Bioengineering and Nanotechnology, The University of Queensland, St Lucia, Brisbane, QLD, Australia; 2Department of Pathology, Key Laboratory for Xinjiang Endemic and Ethnic Diseases, Shihezi University School of Medicine, Shihezhi University, Xinjiang, People’s Republic of China Abstract: Colon cancer is the third most common cancer in the world, with drug resistance and metastasis being the major challenges to effective treatments. To overcome this, combination therapy with different chemotherapeutics is a common practice. In this study, we demonstrated that paclitaxel (PTX together with BEZ235 exhibited a synergetic inhibition effect on colon cancer cell growth. Furthermore, nanoemulsion (NE-loaded PTX and BEZ235 were more effective than the free drug, and a combination treatment of both NE drugs increased the efficiency of the treatments. BEZ235 pretreatment before adding PTX sensitized the cancer cells further, suggesting a synergistic inhibition effect through the phosphatidylinositol-3-kinases/protein kinase B/mammalian target of rapamycin pathway. The 50% inhibitory concentrations for BEZ235 were 127.1 nM and 145.0 nM and for PTX 9.7 nM and 9.5 nM for HCT-116 and HT-29 cells, respectively. When loaded with NE the 50% inhibitory concentrations for BEZ235 decreased to 52.6 nM and 55.6 nM and for PTX to 1.9 nM and 2.3 nM for HCT-116 and HT-29 cells, respectively. Combination treatment with 10 nM NE-BEZ235 and 0.6 nM and 1.78 nM NE-PTX could kill 50% of HCT-116 and HT-29, respectively. The cell death caused by the treatment was through apoptotic cell death, which coincided with decreased expression of anti-apoptotic protein B-cell lymphoma 2. Our data indicate that the combination therapy of PTX with the phosphatidylinositol-3-kinases/protein kinase B/mammalian target of rapamycin dual inhibitor BEZ235 using NE

  16. Q235钢基体表面微晶玻璃功能梯度涂层的残余应力分析%Residual stress analysis in functionally gradient glass-ceramic coatings on Q235 steel

    周黎明; 龚伟; 王恩泽; 韩腾

    2014-01-01

    运用ANSYS有限元软件对Q235钢/微晶玻璃梯度涂层复合材料在制备过程中产生的残余应力进行了数值模拟。建立了该复合材料的有限元分析模型,探讨了不同层数、层厚对该复合材料体系残余应力分布的影响。结果表明:在基体与梯度涂层的界面边缘处存在较大的应力集中;随着层数或层厚的增加,涂层表面最大径向残余压应力增大;梯度层数和涂层厚度对界面处的残余应力都有明显影响。此模拟分析结果可以为该梯度涂层复合材料的设计和制备提供理论依据和参考。%The residual stress of Q 235 steel/glass-ceramic gradient coatings was simulated with the commercial software ANSYS .The finite element analysis model of the composite was established and the distributions of residual stress in the composite system had been investigated based on various the layer numbers and the coating thickness .The results show that there is a remarkable stress concentration near the edge of the interface between substrate and coating .The maximum radial stress on the coating surface increase with the layer number or the coating thickness increasing .The layer numbers and the thickness of gradient coatings have a significant effect on the residual stress at the interface between substrate and coating .The simulation results can be used to provide theoretical guidance for the design and preparation of the composite.

  17. 用N235从富铁高酸度硫酸浸出液中萃取除铁%Removal of Fe3+ from iron rich and high acidity sulfuric acid leaching liquid by extraction of N235

    张魁芳; 刘志强; 曹洪杨; 邱显扬

    2015-01-01

    The extraction of Fe 3+ by N235 was studied based on the technology gap on the removal of Fe3+ from iron rich and high acidity sulfuric acid leaching liquid by extraction. The effects of H2O2 dosage, feed initial pH, extractant concentration, extractant composition and extraction time on the extraction, and the effects of H2SO4 concentration and tripping time on the stripping were investigated. The cross current extraction process was designed and the isotherms of stripping were plotted, and the conditions of extractant transformation were researched. The results show that, when 30% (mass fraction) H2O2 dosage is 3.85 times of theoretical one, Fe2+ can be oxidized into Fe3+ totally, and with 30% (volume fraction) N235 and10% (volume fraction) TBP in sulphonated kerosene as extractant, the extraction rate of Fe3+ from the solution with initial pH of 0.11reaches 96.67% in four-stage cross current extraction with O/A ratio of 1:1 (volume ratio of oil phase to aqueous phase) at 25℃ for 2 min, and the loss rate of Cu2+, Co2+, Ni2+ are 3.04%, 1.39%, 3.84%, respectively. The Fe3+ in loaded organic can be stripped into Fe2(SO4)3 with purity of 98.87% using 0.3 mol/L H2SO4 solution and the stripping rate reaches 99.12% in two-stage counter current stripping with O/A ratio of 1:1 (volume ratio of oil phase to aqueous phase) at 25℃ for 6 min. After stripping, the acid in loaded organic phase can be neutralized using Na2CO3. The organic phase returns to extraction circularly.%对N235萃取除铁进行研究,考察H 2 O 2用量、料液初始pH、萃取剂浓度、萃取剂组成、萃取时间对萃取的影响以及H2SO4浓度、反萃时间对反萃的影响,设计错流萃取过程并绘制反萃平衡等温线,对萃取剂转型条件进行研究。结果表明:H 2 O 2用量为理论量3.85倍时可将Fe2+完全氧化成Fe3+,并采用有机相组成30%(体积分数)N235+10%(体积分数)TBP+磺化煤油作为萃取剂,料液初始pH为0.11,其最佳萃

  18. Study of U235 neutron fission spectrum by the knowledge of cross sections average over that spectrum

    A literature search of cross sections averaged over the fission neutron spectrum confirms inconsistencies between calculated and experimental values for high threshold reactions. Since, in this case, calculated averaged cross sections are systematically lower than measured values, it is concluded that the representations used to carry out these calculations underestimate the number of neutrons in the high energy region of the spectrum. A careful measurement of the averaged cross section for the 45Sc(n,2n) 44gSc and 45Sc(n,2n) 44mSc high threshold reactions had been performed in the RA-6 Neutron Activation Analysis Laboratory after carefully checking that the neutron flux at the core position where the samples were being irradiated was indeed an undisturbed fission spectrum. The experimental values are greater than those calculated with either, Watt type representations or the one based on the Madland and Nix model for the prompt fission spectrum. In many areas of nuclear engineering, like validation of nuclear data, reactor calculations, applied nuclear physics, shielding design, etc., it is of great practical importance to have a representation for the neutron flux that can be expressed in a closed analytical form and that agrees with experimental results, specially for the most widely fissile nuclide, 235U. The results of the calculations mentioned above lead us to propose an analytical form for the 235U fission neutron spectrum that better agrees with experimental results in the whole energy spectrum. We propose two different forms; both are a modification of the Watt-type form that has been adopted within the ENDF/B-V files. One of the new analytical representations is defined in two regions: below 9.5 MeV it is exactly the same formula as that used within the ENDF/B-V files, above this energy the parameters of this formula are changed. The other proposed analytical representation is expressed by a single formula in the whole energy range. These two new

  19. Measurement of fission yields far from the center of isotopic distributions in the thermal neutron fission of 235U

    The main purpose of this work was to measure independent yields, in the thermal neutron fission of 235U, of fission products which lie far from the centers of the isotopic and isobaric yield distributions. These measurements were used to test the predictions of semi-empirical systematics of fission yields and theoretical fission models. Delay times were measured as a function of temperature in the range 1200-2000degC. The very low delay times achieved in the present work permitted expanding the measurable region to the isotopes 147,148Cs and 99Rb which are of special interest in the present work. The delay times of Sr and Ba isotopes achieved were more than two orders of magnitude lower than values reported in the literature and thus short-lived isotopes of these elements could be separated for the first time by mass spectrometry. The half-lives of 147Ba, 148Ba, 149La and 149Ce were measured for the first time. The isotopic distributions of fission yields were measured for the elements Rb, Sr, Cs and Ba in the thermal neutron fission of 235U, those of 99Rb, 147Cs and 148Cs having been measured for the first time. A comparison of the experimental yields with the predictions of the currently accepted semi-empirical systematics of fission yields, which is the odd-even effect systematics, shows that the systematics succeeds in accounting for the strong odd-even proton effect and the weaker odd-even neutron effect and also in predicting the shape of the distributions in the central region. It is shown that prompt neutron emission broadens the distribution only slightly in the wing of heavy isotopes and more significantly in the wing of light isotopes. But the effect of prompt neutron emission cannot explain the large discrepancies existing between the predictions of fission models and the experimentally measured fission yield in the wings of the isotopic distributions. (B.G.)

  20. The adsorption and inhibition effect of calcium lignosulfonate on Q235 carbon steel in simulated concrete pore solution

    Wang, Yishan; Zuo, Yu; Zhao, Xuhui; Zha, Shanshan

    2016-08-01

    The corrosion inhibition of calcium lignosulfonate (CLS) for Q235 carbon steel in saturated Ca(OH)2 + 0.1 mol/L NaCl solution was studied by means of weight loss, polarization, fluorescence microscopy (FM), scanning electron microscopy/energy dispersive spectrometry (SEM/EDS), microscopic infrared spectral imaging (M-IR) and X-ray photoelectron spectroscopy (XPS). For the steel in simulated concrete pore solution (pH 12.6), an increase of Eb value and a decrease of icorr value occurred with different concentrations of CLS. The optimal content of CLS was 0.001 mol/L at which the inhibition rate was 98.86% and the Eb value increased to 719 mV after 10 h of immersion. In mortar solution and in reinforced concrete environment, CLS also showed good inhibition for steel. The preferential adsorption of CLS around pits was detected by M-IR. The result illustrates that at the early stage the adsorption of CLS was heterogeneous and CLS may have a competitive adsorption with chloride ions at the active sites, which would be beneficial for decreasing the susceptibility of pitting corrosion. After the pre-filming time, an intact adsorption CLS film formed on carbon steel surface. The adsorption between CLS and calcium presented as Casbnd Osbnd S bonds. The adsorption of CLS on carbon steel surface occurred probably by both physisorption and chemisorption.

  1. Determination of Nuclear Charge Distributions of Fission Fragments from ^{235} U (n_th , f) with Calorimetric Low Temperature Detectors

    Grabitz, P.; Andrianov, V.; Bishop, S.; Blanc, A.; Dubey, S.; Echler, A.; Egelhof, P.; Faust, H.; Gönnenwein, F.; Gomez-Guzman, J. M.; Köster, U.; Kraft-Bermuth, S.; Mutterer, M.; Scholz, P.; Stolte, S.

    2016-03-01

    Calorimetric low temperature detectors (CLTD's) for heavy-ion detection have been combined with the LOHENGRIN recoil separator at the ILL Grenoble for the determination of nuclear charge distributions of fission fragments produced by thermal neutron-induced fission of ^{235} U. The LOHENGRIN spectrometer separates fission fragments according to their mass-to-ionic-charge ratio and their kinetic energy, but has no selectivity with respect to nuclear charges Z. For the separation of the nuclear charges, one can exploit the nuclear charge-dependent energy loss of the fragments passing through an energy degrader foil (absorber method). This separation requires detector systems with high energy resolution and negligible pulse height defect, as well as degrader foils which are optimized with respect to thickness, homogeneity, and energy loss straggling. In the present, contribution results of test measurements at the Maier Leibnitz tandem accelerator facility in Munich with ^{109} Ag and ^{127} I beams with the aim to determine the most suitable degrader material, as well as measurements at the Institut Laue-Langevin will be presented. These include a systematic study of the quality of Z-separation of fission fragments in the mass range 82≤ A ≤ 132 and a systematic measurement of ^{92} Rb fission yields, as well as investigations of fission yields toward the symmetry region.

  2. Determination of Nuclear Charge Distributions of Fission Fragments from ^{235}U (n_th, f) with Calorimetric Low Temperature Detectors

    Grabitz, P.; Andrianov, V.; Bishop, S.; Blanc, A.; Dubey, S.; Echler, A.; Egelhof, P.; Faust, H.; Gönnenwein, F.; Gomez-Guzman, J. M.; Köster, U.; Kraft-Bermuth, S.; Mutterer, M.; Scholz, P.; Stolte, S.

    2016-08-01

    Calorimetric low temperature detectors (CLTD's) for heavy-ion detection have been combined with the LOHENGRIN recoil separator at the ILL Grenoble for the determination of nuclear charge distributions of fission fragments produced by thermal neutron-induced fission of ^{235}U. The LOHENGRIN spectrometer separates fission fragments according to their mass-to-ionic-charge ratio and their kinetic energy, but has no selectivity with respect to nuclear charges Z. For the separation of the nuclear charges, one can exploit the nuclear charge-dependent energy loss of the fragments passing through an energy degrader foil (absorber method). This separation requires detector systems with high energy resolution and negligible pulse height defect, as well as degrader foils which are optimized with respect to thickness, homogeneity, and energy loss straggling. In the present, contribution results of test measurements at the Maier Leibnitz tandem accelerator facility in Munich with ^{109}Ag and ^{127}I beams with the aim to determine the most suitable degrader material, as well as measurements at the Institut Laue-Langevin will be presented. These include a systematic study of the quality of Z-separation of fission fragments in the mass range 82le A le 132 and a systematic measurement of ^{92}Rb fission yields, as well as investigations of fission yields toward the symmetry region.

  3. Neutron yield and induced radioactivity: a study of 235-MeV proton and 3-GeV electron accelerators

    This study evaluated the magnitude of potential neutron yield and induced radioactivity of two new accelerators in Taiwan: a 235-MeV proton cyclotron for radiation therapy and a 3-GeV electron synchrotron serving as the injector for the Taiwan Photon Source. From a nuclear interaction point of view, neutron production from targets bombarded with high-energy particles is intrinsically related to the resulting target activation. Two multi-particle interaction and transport codes, FLUKA and MCNPX, were used in this study. To ensure prediction quality, much effort was devoted to the associated benchmark calculations. Comparisons of the accelerators' results for three target materials (copper, stainless steel and tissue) are presented. Although the proton-induced neutron yields were higher than those induced by electrons, the maximal neutron production rates of both accelerators were comparable according to their respective beam outputs during typical operation. Activation products in the targets of the two accelerators were unexpectedly similar because the primary reaction channels for proton- and electron-induced activation are (p,pn) and (γ,n), respectively. The resulting residual activities and remnant dose rates as a function of time were examined and discussed. (authors)

  4. Energies and Yields of Prompt Gamma Rays from Fragments in Slow-Neutron Induced Fission of 235U

    Measurements were made on the gamma radiation emitted from fission fragments in slow-neutron induced fission of 235U. The fragments were detected with solid state detectors of the surface barrier type and the gamma radiation with a Nal(Tl) scintillator. Mass selection was used so that the gamma radiation could be measured as a function of fragment mass. Time discrimination between the fission gammas and the prompt neutrons released in the fission process was employed to reduce the background. The gamma radiation emitted during different time intervals after the fission event was studied with the help of a collimator, the position of which was changed along the path of the fission fragments. In this way it was possible to select various collimator settings and let gamma radiation of different half-lives be enhanced. Gamma-ray energy spectra from these time components were then recorded as function of mass. The spectrum shape differed greatly depending on the half-life of the radiation and the fragment from which it was emitted. The results of the present measurements were discussed in the light of existing fission models, and comparisons were made with prompt gamma-ray and neutron data from other fission experiments

  5. Neutronics and thermalhydraulics characteristics of the CANDU core fueled with slightly enriched uranium 0.9% U235

    The interest concerning the slightly enriched uranium (SEU) fuel cycle is due to the possibility to adapt (to convert) the current reactor design using natural uranium fuel to this cycle. Preliminary evaluations based on discharged fuel burnup estimates versus enrichment and on Canadian experience in fuel irradiation suggest that for a 0.93% U-235 enrichment no design modifications are required, not even for the fuel bundle. The purpose of this paper is to resume the results of the studies carried on in order to clarify this problem. The calculation methodology used in reactor physics and thermal-hydraulics analyses that were performed adapted and developed the AECL suggested methodology. In order to prove the possibility to use the SEU 0.93% without any design modification, all the main elements from the CANDU Reactor Physics Design Manual were studied. Also, some thermal-hydraulics analyses were performed to ensure that the operating and safety parameters were respected. The estimations sustain the assumption that the current reactor and fuel bundle design is compatible to the using of the SEU 0.93% fuel. (author)

  6. Numerical simulation of stress distribution in Al2 O3-TiC/Q235 diffusion bonded joints

    2008-01-01

    The distributions of the axial stress and shear stress in Al2O3-TiC/Q235 diffusion bonded joints were studied using finite element method (FEM). The effect of interlayer thickness on the axial stress and shear stress was also investigated. The results indicate that the gradients of the axial stress and shear stress are great near the joint edge. The maximal shear stress produces at the interface of the Al2O3-TiC and Ti interlayer. With the increase of Cu interlayer thickness, the magnitudes of the axial stress and shear stress first decrease and then increase. The distribution of the axial stress changes greatly with a little change in the shear stress. The shear fracture initiates at the interface of the Al2O3-TiC/ Ti interlayer with high shear stress and then propagates to the Al2O3-TiC side, which is consistent with the stress FEM calculating results.

  7. Variation of the Binary-to-Ternary Fission Ratio for U235 in the Thermal-Neutron-Energy Region

    The slow chopper installed at BRI was used to make an accurate determination of the binary-to-ternary fission ratio for U235 in the neutron-energy range from 0.005 eV to 0.2 eV. Large gold-silicon suríace-barrier detectors are used for the consecutive measurement of long-range α-particles (absorber in) and fission fragments (absorber out). The time analysis is done with a 100-channel time-of-flight analyser. A one-metre flight-path and a rotor speed of 50 rev/s is used. The B/T ratio was also measured with a high statistical accuracy (about 1%) in intense beams with well-defined neutron spectra, i.e. a ''cold neutron'' beam, a beam extracted from a thermal column and a beam of 0.3-eV neutrons produced by crystal diffraction. The B/T ratio exhibits a small and smooth variation in the energy range considered. This effect seems to be correlated with measurements of some other fission parameters in the same neutron-energy range. (author)

  8. Computer aided structure prediction of 0H18N9 and S235JR steels laser welded joints

    J. Górka

    2007-03-01

    Full Text Available Purpose: of these researches was to investigate possibilities of joining materials with different chemical composition and properties. CAW software to prediction of joints structure was used.Design/methodology/approach: the quality of single- and double sided joints was assessed by metallographic examinations, hardness tests, tensile and bending tests.Findings: a computer aided structure prediction was tested by metallographic examinations and hardness tests. Because of possibility of use these type of joints in medical equipment production tensile and bending tests and also corrosion resistance tests were preformed.Research limitations/implications: for complete information about tested different chemical composition and properties materials joints it is needed to check others materials in place of S235JR carbon steel.Practical implications: result of this paper is a information that is possible to join materials with different chemical composition and properties materials with different chemical composition and properties. It is also possible to precise predict structure of weld using computer software.Originality/value: the researches were provided for welding materials used in medical equipment producing. Welded joints were tested for a corrosion resistance in typical disinfectants used in medical conditions. At the beginning computer prediction was used.

  9. On monitoring anthropogenic airborne uranium concentrations and (235)U/(238)U isotopic ratio by Lichen - bio-indicator technique.

    Golubev, A V; Golubeva, V N; Krylov, N G; Kuznetsova, V F; Mavrin, S V; Aleinikov, A Yu; Hoppes, W G; Surano, K A

    2005-01-01

    Lichens are widely used to assess the atmospheric pollution by heavy metals and radionuclides. However, few studies are available in publications on using lichens to qualitatively assess the atmospheric pollution levels. The paper presents research results applying epiphytic lichens as bio-monitors of quantitative atmospheric contamination with uranium. The observations were conducted during 2.5 years in the natural environment. Two experimental sites were used: one in the vicinity of a uranium contamination source, the other one - at a sufficient distance away to represent the background conditions. Air and lichens were sampled at both sites monthly. Epiphytic lichens Hypogimnia physodes were used as bio-indicators. Lichen samples were taken from various trees at about 1.5m from the ground. Air was sampled with filters at sampling stations. The uranium content in lichen and air samples as well as isotopic mass ratios (235)U/(238)U were measured by mass-spectrometer technique after uranium pre-extraction. Measured content of uranium were 1.45 mgkg(-1) in lichen at 2.09 E-04 microgm(-3) in air and 0.106 mgkg(-1) in lichen at 1.13 E-05 microgm(-3) in air. The relationship of the uranium content in atmosphere and that in lichens was determined, C(AIR)=exp(1.1 x C(LICHEN)-12). The possibility of separate identification of natural and man-made uranium in lichens was demonstrated in principle. PMID:16083999

  10. Star formation black hole growth and dusty tori in the most luminous AGNs at z=2-3.5

    Netzer, Hagai; Nordon, Raanan; Trakhtenbrot, Benny; Lira, Paulina; Shemmer, Ohad

    2015-01-01

    We report herschel observations of 100 very luminous, optically selected AGNs at z=2-3.5 with log(LUV)(erg/sec)> 46.5, where LUV=L1350A. The distribution in LUV is similar to the general distribution of SDSS AGNs in this redshift and luminosity interval. We measured SF luminosity, LSF, and SFR in 34 detected sources by fitting combined SF and WISE-based torus templates. We also obtained statistically significant stacks for the undetected sources in two luminosity groups. The sample properties are compared with those of very luminous AGNs at z>4.5. The main findings are: 1) The mean and the median SFRs of the detected sources are 1176 and 1010 Msun/yr, respectively. The mean SFR of the undetected sources is 148 Msun/yr. The ratio of SFR to BH accretion rate is approximately 80 for the detected sources and less than 10 for the undetected sources. There is no difference in LAGN and only a very small difference in L(torus) between detected and undetected sources. 2) The redshift distribution of LSF and LAGN for t...

  11. Influence of fission modes on prompt neutron characteristics in the neutron-induced fission of 235U

    The de-excitation of the fission fragments formed in the neutron-induced fission of 235U, for incident energies from 0.5 to 6.0 MeV, is simulated numerically. Neutrons are emitted sequentially from a Weisskopf spectrum with a temperature set by previous neutron emissions. The complete decay chain is followed until a fission product is formed and no further neutron emission is allowed energetically. Detailed results are obtained, such as the average prompt neutron multiplicity as a function of the fragment mass and the total kinetic energy ν(A,TKE) and the multiplicity distribution P(ν). An interpretation in terms of fission modes is proposed. It appears that numerical modeling tools have to be sharpened. The results presented here are very promising and should be improved. The proper Hauser-Feshbach treatment (as opposed to Weisskopf-Ewing) of the evaporation process of the excited fission fragments has to be implemented, in particular to correctly account for the competition between neutron and gamma emission near the neutron binding energy

  12. Analysis of heat affected zone obtained by CO2 laser cutting of low carbon steel (S235)

    Zaied, M.; Miraoui, I.; Boujelbene, M.; Bayraktar, E.

    2013-12-01

    Laser cutting is associated with thermal effects at the cutting surface resulting in alteration of microstructure and mechanical properties. An abrupt change on the cutting surface is caused by a structural modified zone called heat affected zone (HAZ) due to weld heat treatment introduced by a high thermal gradient in the substrate material. Heat affected zone is often associated with undesirable effects such as surface cracking, fatigue resistance, etc. Therefore, it is important to minimize the thickness of this zone (HAZ). The objective of this work is to study the effect of high-power CO2 laser cutting on the heat affected zone. The laser cutting of low carbon steel (S235) is investigated with the aim of evaluating the effect of the input laser cutting parameters: laser power and cutting speed, on heat affected zone. An overall optimization was applied to find out the optimal cutting parameters that would minimize the thickness of heat affected zone. It was found that laser cutting parameters have an effect on the heat affected zone. The HAZ can be minimized by increasing the laser cutting speed and decreasing the laser power.

  13. Contribution to the study of the interaction of slow neutrons with 235U using the time-of-flight method

    This study concerns the properties of the excited levels of uranium 236 obtained by interaction of slow neutron with uranium 235. The experiments have been carried out at the Saclay linear electron accelerator by use of the time of flight method. In the first part of this paper, we examine the technical and physical conditions which rule the experiments: compromise between resolution and counting rate, time dispersion due to the slowing down of the neutrons and crystalline binding effects. In a second part the experimental results i.e. total, fission and ternary fission cross sections are given. The third part deals with the analysis of these results: the resonance parameters determination (Τn, Τγ, Τf), the study of their statistical distribution and of their correlations. We tried some classifications of the resonances according to their parameters and compared these classifications to each other and to other results. At least the evidence of a cross section correlation with a range smaller than 100 eV seems to be confirmed. (author)

  14. Homogeneous water nucleation and droplet growth in methane and carbon dioxide mixtures at 235 K and 10 bar.

    Holten, V; van Dongen, M E H

    2010-05-28

    Homogeneous nucleation rates and droplet growth rates of water in pure methane and mixtures of methane and carbon dioxide were measured in an expansion wave tube at 235 K and 10 bar. The nucleation rate in pure methane is three orders of magnitude higher than literature nucleation rates of water in low-pressure helium or argon. Addition of carbon dioxide to the carrier gas mixture increases the rates even more. Specifically, rates in a mixture of methane and 3% carbon dioxide are a factor of 10 higher than the rates in pure methane. With 25% carbon dioxide, the rates are four orders of magnitude higher than the rates in pure methane. An application of the nucleation theorem shows that the critical cluster consists of 22 water molecules and 5 methane molecules, for nucleation in pure methane. Growth rates of water droplets were measured in methane and in methane-carbon dioxide mixtures at 243 K and 11.5 bar. At equal temperature, pressure and water vapor fraction, the growth rate of the squared droplet radius is about 20% lower in the mixture with 25% carbon dioxide than in pure methane. The lower growth rate is caused by a smaller diffusion coefficient of water in the mixture with carbon dioxide; the difference of the diffusion coefficients is qualitatively reproduced by the empirical Fuller correlation combined with Blanc's law. PMID:20515097

  15. Design of a high-flux epithermal neutron beam using 235U fission plates at the Brookhaven Medical Research Reactor.

    Liu, H B; Brugger, R M; Rorer, D C; Tichler, P R; Hu, J P

    1994-10-01

    Beams of epithermal neutrons are being used in the development of boron neutron capture therapy for cancer. This report describes a design study in which 235U fission plates and moderators are used to produce an epithermal neutron beam with higher intensity and better quality than the beam currently in use at the Brookhaven Medical Research Reactor (BMRR). Monte Carlo calculations are used to predict the neutron and gamma fluxes and absorbed doses produced by the proposed design. Neutron flux measurements at the present epithermal treatment facility (ETF) were made to verify and compare with the computed results where feasible. The calculations indicate that an epithermal neutron beam produced by a fission-plate converter could have an epithermal neutron intensity of 1.2 x 10(10) n/cm2.s and a fast neutron dose per epithermal neutron of 2.8 x 10(-11) cGy.cm2/nepi plus being forward directed. This beam would be built into the beam shutter of the ETF at the BMRR. The feasibility of remodeling the facility is discussed. PMID:7869995

  16. Effect of U-238 and U-235 cross sections on nuclear characteristics of fast and thermal reactors

    Akie, Hiroshi; Takano, Hideki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Kaneko, Kunio

    1997-03-01

    Benchmark calculation has been made for fast and thermal reactors by using ENDF/B-VI release 2(ENDF/B-VI.2) and JENDL-3.2 nuclear data. Effective multiplication factors (k{sub eff}s) calculated for fast reactors calculated with ENDF/B-VI.2 becomes about 1% larger than the results with JENDL-3.2. The difference in k{sub eff} is caused mainly from the difference in inelastic scattering cross section of U-238. In all thermal benchmark cores, ENDF/B-VI.2 gives smaller multiplication factors than JENDL-3.2. In U-235 cores, the difference is about 0.3%dk and it becomes about 0.6% in TCA U cores. The difference in U-238 data is also important in thermal reactors, while there are found 0.1-0.3% different v values of U isotopes in thermal energy between ENDF/B-VI.2 and JENDL-3.2. (author)

  17. Fission-product energy release for times following thermal-neutron fission of 235U between 2 and 14000 seconds

    Fission-product decay energy-releases rates were measured for thermal-neutron fission of 235U. Samples of mass 1 to 10 μg were irradiated for 1 to 100 sec by use of the fast pneumatic-tube facility at the Oak Ridge Research Reactor. The resulting beta- and gamma-ray emissions were counted for times-after-fission between 2 and 14,000 seconds. The data were obtained for beta and gamma rays separately as spectral distributions, N(E/sub γ/) vs E/sub γ/ and N(E/sub beta/) vs E/sub β/. For the gamma-ray data the spectra were obtained by using a NaI detector, while for the beta-ray data the spectra were obtained by using an NE-110 detector with an anticoincidence mantle. The raw data were unfolded to provide spectral distributions of modest resolution. These were integrated over E/sub γ/ and E/sub β/ to provide total yield and energy integrals as a function of time after fission. Results are low compared to the present 1973 ANS Decay-heat standard. A complete description of the experimental apparatus and data-reduction techniques is presented. The final integral data are given in tabular and graphical form and are compared with published data. 41 figures, 13 tables

  18. Measurement of the fast neutron capture cross section of /sup 238/U relative to /sup 235/U(n,f)

    Fawcett, L.R. Jr.; Poenitz, W.P.; Smith, D.L.

    1979-01-01

    The capture cross section of /sup 238/U was measured using the activation technique and /sup 235/U(n,f) as a reference cross section. Capture events were measured by detection of two prominent ..gamma..-transitions in the decay of the /sup 239/U daughter nuclide, /sup 239/Np, employing a high resolution Ge(Li) detector. The system was calibrated with samples activated in a thermal neutron flux relative to the capture cross section of gold, and with an absolutely calibrated ..cap alpha..-emitter, /sup 243/Am, which decays to /sup 239/Np. Cross section measurements were carried out in the neutron energy range from 30 keV to 3 MeV. Emphasis was on absolute values between 150 keV and 1 MeV where the /sup 238/U(n,..gamma..) cross section and its cross section is small. Background from fission products was found to restrict the accuracy of the measured data at energies > 1.5 MeV.

  19. NVP-BEZ235 overcomes gefitinib-acquired resistance by down-regulating PI3K/AKT/ mTOR phosphorylation

    Sun ZH

    2015-01-01

    Full Text Available Zhihua Sun,2,* Qiuhui li,1,* Sheng Zhang,1 Jing Chen,1 Lili Huang,3 Jinghua Ren,1 Yu Chang,1 Yichen Liang,1 Gang Wu1 1Cancer Center, Union Hospital, Tongji Medical College, Huazhong University of Science and Technology, Wuhan, Hubei, People’s Republic of China; 2Oncology department, Xiangyang central Hospital, Xiangyang, Hubei, People’s Republic of China; 3Radiation Oncology Department, Fifth Affiliated Hospital of Sun Yat-sen University, Zhuhai, Guangdong, People's Republic of China *These authors contributed equally to this work Background: Patients harboring activating mutations in epidermal growth factor receptors (EGFR are particularly sensitive to EGFR tyrosine kinase inhibitors (TKIs. However, most patients develop an acquired resistance after a period of about 10 months. This study focuses on the therapeutic effect of NVP-BEZ235, a dual inhibitor of phosphatidylinositol- 3-kinase/mammalian target of rapamycin (PI3K/mTOR, in gefitinib-resistant non-small cell lung cancer. Methods: H1975 cell line was validated as a gefitinib-resistant cell model by the nucleotide-sequence analysis. We used the 3-(4,5-Dimethylthiazol-2-yl-2,5-diphenyltetrazolium bromide (MTT assay to detect the growth of H1975 cell line in vitro. H1975 cells' migration was detected by the migration assay. Xenograft models were used to investigate the growth of gefitinib-resistant non-small cell lung cancer in vivo. Western blot and immunohistochemical analysis were used to investigate the level of PI3K/protein kinase B(AKT/mTOR signaling pathway proteins. Results: We show that NVP-BEZ235 effectively inhibited the growth of H1975 cells in vivo as well as in vitro. Similarly, H1975 cell migration was reduced by NVP-BEZ235. Further experiments revealed that NVP-BEZ235 attenuated the phosphorylation of PI3K/AKT/mTOR signaling pathway proteins. Conclusion: Taken together, we suggest that NVP-BEZ235 inhibits gefitinib-resistant tumor growth by downregulating PI3K

  20. The analysis of the clinical diagnosis of 235 cases of AIDS patients with pulmonary infection%235例艾滋病患者合并肺部感染的临床诊治分析

    路钧; 段炬萍

    2012-01-01

    目的 探讨艾滋病合并肺部感染的临床表现特征及诊断.方法 对某院自2005年9月~2012年2月诊断的235例艾滋病合并肺部感染患者的临床表现及胸部X线片进行统计学分析处理.结果 艾滋病患者易发生多种病原菌感染,血培养阳性78例,其中青霉菌阳性48例,金葡萄球菌18例,草绿色链球菌6例,缓慢葡萄球菌3例,人葡萄球菌2例,大肠埃希氏杆菌1例;痰培养中128例阳性,其中白色念珠菌47例,热带念珠菌16例,金葡萄球菌54例,草绿色链球菌7例,人葡萄球菌5例,肺炎链球菌9例,其他10例,经药物治疗后病原菌阳性率明显降低.结论 肺部感染是艾滋病最为常见的感染,通过X胸片的检查及临床表现,对通过药物治疗及预后有重要的参考价值.因此,了解艾滋病合并肺部感染的临床特点及影像特征,对艾滋病患者的早期诊断、有效治疗有重要的意义.%OBJECTIVE To explore the clinical features and diagnosis of cases with AIDS and pulmonary infection. METHODS The clinical manifestations and chest X-ray films of 235 cases of AIDS complicated by lung infection in our hospital from September 2005 to February 2012 were statistically analyzed. RESULTS HIV patients were prone to cause a variety of pathogen infection, with positive blood culture in 78 cases, including positive penicillium in 48 cases, 18 cases of staphylococcus au-reus, six cases of streptococcus viridans, three cases of slow aureus, two cases of people staphylococci, one case of colon angstrom hope spp. In the sputum culture, 128 cases were positive, including 47 cases of Candida albicans, 16 cases of Candida tropicalis, 54 cases of staphylococcus aureus, seven cases of streptococcus viridans, five cases of human staphylococcus, 9 cases of streptococcus pneumoniae, and others were in 10 cases, the pathogen—positive rate was significantly lower after drug treatment. CONCLUSION Lung infection is the most common HIV infection. The

  1. Coulomb effects in isobaric cold fission from reactions 233U(nth,f), 235U(nth,f), 239Pu(nth,f) and 252Cf(sf)

    Montoya, Modesto

    2014-01-01

    The Coulomb effect hypothesis, formerly used to interpret fluctuations in the curve of maximal total kinetic energy as a function of light fragment mass in reactions 233U(nth,f), 235U(nth,f) and 239Pu(nth,f), is confirmed in high kinetic energy as well as in low excitation energy windows, respectively. Data from reactions 233U(nth,f), 235U(nth,f), 239Pu(nth,f) and 252Cf(sf) show that, between two isobaric fragmentations with similar Q-values, the more asymmetric charge split reaches the higher value of total kinetic energy. Moreover, in isobaric charge splits with different Q-values, similar preference for asymmetrical fragmentations is observed in low excitation energy windows.

  2. Measurement of Neutron Induced Fission of 235U, 233U and 245Cm with the FIC Detector at the CERN n()TOF Facility

    A series of measurements of neutron induced fission cross section of various TRU isotopes have been performed at the CERN n()TOF spallation neutron facility, in the energy range from thermal to nearly 250 MeV. The experimental apparatus consists in a fast ionization chamber (FIC), used as a fission fragment detector with a high efficiency. Good discrimination between alphas and fission fragments can be obtained with a simple amplitude threshold. In order to allow the monitoring of the neutron beam and to extract the n()TOF neutron flux, the well known cross section of the 235U(n,f) reaction, considered as a fission standard, has been used. Preliminary results for the cross section are shown for some selected isotopes such as 235U, 233U and 245Cm in the energy range from 0.050 eV to about 2 MeV.

  3. Try235Phe homozygous mutation of the steroid 5-a reductase type 2 (SRD5A2) gene in a Turkish patient.

    Parlak, Mesut; Durmaz, Erdem; Gursoy, Semin; Bircan, Iffet; Akcurin, Sema

    2014-01-01

    Steroid 5-a reductase type 2 isoenzyme (SRD5A2) deficiency is a male-limited autosomal recessive disorder that results in decreased conversion of testosterone to dihydrotestosterone with various de.gree of incomplete virilization in affected 46, XY infants. No clear genotype-phenotype relationship has been reported till date; moreover, the same mutation can result in considerable heterogeneity in clinical manifestations. Of 6 documented cases with Try235Phe homozygous mutation of the SRD5A2 gene, 3 patients had predominantly female external genitalia whereas the other 3 had predominantly male phenotype. We report Try235Phe homozygous mutation of the SRD5A2 gene in a Turkish patient who was initially assigned as a girl because of the predominantly female appearance of the external genitalia. PMID:25266188

  4. Studies of the opportunity to convert the 'ARGUS-90' research reactor with 90% fuel enrichment in U-235 to low-enriched fuel (∼20%)

    Aiming to assess the consequences of abandoning the employment of highly enriched nuclear fuel (HEU) in the reactor engineering, the opportunity has been studied to convert the 'Argus-90' reactor operating with the uranyl sulphate water solution fuel of 90% enrichment in uranium-235 to low-enriched fuel (LEU) of ∼20% enrichment. A unified technology for the preparation of a solution fuel of 20% and 90% enrichment in U-235 has been confirmed. The effect of low-enriched fuel on the core neutronics parameters has been studied as well as on the efficiency of operating controls of the reactor control and protection system and radiolytic parameters of the solution fuel. (author)

  5. Comparison of the ENDF/B-V and SOKRATOR evaluations of 235U, 239Pu, 240Pu and 241Pu at low neutron energies

    The US and USSR's most recent evaluationsof 235U, 239Pu, 240Pu and 241Pu are compared over the thermal region and over the first few resonances. The two evaluations rest on essentially the same experimental data base and the differences reflect different approaches to the representation of the cross sections or different weightings of the experimental results. It is found that over the thermal and resolved ranges the two evaluations are very similar. Some differences in approaches are briefly discussed

  6. Investigation of the prompt neutron emission mechanism in low energy fission of 235,233U(nth, f) and 252Cf(sf)

    Val’ski G.V.; Gagarski A.M.; Shcherbakov O.A.; Vorobyev A.S.; Petrov G.A.

    2010-01-01

    A series of experiments has been performed to measure prompt neutron angular and energy distributions from thermal neutron-induced fission of 235,233U in correlation with the fission fragments. These distributions have been analyzed with the assumption of neutron isotropic emission from accelerated fission fragments. The performed analysis demonstrates that all obtained results can be described within 5% accuracy using this assumption. This discrepancy is approximately constant and doesn’t de...

  7. Uranium 238U/235U isotope ratios as indicators of reduction: Results from an in situ biostimulation experiment at Rifle, Colorado, USA

    Bopp IV, C.J.; Lundstrom, C.C.; Johnson, T.M.; Sanford, R.A.; Long, P.E.; Williams, K.H.

    2010-02-01

    The attenuation of groundwater contamination via chemical reaction is traditionally evaluated by monitoring contaminant concentration through time. However, this method can be confounded by common transport processes (e.g. dilution, sorption). Isotopic techniques bypass the limits of concentration methods, and so may provide improved accuracy in determining the extent of reaction. We apply measurements of {sup 238}U/{sup 235}U to a U bioremediation field experiment at the Rifle Integrated Field Research Challenge Site in Rifle, Colorado (USA). An array of monitoring and injection wells was installed on a 100 m{sup 2} plot where U(VI) contamination was present in the groundwater. Acetate-amended groundwater was injected along an up-gradient gallery to encourage the growth of dissimilatory metal reducing bacteria (e.g. Geobacter species). During amendment, U concentration dropped by an order of magnitude in the experiment plot. We measured {sup 238}U/{sup 235}U in samples from one monitoring well by MC-ICP-MS using a double isotope tracer method. A significant {approx}1.00{per_thousand} decrease in {sup 238}U/{sup 235}U occurred in the groundwater as U(VI) concentration decreased. The relationship between {sup 238}U/{sup 235}U and concentration corresponds approximately to a Rayleigh distillation curve with an effective fractionation factor ({alpha}) of 1.00046. We attribute the observed U isotope fractionation to a nuclear field shift effect during enzymatic reduction of U(VI){sub (aq)} to U(IV){sub (s)}.

  8. Monte Carlo analysis of direct measurements of the fission neutron yield per absorption by 233U and 235U of monochromatic neutrons

    Monte Carlo analysis of the measurements of Smith et al. of the number of fission neutrons produced per neutron absorbed, eta, for 2200 m/sec neutrons absorbed by 233U and 235U yields: eta2200233 = 2.2993 +- 0.0082 and eta2200235 = 2.0777 +- 0.0064. The standard deviations include Monte Carlo, cross section, and experimental uncertainties. The Monte Carlo analysis was confirmed by calculating measured quantities used by the experimentalists in determining eta2200

  9. Power spectral density measurements with 252Cf for unreflected 17.77-cm-dia uranium (93.2 wt % 235U) metal cylinders

    The method of reactivity determination using noise analysis correlation measurements with 252Cf was used to determine the reactivity for subcritical 17.77-cm-dia uranium (93.2 wt percent 235U) metal cylinders with reactivities as low as 25 dollars. Far subcritical tests were performed with right circular cylinders of uranium metal for which the subcritical reactivity was known from other inverse kinetics and prompt neutron decay constant measurements

  10. Comunicato stampa N°235 della IARC "LA IARC AFFERMA CHE ANCHE L'ESPOSIZIONE A BASSE DOSI DI RADIAZIONI AUMENTA IL RISCHIO DI MORIRE DI LEUCEMIA TRA I LAVORATORI DEL SETTORE NUCLEARE" pubblicato il 22 Giugno 2015

    Fellone, Lucio

    2015-01-01

    Versione autorizzata in italiano del Comunicato Stampa della IARC N°235 pubblicato il 22 giugno 2015: "LA IARC AFFERMA CHE ANCHE L'ESPOSIZIONE A BASSE DOSI DI RADIAZIONI AUMENTA IL RISCHIO DI MORIRE DI LEUCEMIA TRA I LAVORATORI DEL SETTORE NUCLEARE". Documento originale all'indirizzo: http://www.iarc.fr/en/media-centre/pr/2015/pdfs/pr235_E.pdf Authorized Italian version of the IARC Press Release N°235 published on 22 June 2015: EVEN LOW DOSES OF RADIATION INCREASE RI...

  11. Development of a recovery method of 131I in the 99Mo process through the fission of 235U

    131I is an iodine radioisotope widely used in nuclear medicine that can be used either for diagnostic or for treatment due to its physical decay by β- and its high emission of y-rays. It is produced at IPEN using the indirect reaction: 130Te(n,y)131mTe → 131Te → 131I where TeO2 targets are irradiated in a Nuclear Reactor. There is also the possibility of producing 131I by the fission of 235U, where about 300 different elements are produced together with 131I. The 131I produced through this method presents high specific activity and radioactive concentration suitable for the labeling of molecules. The aim of this work was to develop a recovery method of 131I with the required quality to be used in Nuclear Medicine in the 99Mo production process through the route of acid dissolution of metallic 235U targets. 131I can appear in two phases of the process, both in the gaseous phase produced during the dissolution of metallic U targets and in the dissolution solution. This work studied the recovery of 131I in these two phases. Several materials were used for the capture and recovery of 131I at the two phases of the process, the gaseous one and the solution of dissolution of U targets. Columns of alumina with Cu, acid alumina with Cu, Ag microspheres, Cu microspheres, Ag nanospheres, anionic cartridges, Ag cartridges, anion exchange resin and activated charcoal columns were tested. Solutions containing 131I in 0.1 mol.L-1 NaOH were percolated through the materials and the eluted solutions were analyzed in a dose calibrator. The precipitation of AgI was also studied wth further dissolution of this precipitate with 0.1 mol L-1 NH4OH and 5% Na2S2O3. The recovery results varied according to the material, activated charcoal showed recovery yields between 42% and 83% but the recovery yield of the alumina column with Cu ranged from 20% to 85%. Tests with Ag nanospheres showed recovery yield of 26% using 0.1 mol L-1NaOH and 72% for Na2S2O3. Tests with anionic cartridges

  12. Star Formation Black Hole Growth and Dusty Tori in the Most Luminous AGNs at z=2-3.5

    Netzer, Hagai; Lani, Caterina; Nordon, Raanan; Trakhtenbrot, Benny; Lira, Paulina; Shemmer, Ohad

    2016-03-01

    We report Herschel/SPIRE observations of 100 very luminous, optically selected active galactic nuclei (AGNs) at z=2{--}3.5 with {log} {L}{{1350}} (erg s-1) ≥ 46.5 , where {L}{{1350}} is λLλ at 1350 Å. The distribution in {L}{{1350}} is similar to the general distribution of Sloan Digital Sky Survey AGNs in this redshift and luminosity interval. We measured star-formation (SF) luminosity, {L}{{SF}}, and SF rate (SFR) in 34 detected sources by fitting combined SF and torus templates, where the torus emission is based on Wide Field Infrared Survey Explorer observations. We also obtained statistically significant stacks for the undetected sources in two luminosity groups. The sample properties are compared with those of very luminous AGNs at z\\gt 4.5. The main findings are: (1) The mean and the median SFRs of the detected sources are {1176}-339+476 and {1010}-503+706 M⊙ yr-1, respectively. The mean SFR of the undetected sources is 148 M⊙ yr-1. The ratio of SFR to the black hole accretion rate is ≈80 for the detected sources and less than 10 for the undetected sources. Unlike a sample of sources at z ≃ 4.8 that we studied recently, there is no difference in {L}{{AGN}} and only a very small difference in {L}{{torus}} between the detected and undetected sources. (2) The redshift distribution of {L}{{SF}} and {L}{{AGN}} for the most luminous, redshift 2-7 AGNs are different. Similar to previous studies, the highest {L}{{AGN}} are found at z ≈ 3. However, the {L}{{SF}} of such sources peaks at z ≈ 5. Assuming the objects in our sample are hosted by the most massive galaxies at those redshifts, we find that approximately 2/3 of the hosts are already below the main sequence of SF galaxies at z = 2-3.5. (3) The spectral energy distributions (SEDs) of dusty tori at high redshift are similar to the shapes found in low redshift, low luminosity AGNs. Herschel upper limits put strong constraints on the long wavelength shape of the SED, ruling out several earlier

  13. Measurement of neutron induced fission of {sup 235}U, {sup 233}U and {sup 245}Cm with the FIC detector at the CERN n-TOF facility

    Calviani, M.; Karadimos, D.; Abbondanno, U.; Aerts, G.; Alvarez, H.; Alvarez-Velarde, F.; Andriamonje, S.; Andrzejewski, J.; Assimakopoulos, P.; Audouin, L.; Badurek, G.; Baumann, P.; Becvar, F.; Berthoumieux, E.; Calvino, F.; Cano-Ott, D.; Capote, R.; Carrapic, C.; Cennini, P.; Chepel, V.; Chiaveri, E.; Colonna, N.; Cortes, G.; Couture, A.; Cox, J.; Dahlfors, M.; David, S.; Dillmann, I.; Domingo-Pardo, C.; Dridi, W.; Duran, I.; Eleftheriadis, C.; Embid-Segura, M.; Ferrant, L.; Ferrari, A.; Ferreira-Marques, R.; Fujii, K.; Furman, W.; Goncalves, I.; Gonzalez-Romero, E.; Gramegna, F.; Guerrero, C.; Gunsing, F.; Haas, B.; Haight, R.; Heil, M.; Herrera-Martinez, A.; Igashira, M.; Jericha, E.; Kappeler, F.; Kadi, Y.; Karamanis, D.; Kerveno, M.; Koehler, P.; Kossionides, E.; Krticka, M.; Lampoudis, C.; Leeb, H.; Lindote, A.; Lopes, I.; Lozano, M.; Lukic, S.; Marganiec, J.; Marrone, S.; Martinez, T.; Massimi, C.; Mastinu, P.; Mengoni, A.; Milazzo, P.M.; Moreau, C.; Mosconi, M.; Neves, F.; Oberhummer, H.; O' Brien, S.; Pancin, J.; Papachristodoulou, C.; Papadopoulos, C.; Paradela, C.; Patronis, N.; Pavlik, A.; Pavlopoulos, P.; Perrot, L.; Pigni, M.T.; Plag, R.; Plompen, A.; Plukis, A.; Poch, A.; Praena, J.; Pretel, C.; Quesada, J.; Rauscher, T.; Reifarth, R.; Rubbia, C.; Rudolf, G.; Rullhusen, P.; Salgado, J.; Santos, C.; Sarchiapone, L.; Savvidis, I.; Stephan, C.; Tagliente, G.; Tain, J.L.; Tassan-Got, L.; Tavora, L.; Terlizzi, R.; Vannini, G.; Vaz, P.; Ventura, A.; Villamarin, D.; Vincente, M.C.; Vlachoudis, V.; Vlastou, R.; Voss, F.; Walter, S.; Wiescher, M.; Wisshak, K

    2008-07-01

    A series of measurements of neutron induced fission cross section of various transuranic isotopes have been performed at the CERN n-TOF spallation neutron facility, in the energy range from thermal to nearly 250 MeV. The experimental apparatus consists in a fast ionization chamber (FIC), used as a fission fragment detector with a high efficiency. Good discrimination between alphas and fission fragments can be obtained with a simple amplitude threshold. In order to allow the monitoring of the neutron beam and to extract the n-TOF neutron flux, the well known cross section of the {sup 235}U(n,f) reaction, considered as a fission standard, has been used. Preliminary results for the cross section are shown for some selected isotopes such as {sup 235}U, {sup 233}U and {sup 245}Cm in the energy range from 0.050 eV to about 2 MeV. These results for {sup 235}U, {sup 233}U and {sup 245}Cm show results consistent with databases in the resonance region, with no normalization required for {sup 233}U. In the case of {sup 245}Cm, for the energy range between thermal and 20 eV, we obtained the first experimental data ever published, while showing a good agreement with previous data in the region above that value.

  14. Measurement of neutron induced fission of 235U, 233U and 245Cm with the FIC detector at the CERN n-TOF facility

    A series of measurements of neutron induced fission cross section of various transuranic isotopes have been performed at the CERN n-TOF spallation neutron facility, in the energy range from thermal to nearly 250 MeV. The experimental apparatus consists in a fast ionization chamber (FIC), used as a fission fragment detector with a high efficiency. Good discrimination between alphas and fission fragments can be obtained with a simple amplitude threshold. In order to allow the monitoring of the neutron beam and to extract the n-TOF neutron flux, the well known cross section of the 235U(n,f) reaction, considered as a fission standard, has been used. Preliminary results for the cross section are shown for some selected isotopes such as 235U, 233U and 245Cm in the energy range from 0.050 eV to about 2 MeV. These results for 235U, 233U and 245Cm show results consistent with databases in the resonance region, with no normalization required for 233U. In the case of 245Cm, for the energy range between thermal and 20 eV, we obtained the first experimental data ever published, while showing a good agreement with previous data in the region above that value.

  15. High accuracy measurement of the $^{235}$U(n,f) reaction cross-section in the 10-30 keV neutron energy range

    The analysis of the neutron flux of n_TOF (in EAR1) revealed an anomaly in the 10-30 keV neutron energy range. While the flux extracted on the basis of the $^{6}$Li(n,t)$^{4}$He and $^{10}$B(n,$\\alpha$)$^{7}$Li reactions mostly agreed with each other and with the results of FLUKA simulations of the neutron beam, the one based on the $^{235}$U(n,f) reaction was found to be systematically lower, independently of the detection system used. A possible explanation is that the $^{235}$U(n,f) crosssection in that energy region, where in principle should be known with an uncertainty of 1%, may be systematically overestimated. Such a finding, which has a negligible influence on thermal reactors, would be important for future fast critical or subcritical reactors. Furthermore, its interest is more general, since the $^{235}$U(n,f) reaction is often used at that energy to determine the neutron flux, or as reference in measurements of fission cross section of other actinides. We propose to perform a high-accuracy, high-r...

  16. C235-V3 cyclotron for a proton therapy center to be installed in the hospital complex of radiation medicine (Dimitrovgrad)

    Galkin, R. V.; Gurskii, S. V.; Jongen, Y.; Karamysheva, G. A.; Kazarinov, M. Yu.; Korovkin, S. A.; Kostromin, S. A.; Calderan, J.-M.; Cahay, P.; Mokrenko, S. P.; Morozov, N. A.; Nkongolo, H.; Ol'shevskii, A. G.; Paradis, Y.; Petrov, D. S.; Romanov, V. M.; Samsonov, E. V.; Syresin, E. M.; Shakun, A. N.; Shakun, N. G.; Shirkov, G. D.; Shirkov, S. G.

    2014-06-01

    Proton therapy is an effective method of treating oncologic diseases. In Russia, construction of several centers for proton and ion therapy is slated for the years to come. A proton therapy center in Dimitrovgrad will be the first. The Joint Institute for Nuclear Research (Russia) in collaboration with Ion Beam Application (IBA) (Belgium) has designed an C235-V3 medical proton cyclotron for this center. It outperforms previous versions of commercial IBA cyclotrons, which have already been installed in 11 oncologic hospital centers in different countries. Experimental and calculation data for the beam dynamics in the C235-V3 medical cyclotron are presented. Reasons for beam losses during acceleration are considered, the influence of the magnetic field radial component in the midplane of the accelerator and main resonances is studied, and a beam extraction system is designed. In 2011-2012 in Dubna, the cyclotron was mounted, its magnetic field was properly configured, acceleration conditions were optimized, and beam extraction tests were carried out after which it was supplied to Dimitrovgrad. In the C235-V3 cyclotron, an acceleration efficiency of 72% and an extraction efficiency of 62% have been achieved without diaphragming to form a vertical profile of the beam.

  17. Uncertainty analysis on reactivity and discharged inventory for a pressurized water reactor fuel assembly due to 235,238U nuclear data uncertainties

    This paper discusses the uncertainty analysis on reactivity and inventory for a typical PWR fuel element as a result of uncertainties in 235,238U nuclear data. A typical Westinghouse 3-loop fuel assembly fuelled with UO2 fuel with 4.8% enrichment has been selected. The Total Monte-Carlo method has been applied using the deterministic transport code DRAGON. This code allows the generation of the few-groups nuclear data libraries by directly using data contained in the nuclear data evaluation files. The nuclear data used in this study is from the JEFF3.1 evaluation, and the nuclear data files for 238U and 235U (randomized for the generation of the various DRAGON libraries) are taken from the nuclear data library TENDL. The total uncertainty (obtained by randomizing all 238U and 235U nuclear data in the ENDF files) on the reactor parameters has been split into different components (different nuclear reaction channels). Results show that the TMC method in combination with a deterministic transport code constitutes a powerful tool for performing uncertainty and sensitivity analysis of reactor physics parameters. (authors)

  18. Relative intensities of 2.5 and 14-MeV source neutrons from comparative responses of U-235 and U-238 detectors

    The response of polyethylene-moderated U-235 fission counters is only weakly dependent on incident neutron energy, while the response of unmoderated U-238 or Th-232 fission counters increases strongly with energy. A given concentration of D-T neutrons in a mixed DT-DD source results in a unique relative detector response that depends on the parameters R14 and R2.5, where R14 is the ratio of the unmoderated U-238 and moderated U-235 detector efficiencies for a pure 14-MeV neutron source, and R2.5 is the corresponding ratio for a pure 2.5 MeV source. We have determined R14 and R2.5 using D-D and D-T neutron generators inside the TFTR vacuum vessel. The results indicate that, for our detector geometry, the ratio of U-238 to U-235 count rates should increase by a factor of about 3 when the fusion neutron source changes from pure D-D to pure D-T. This calibration is being applied to recent TFTR /open quotes/supershot/close quotes/ data, where the uncollided neutron flux in the post-beam phase contains a high proportion of D-T neutrons from the burnup of D-D tritons. 8 refs., 4 figs,. 2 tabs

  19. Standard test method for analysis of urine for uranium-235 and uranium-238 isotopes by inductively coupled plasma-mass spectrometry

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This test method covers the determination of the concentration of uranium-235 and uranium-238 in urine using Inductively Coupled Plasma-Mass Spectrometry. This test method can be used to support uranium facility bioassay programs. 1.2 This method detection limits for 235U and 238U are 6 ng/L. To meet the requirements of ANSI N13.30, the minimum detectable activity (MDA) of each radionuclide measured must be at least 0.1 pCi/L (0.0037 Bq/L). The MDA translates to 47 ng/L for 235U and 300 ng/L for 238U. Uranium– 234 cannot be determined at the MDA with this test method because of its low mass concentration level equivalent to 0.1 pCi/L. 1.3 The digestion and anion separation of urine may not be necessary when uranium concentrations of more than 100 ng/L are present. 1.4 Units—The values stated in picoCurie per liter units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard. 1....

  20. Performance of the LEU fuel and use of higher 235U loading in the Pakistan Research Reactor-1 (PARR-1) fuel

    The Pakistan Research Reactor (PARR-1) is a 10 MWth swimming pool research reactor using MTR type fuel. It achieved first criticality on December 21, 1965. After operation of about 25 years it was converted to LEU (20%235U) fuel with power upgraded to 10 MWth. During studies for new fuel design it was found that 290 grams of 235U per standard fuel element will be sufficient to attain about 35% burnup and the fuel was fabricated with this loading. The converted and upgraded reactor attained first criticality in October 1991 and full power in May 1992. Since then the reactor has been in regular operation with satisfactory fuel performance. In 1998 the target burnup was enhanced to 40% and several fuel elements have been discharged after achieving this burnup. In the next fuel design it is being considered, to increase the 235U loading by about 10%. Preliminary analyses show that burnup can be enhanced to about 50% in this way. Detailed analyses of the mixed cores (containing 290 and 320 gram fuel elements) and then high loading cores are being planned. At the time of conversion to LEU fuel, several of the HEU fuel elements had very low burnup. It is also being studied to re-use these elements with the present LEU fuel. (author)

  1. Concentrations of uranium and 235U/238U ratios in soil and plant samples collected around the uranium conversion building in the JCO campus

    In order to assess possible contamination by U in the JCO campus following the criticality accident, 10 soil samples and 15 plant samples were collected around the uranium conversion building. Uranium concentrations and isotopic compositions (235U/238U ratio) were determined by ICP-MS. Concentrations of Th in soil were also determined for comparison. Concentrations of U in soils were comparable to the U values for common Japanese soils. However, the U/Th ratios for these soil samples were markedly higher than the control value, suggesting possible contamination by U. The 235U/238U atom ratios in soil and plant samples were notably higher than the natural ratio, 0.00725. The highest values, 0.0162 for soil and 0.0193 for plant, were found in samples collected near the conversion building. However, a relatively high ratio was observed at a site more than 50 m from the building, indicating that enriched U may have been released not only from the conversion building but also from other unknown sources. 235U/238U atom ratios were in general higher in plants than in soils collected at the same points

  2. Long-Range Alpha Particle Emission in the Fission of U235 by 3-MeV Neutrons

    The energy and angular distribution of long-range alpha particles emitted in the fission of U235 induced by 3-MeV neutrons have been measured. The alpha panicles were detected by solid-state detector and the fission fragments were detected by a gas scintillation counter. The neutrons were produced by the T (p, n) He3 reaction using a 5.5- MeV Van de Graaff accelerator. About 3000 fission events accompanied by the emission of a high-energy alpha panicle were recorded. The most probable energy of the alpha particles is between 15-16 MeV. and the energy distribution has a full width at half maximum of about D MeV, which is the same as observed in tliermal- neutron fission. The angular distribution of the long-range alpha panicles with respect to the incident neutron direction was found to be forward-peaked, in agreement with previous work on alpha emission in 14-MeV neutron-induced fission of LP. At angles of 0° and 90° with respect to the incident neutron direction the alpha panicles were detected with an angular spread of about ± 25°. The anisotropy [Nα(0°)/ Nα(90°)] was found to be 1.320 ± 0.12. This value is in agreement with the anisotropy calculated on the basis of statistical evaporation of panicles. The results of the present investigation are consistent with the hypothesis that the emission of long-range alpha panicles in fission is an evaporation process. The implications of the results of this work and of other recent investigations on long-range alpha emission are discussed. (author)

  3. U3-U5-PU9-CRITICALS, Critical Dimensions of Systems containing U235, Pu239, and U233

    Description: Compilation of critical data obtained from experiments performed in a number of laboratories during the period of 1945 through 1985. It supplements the Nuclear Safety Guide [Report. TID-7016 (Rev. 2)(ref.2) in presenting critical data on which recommendations of the Guide are based. This report gives critical data without safety factors, and is no substitute for the Guide or for the related document, The American National Standard for Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors (ref.3). This standard is supported by publications of H. K. Clark that interpret criticality information for Pu, U-233 and U-235 systems (ref.4-6). Information for guiding the safety design of equipment for handling the three common fissile materials appears to a certain extent in the Nuclear Safety Guide, and with greater detail in several handbooks (ref.7). Other publications specify conditions for unique processes with particular fissionable material (ref.8). Experiments of several types which contribute results applicable to nuclear design and to safety problems have been described by Callihan (ref.9). Critical measurements with materials of interest in desired configurations yield information of greatest usefulness and accuracy. In some cases, calculated results are desirable to fill in experimental data or to extend them. Where they appear in the reports, they are identified as calculations because of the uncertainty associated with them. Calculated extensions of experimental data are included to show the nature of trends, not to substitute for results of experiments. They should be used with caution. A fundamental aim of this document is to illustrate relationships among critical data. The compilation and correlation of data for this purpose, from many measurements in a number of laboratories, require a certain amount of normalization or reduction to common terms. Frequently, for example, the effects of variations in geometry or

  4. Calculation of prompt fission product average cross sections for neutron-induced fission of 235U and 239Pu

    Yield-weighted average cross sections of neutron radiative capture, (n,2n), and (n,3n) reactions over prompt fission products (FPs) from 235U and 239Pu are calculated. The prompt fission production yields are taken from the ENDF/B-VII.0 library. The FPs for each fissile material exist over a range of approximately 1000 neutron-rich nuclides. Several nuclear reaction codes are utilized for calculating the cross sections on each individual fission product - EMPIRE-2.19, TALYS-1.0, GNASH, and CoH. The influence of the FP isomers on the average cross sections is examined with TALYS. We investigate the dependence of the average cross sections on the number of FPs taken for averaging. It is shown that the average capture cross section is much more sensitive to the number of FPs included, compared with the (n,2n) and (n,3n) reactions. An intercomparison of the calculated cross sections with the different reaction codes is carried out. In the capture reaction, EMPIRE predicted lower cross section than TALYS and CoH owing to different default assumptions used in the γ-ray strength function modeling. Moreover, the pre-equilibrium models implemented in each code give different predictions for the neutron-emission reactions, although the differences are relatively small. We also discuss a difference between the macroscopic and microscopic calculation options in TALYS for the pre-equilibrium model, optical potential model, and γ-ray strength function. The predictive capability of the reaction codes for the capture reaction is examined by comparing their calculations with the ENDF data, which are based on measurements. Compared with the historic Foster and Arthur's evaluation, our new (n,2n) predictions are similar, although our capture predictions are almost an order of magnitude higher. Recommended cross sections for use in applications have been tabulated in ENDF-formatted files. (author)

  5. Prediction of ground vibration due to the collapse of a 235 m high cooling tower under accidental loads

    Highlights: ► Ground vibration due to the collapse of a huge cooling tower was predicted. ► Accidental loads with different characteristics caused different collapse modes. ► Effect of ground vibration on the nuclear-related facilities cannot be ignored. -- Abstract: A comprehensive approach is presented in this study for the prediction of the ground vibration due to the collapse of a 235 m high cooling tower, which can be caused by various accidental loads, e.g., explosion or strong wind. The predicted ground motion is to be used in the safety evaluation of nuclear-related facilities adjacent to the cooling tower, as well as the plant planning of a nuclear power station to be constructed in China. Firstly, falling weight tests were conducted at a construction site using the dynamic compaction method. The ground vibrations were measured in the form of acceleration time history. A finite element method based “falling weight-soil” model was then developed and verified by field test results. Meanwhile, the simulated collapse processes of the cooling tower under two accidental loads were completed in a parallel study, the results of which are briefly introduced in this paper. Furthermore, based on the “falling weight-soil” model, “cooling tower-soil” models were developed for the prediction of the ground vibrations induced by two collapse modes of the cooling tower. Finally, for a deep understanding of the vibration characteristics, a parametric study was also conducted with consideration of different collapse profiles, soil geologies as well as the arrangements of an isolation trench. It was found that severe ground vibration occurred in the vicinity of the cooling tower when the collapse happened. However, the vibration attenuated rapidly with the increase in distance from the cooling tower. Moreover, the “collapse in integrity” mode and the rock foundation contributed to exciting intense ground vibration. By appropriately arranging an isolation

  6. Prediction of ground vibration due to the collapse of a 235 m high cooling tower under accidental loads

    Lin, Feng; Li, Yi [Department of Building Engineering, Tongji University, No. 1239 Siping Road, Shanghai 200092 (China); Gu, Xianglin, E-mail: gxl@tongji.edu.cn [Department of Building Engineering, Tongji University, No. 1239 Siping Road, Shanghai 200092 (China); Zhao, Xinyuan [Department of Building Engineering, Tongji University, No. 1239 Siping Road, Shanghai 200092 (China); Tang, Dongsheng [Guangdong Electric Power Design Institute, No. 1 Tianfeng Road, Guangzhou, Guangdong 510663 (China)

    2013-05-15

    Highlights: ► Ground vibration due to the collapse of a huge cooling tower was predicted. ► Accidental loads with different characteristics caused different collapse modes. ► Effect of ground vibration on the nuclear-related facilities cannot be ignored. -- Abstract: A comprehensive approach is presented in this study for the prediction of the ground vibration due to the collapse of a 235 m high cooling tower, which can be caused by various accidental loads, e.g., explosion or strong wind. The predicted ground motion is to be used in the safety evaluation of nuclear-related facilities adjacent to the cooling tower, as well as the plant planning of a nuclear power station to be constructed in China. Firstly, falling weight tests were conducted at a construction site using the dynamic compaction method. The ground vibrations were measured in the form of acceleration time history. A finite element method based “falling weight-soil” model was then developed and verified by field test results. Meanwhile, the simulated collapse processes of the cooling tower under two accidental loads were completed in a parallel study, the results of which are briefly introduced in this paper. Furthermore, based on the “falling weight-soil” model, “cooling tower-soil” models were developed for the prediction of the ground vibrations induced by two collapse modes of the cooling tower. Finally, for a deep understanding of the vibration characteristics, a parametric study was also conducted with consideration of different collapse profiles, soil geologies as well as the arrangements of an isolation trench. It was found that severe ground vibration occurred in the vicinity of the cooling tower when the collapse happened. However, the vibration attenuated rapidly with the increase in distance from the cooling tower. Moreover, the “collapse in integrity” mode and the rock foundation contributed to exciting intense ground vibration. By appropriately arranging an isolation

  7. Delayed Fission Gamma-ray Characteristics of Th-232 U-233 U-235 U-238 and Pu-239

    Lane, Taylor [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Parma, Edward J. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2015-08-01

    Delayed fission gamma-rays play an important role in determining the time dependent ioniz- ing dose for experiments in the central irradiation cavity of the Annular Core Research Reactor (ACRR). Delayed gamma-rays are produced from both fission product decay and from acti- vation of materials in the core, such as cladding and support structures. Knowing both the delayed gamma-ray emission rate and the time-dependent gamma-ray energy spectrum is nec- essary in order to properly determine the dose contributions from delayed fission gamma-rays. This information is especially important when attempting to deconvolute the time-dependent neutron, prompt gamma-ray, and delayed gamma-ray contribution to the response of a diamond photo-conducting diode (PCD) or fission chamber in time frames of milliseconds to seconds following a reactor pulse. This work focused on investigating delayed gamma-ray character- istics produced from fission products from thermal, fast, and high energy fission of Th-232, U-233, U-235, U-238, and Pu-239. This work uses a modified version of CINDER2008, a transmutation code developed at Los Alamos National Laboratory, to model time and energy dependent photon characteristics due to fission. This modified code adds the capability to track photon-induced transmutations, photo-fission, and the subsequent radiation caused by fission products due to photo-fission. The data is compared against previous work done with SNL- modified CINDER2008 [ 1 ] and experimental data [ 2 , 3 ] and other published literature, includ- ing ENDF/B-VII.1 [ 4 ]. The ability to produce a high-fidelity (7,428 group) energy-dependent photon fluence at various times post-fission can improve the delayed photon characterization for radiation effects tests at research reactors, as well as other applications.

  8. Autoimmune Conditions in 235 Hemochromatosis Probands with HFE C282Y Homozygosity and Their First-Degree Relatives

    James C. Barton

    2015-01-01

    Full Text Available We performed a retrospective study of autoimmune conditions (ACs in 235 hemochromatosis probands at diagnosis by analyzing age, sex, ACs, history of first-degree family members with ACs (FH, diabetes, heavy ethanol consumption, elevated serum ALT/AST, nonalcoholic fatty liver disease, viral hepatitis, cirrhosis, iron removed to achieve iron depletion (QFe, and positivity for human leukocyte antigen (HLA haplotypes A∗01, B∗08; A∗02, B∗44; A∗03, B∗07; A∗03, B∗14; and A∗29, B∗44. There were 138 men (58.7%. Median followup was 19.6 y. One or more of 19 ACs were diagnosed in each of 35 probands (14.9%. Prevalences of Hashimoto’s thyroiditis, rheumatoid arthritis, and ankylosing spondylitis were 8.1% (95% CI: [5.1, 12.5], 1.7% [0.6, 4.6], and 0.0085 [0.0015, 0.0337], respectively. Eighteen probands (7.7% had a FH. Eight probands with ACs had 9 family members with ACs. In a logistic regression, ACs were less likely in men (odds ratio (OR 0.3 [0.1, 0.6] and more likely in probands with a FH (OR 4.1 [1.4, 11.8]. Overall ACs risk was not significantly associated with QFe or HLA haplotypes. Estimated survival of probands with and without ACs did not differ significantly. We conclude that ACs are common in hemochromatosis probands, especially women and probands with a FH.

  9. Catch uranium 235

    This book is divided into seven chapters. The contents of this book are look for the source of nuclear energy with summary of quantum physics, structure of matter and an atomic nucleus and generative principle of nuclear energy, look for useful resource with natural energy resources in the world and home and development and application of alternative energy, development by nuclear energy with basic conception of nuclear power plant and structure and major system, useful using for a radioactive isotope with various using of X rays and useful use of a radioactive isotope, nuclear safety and safety regulations, safe management for an radiation and international environment around nuclear energy.

  10. Chemical Stability of P507-N235 System and Its Synergistic Extraction for NdCl3%P507与N235混合溶剂的稳定性及对NdCl3的协萃效应

    杨幼明; 蓝桥发; 邓声华; 聂华平; 叶信宇

    2013-01-01

    The salty waste water generated by saponification in the rare earth extraction process has greatly given rise to environmental pollution.A double solvent system of P507 and N235,which extract rare earth ions and acids respectively,was designed for rare earth extraction without saponification.The chemical stability and synergistic effect of P507-N235 system for Nd3 +were investigated and the experimental results showed that chemical structure of the mixed extractants was stable after extraction-regeneration process although mixing of P507 and N235 was an exothermic reaction with changing characteristic peaks in their infrared spectra.A significant synergistic effect was achieved and the as-prepared complex in extraction was REA3·(R3N·HA)·3R3NHCl.The results obtained may contribute to the development of non-saponification rare earth extraction process.%稀土萃取分离过程皂化产生的含盐废水严重污染环境.利用P507萃取稀土离子、N235萃取酸的特性,设计了P507-N235双溶剂无皂化稀土萃取体系,研究了双溶剂有机相的稳定性及对Nd3+的协萃效应.P507与N235混合时发生放热现象,红外光谱分析显示其特征峰发生了变化,但32次萃取-再生后的混合萃取剂的化学结构稳定;P507与N235对Nd3+具有显著的协萃效果,形成的萃合物为REA3·(R3N·HA)·3R3 NHCl.研究结果为无皂化稀土萃取分离新工艺开发提供了依据.

  11. NVP-BEZ235 and NVP-BGT226, dual phosphatidylinositol 3-kinase/mammalian target of rapamycin inhibitors, enhance tumor and endothelial cell radiosensitivity

    The phosphatidylinositol 3-kinase (PI3K)/Akt pathway is activated in tumor cells and promotes tumor cell survival after radiation-induced DNA damage. Because the pathway may not be completely inhibited after blockade of PI3K itself, due to feedback through mammalian target of rapamycin (mTOR), more effective inhibition might be expected by targeting both PI3K and mTOR inhibition. We investigated the effect of two dual PI3K/mTOR (both mTORC1 and mTORC2) inhibitors, NVP-BEZ235 and NVP-BGT226, on SQ20B laryngeal and FaDu hypopharyngeal cancer cells characterised by EGFR overexpression, on T24 bladder tumor cell lines with H-Ras mutation and on endothelial cells. Analysis of target protein phosphorylation, clonogenic survival, number of residual γH2AX foci, cell cycle and apoptosis after radiation was performed in both tumor and endothelial cells. In vitro angiogenesis assays were conducted as well. Both compounds effectively inhibited phosphorylation of Akt, mTOR and S6 target proteins and reduced clonogenic survival in irradiated tumor cells. Persistence of DNA damage, as evidenced by increased number of γH2AX foci, was detected after irradiation in the presence of PI3K/mTOR inhibition, together with enhanced G2 cell cycle delay. Treatment with one of the inhibitors, NVP-BEZ235, also resulted in decreased clonogenicity after irradiation of tumor cells under hypoxic conditions. In addition, NVP-BEZ235 blocked VEGF- and IR-induced Akt phosphorylation and increased radiation killing in human umbilical venous endothelial cells (HUVEC) and human dermal microvascular dermal cells (HDMVC). NVP-BEZ235 inhibited VEGF-induced cell migration and capillary tube formation in vitro and enhanced the antivascular effect of irradiation. Treatment with NVP-BEZ235 moderately increased apoptosis in SQ20B and HUVEC cells but not in FaDu cells, and increased necrosis in both tumor and endothelial all cells tumor. The results of this study demonstrate that PI3K/mTOR inhibitors can

  12. Comparison of the effects of the PI3K/mTOR inhibitors NVP-BEZ235 and GSK2126458 on tamoxifen-resistant breast cancer cells

    Kim, Ji Eun; Rewcastle, Gordon W; Finlay, Graeme J; Baguley, Bruce C

    2011-01-01

    Background Treatment with anti-estrogens or aromatase inhibitors is commonly used for patients with estrogen receptor-positive (ER+) breast cancers; however resistant disease develops almost inevitably, requiring a choice of secondary therapy. One possibility is to use inhibitors of the PI3K/mTOR pathway and several candidate drugs are in development. We examined the in vitro effects of two inhibitors of the PI3K/mTOR pathway on resistant MCF-7 cells. Results The derived sub-lines showed increased resistance to tamoxifen but none exhibited concomitantly increased sensitivity to the PI3K inhibitors. NVP-BEZ235 and GSK2126458 acted mainly by induction of cell cycle arrest, particularly in G1-phase, rather than by induction of apoptosis. The lines varied considerably in their utilization of the AKT, p70S6K and ERK pathways. NVP-BEZ235 and GSK2126458 inhibited AKT signaling but NVP-BEZ235 showed greater effects than GSK2126458 on p70S6K and rpS6 signaling with effects resembling those of rapamycin. Methods We cultured MCF-7 cells for prolonged periods either in the presence of the anti-estrogen tamoxifen (three sub-lines) or in estrogen free medium (two sub-lines) to mimic the effects of clinical treatment. We then analyzed the effects of two dual PI3K/mTOR phosphoinositide-3-kinase inhibitors, NVP-BEZ235 and GSK2126458, on the growth and signaling pathways of these MCF-7 sub-lines. The functional status of the PI3K, mTOR and ERK pathways was analyzed by measuring phosphorylation of AKT, p70S6K, rpS6 and ERK. Conclusion Increased resistance to tamoxifen in these MCF-7 sub-lines is not associated with hypersensitivity to PI3K inhibitors. While both drugs inhibited AKT signaling, NVP-BEZ235 resembled rapamycin in inhibiting the mTOR pathway. PMID:21464613

  13. Redundant 230Th/ 234U/ 238U, 231Pa/ 235U and 14C dating of fossil corals for accurate radiocarbon age calibration

    Chiu, Tzu-Chien; Fairbanks, Richard G.; Mortlock, Richard A.; Cao, Li; Fairbanks, Todd W.; Bloom, Arthur L.

    2006-09-01

    230Th/ 234U/ 238U dating of fossil corals by mass spectrometry is remarkably precise, but some samples exposed to freshwater over thousands of years may gain and/or lose uranium and/or thorium and consequently yield inaccurate ages. Although a δ 234U initial value equivalent to modern seawater and modern corals has been an effective quality control criterion, for samples exposed to freshwater but having δ 234U initial values indistinguishable from modern seawater and modern corals, there remains a need for additional age validation in the most demanding applications such as the 14C calibration (Fairbanks et al., 2005. Radiocarbon calibration curve spanning 0 to 50,000 years BP based on paired 230Th/ 234U/ 238U and 14C dates on pristine corals. Quaternary Science Reviews 24(16-17), 1781-1796). In this paper we enhance screening criteria for fossil corals older than 30,000 years BP in the Fairbanks0805 radiocarbon calibration data set (Fairbanks et al., 2005) by measuring redundant 230Th/ 234U/ 238U and 231Pa/ 235U dates via multi-collector magnetic sector inductively coupled plasma mass spectrometry (MC-MS-ICPMS) using techniques described in Mortlock et al. (2005. 230Th/ 234U/ 238U and 231Pa/ 235U ages from a single fossil coral fragment by multi-collector magnetic-sector inductively coupled plasma mass spectrometry. Geochimica et Cosmochimica Acta 69(3), 649-657.). In our present study, we regard paired 231Pa/ 235U and 230Th/ 234U/ 238U ages concordant when the 231Pa/ 235U age (±2 σ) overlaps with the associated 230Th/ 234U/ 238U age (±2 σ). Out of a representative set of 11 Fairbanks0805 (Fairbanks et al., 2005) radiocarbon calibration coral samples re-measured in this study, nine passed this rigorous check on the accuracy of their 230Th/ 234U/ 238U ages. The concordancy observed between 230Th/ 234U/ 238U and 231Pa/ 235U dates provides convincing evidence to support closed system behavior of these fossil corals and validation of their 230Th/ 234U/ 238U

  14. Effects of vegetarian type and duration on body composition in 235 Shanghai vegetarians%上海市235名素食者素食类型和时间对其体成分的影响

    毛绚霞; 沈秀华; 唐文静; 赵烨; 彭一航; 赵诣; 汤庆娅; 蔡威

    2016-01-01

    目的 了解不同素食类型和素食时间对素食者体成分状态的影响.方法 2012年4月-2013年7月在上海市市中心10家素餐馆中招募愿意接受调查的上海市区成年健康素食者235名,按照素食类型分为全素组(n=99)和奶蛋素组(n=136),按照素食时间分为素食<5年组(n=157)和素食≥5年组(n=78),分别实施问卷调查,测量身高和体质量,采用人体成分分析仪进行体成分测量.结果 多因素分析发现:校正年龄、性别和素食时间后,全素组与奶蛋素组人体蛋白质、骨骼肌、矿物质及脂肪的百分含量等体成分指标的差异无统计学意义(P>0.05);校正年龄、性别、素食时间和膳食能量摄入量后,两组超重/肥胖的发病危险性无显著差异(P>0.05),但奶蛋素组发生中心性肥胖的危险性显著低于全素组(OR=0.164,95%CI0.048~0.554,P =0.004);素食<5年组与素食≥5年组上述指标的差异无统计学意义(P>0.05).结论 不同素食类型和素食时间长短对各项体成分指标无明显影响;奶蛋素可能比全素更有助于降低发生中心性肥胖的危险性,但尚需进一步研究加以证实.

  15. Chemical, optical and other data collected aboard the THOMAS G. THOMPSON during cruise TN235 in the South Pacific Ocean from 2009-05-16 to 2009-06-08 (NODC Accession 0104352)

    National Oceanic and Atmospheric Administration, Department of Commerce — NODC Accession 0104352 includes chemical, optical and other data collected aboard the THOMAS G. THOMPSON during cruise TN235 in the South Pacific Ocean from...

  16. 235例肺外结核性创面患者流行病学调查%Epidemiological investigation of 235 patients with extra-pulmonary tuberculosis wounds

    常娜; 贾赤宇; 刘真; 张亚洁; 李文婷; 田甜

    2015-01-01

    目的 初步探讨肺外结核性创面流行病学特点和规律,为临床研究提供可靠数据.方法 对笔者单位2010年1月-2012年12月收治的肺外结核性创面患者的性别、年龄、民族、家庭背景、卡介苗接种情况、原发病灶、外伤史这几项资料进行回顾性分析,总结其规律及特点. 结果 5 863例肺外结核病患者中,235例出现结核性创面,占4.0%.其中男139例、女96例,男女之比为1.4∶1.0.年龄1~87(37±18)岁,其中大于15岁且小于或等于30岁青壮年患者构成比最大(100例,42.6%).多数患者为汉族;仅有11例患者为少数民族,占4.7%.患者中163例来自农村,占69.4%;72例来自城镇,占30.6%.卡介苗接种率为13.6%(32例).原发病灶中,以周围淋巴结结核为主,共112例,占47.7%,其中又以颈部淋巴结结核为主(99例,88.4%).21例(男19例、女2例)患者近期有车祸等外伤史. 结论 结核性创面有一定的发病率,并非罕见,以农村地区青壮年人群多发,患者的卡介苗接种率较低,颈部淋巴结结核为主要原发病灶.%Objective To investigate the epidemiological characteristics and patterns of extra-pulmonary tuberculosis wounds in order to provide reliable data for further clinical research.Methods Records of patients with extra-pulmonary tuberculosis wounds hospitalized from January 2010 to December 2012 were retrospectively analyzed,including gender,age,nationality,family background,Bacille CalmetteGuerin (BCG) vaccination,primary lesion,and history of injury.Results Tuberculosis wounds were found in 235 patients among 5 863 patients with extra-pulmonary tuberculosis,accounting for 4.0%.Among the patients with tuberculosis wounds,there were 139 male and 96 female,and the ratio of male to female was 1.4∶ 1.0.The age of patients ranged from 1 to 87 (37 ± 18) years old,and the highest incidence occurred in patients older than 15 and younger than or equal to 30 years old (100 cases

  17. Validation of a high-resolution gamma-ray spectrometry method for determination of 235U isotopic abundance

    The development of advanced computational algorithms for analysis of complex gamma and X-ray spectra has stimulated new investigations involving the use of nondestructive assay (NDA) based methodologies for measuring isotopic composition of nuclear materials. These new techniques provide an improved performance compared to the older analysis methodologies. Although in most cases, destructive assay (DA) techniques are the only way to achieve the desired accuracy, NDA is becoming a more frequently used alternative technique. NDA analysis can be a more simple and desirable solution for several measurement problems whenever its performance meets the imposed requirements. Since 2004 the Nuclear Energy Commission of Brazil (CNEN), in cooperation with the United States Department of Energy (US-DOE), through the Safeguards Laboratory (LASAL) and Oak Ridge National Laboratory (ORNL), respectively, has conducted several joint research activities. One of those projects is aimed to develop and implement a powerful and reliable NDA technique for isotopic and quantitative verification of uranium inventories in Brazilian bulk facilities. In Safeguards applications, desired performance for the applied measurement techniques depends on several factors (i.e. material characteristics, plant throughput, etc). In many cases use of complex DA techniques (i.e. mass spectrometry) requires substantial resources and, when applicable, an NDA option could be a more cost- and time-effective solution. Recently completed first phase of the project included hardware and software upgrades: new high-purity germanium (HPGe) detector, multi-channel analyzer (MCA), and an updated version of the multi-group analysis code - MGAU [1]. Current work includes investigation and validation of the new methodology for measuring powders and pellets enriched from 0.5 to 5% of 235U. The effects of several parameter variations (i.e. counting statistics, geometry, background level, temperature, humidity, etc.) were

  18. Coulex fission of 234U, 235U, 237Np, and 238Np studied within the SOFIA experimental program

    SOFIA (Studies On FIssion with Aladin) is an experimental project which aims at systematically measuring the fission fragments' isotopic yields as well as their total kinetic energy, for a wide variety of fissioning nuclei. The PhD work presented in this dissertation takes part in the SOFIA project, and covers the fission of nuclei in the region of the actinides: 234U, 235U, 237Np and 238Np. The experiment is led at the heavy-ion accelerator GSI in Darmstadt, Germany. This facility provides intense relativistic primary beam of 238U. A fragmentation reaction of the primary beam permits to create a secondary beam of radioactive ions, some of which the fission is studied. The ions of the secondary beam are sorted and identified through the FR-S (Fragment Separator), a high resolution recoil spectrometer which is tuned to select the ions of interest.The selected - fissile - ions then fly further to Cave-C, an experimental area where the fission experiment itself takes place. At the entrance of the cave, the secondary beam is excited by Coulomb interaction when flying through an target; the de-excitation process involves low-energy fission. Both fission fragments fly forward in the laboratory frame, due to the relativistic boost inferred from the fissioning nucleus.A complete recoil spectrometer has been designed and built by the SOFIA collaboration in the path of the fission fragments, around the existing ALADIN magnet. The identification of the fragments is performed by means of energy loss, time of flight and deviation in the magnet measurements. Both fission fragments are fully (in mass and charge) and simultaneously identified.This document reports on the analysis performed for (1) the identification of the fissioning system, (2) the identification of both fission fragments, on an event-by-event basis, and (3) the extraction of fission observables: yields, TKE, total prompt neutron multiplicity. These results, concerning the actinides, are discussed, and the

  19. Evolution of micro-arc oxidation behaviors of the hot-dipping aluminum coatings on Q235 steel substrate

    Micro-arc oxidation (MAO) is not applicable to prepare ceramic coatings on the surface of steel directly. In this work, hybrid method of MAO and hot-dipping aluminum (HDA) were employed to fabricate composite ceramic coatings on the surface of Q235 steel. The evolution of MAO coatings, such as growth rate, thickness of the total coatings, ingrown and outgrown coatings, cross section and surface morphologies and phase composition of the ceramic coatings were studied. The results indicate that both the current density and the processing time can affect the total thickness, the growth rate and the ratio of ingrown and outgrown thickness of the ceramic coatings. The total thickness, outgrown thickness and growth rate have maximum values with the processing time prolonged. The time when the maximum value appears decreases and the ingrown dominant turns to outgrown dominant little by little with the current density increasing. The composite coatings obtained by this hybrid method consists of three layers from inside to outside, i.e. Fe-Al alloy layer next to the substrate, aluminum layer between the Fe-Al layer and the ceramic coatings which is as the top exterior layer. Metallurgical bonding was observed between every of the two layers. There are many micro-pores and micro-cracks, which act as discharge channels and result of quick and non-uniform cooling of melted sections in the MAO coatings. The phase composition of the ceramic coatings is mainly composed of amorphous phase and crystal Al2O3 oxides. The crystal Al2O3 phase includes κ-Al2O3, θ-Al2O3 and β-Al2O3. Compared with the others, the β-Al2O3 content is the least. The MAO process can be divided into three periods, namely the common anodic oxidation stage, the stable MAO stage and the ceramic coatings destroyed stage. The exterior loose part of the ceramic coatings was destroyed badly in the last period which should be avoided during the MAO process.

  20. Trace element distribution and 235U/238U ratios in Euphrates waters and in soils and tree barks of Dhi Qar province (southern Iraq).

    Riccobono, Francesco; Perra, Guido; Pisani, Anastasia; Protano, Giuseppe

    2011-09-01

    To assess the quality of the environment in southern Iraq after the Gulf War II, a geochemical survey was carried out. The survey provided data on the chemistry of Euphrates waters, as well as the trace element contents, U and Pb isotopic composition, and PAH levels in soil and tree bark samples. The trace element concentrations and the (235)U/(238)U ratio values in the Euphrates waters were within the usual natural range, except for the high contents of Sr due to a widespread presence of gypsum in soils of this area. The trace element contents in soils agreed with the common geochemistry of soils from floodplain sediments. Some exceptions were the high contents of Co, Cr and Ni, which had a natural origin related to ophiolitic outcrops in the upper sector of the Euphrates basin. The high concentrations of S and Sr were linked to the abundance of gypsum in soils. A marked geochemical homogeneity of soil samples was suggested by the similar distribution pattern of rare earth elements, while the (235)U/(238)U ratio was also fairly homogeneous and within the natural range. The chemistry of the tree bark samples closely reflected that of the soils, with some notable exceptions. Unlike the soils, some tree bark samples had anomalous values of the (235)U/(238)U ratio due to mixing of depleted uranium (DU) with the natural uranium pool. Moreover, the distribution of some trace elements (such as REEs, Th and Zr) and the isotopic composition of Pb in barks clearly differed from those of the nearby soils. The overall results suggested that significant external inputs occurred implying that once formed the DU-enriched particles could travel over long distances. The polycyclic aromatic hydrocarbon concentrations in tree bark samples showed that phenanthrene, fluoranthene and pyrene were the most abundant components, indicating an important role of automotive traffic. PMID:21774965

  1. Beta and gamma decay heat measurements between 0.1s--50,000s for neutron fission of 235U, 238U and 239Pu

    A helium-jet/tape-transport system is employed in the study of beta-particle and gamma-ray energy spectra of aggregate fission products as a function of time after fission. During the initial nine months of this project we have investigated the following areas: Design, assembly and characterization of a beta-particle spectrometer; Measurement of 235U(nthff) beta spectra for delay times 0.2 s to 12,000 s; Assembly and characterization of a 5 x 5 Nal(Tl) gamma-ray spectrometer; Measurement of 235U(nthff) gamma-ray spectra for delay times 0.2s to 1 5,500s; Assembly and characterization of HPGe gamma-ray spectrometer with a Nal(Tl) Compton-and-background-suppression annulus; Measurement of 235U(n th,ff) high-resolution gamma-ray spectra for delay times 0.6 s to over 100,000 s; Comparison of individual gamma-line intensities with ENDF/B-VI; Adaptation to our computer of unfolding program FERDO for beta and gamma aggregate fission-product energy spectra and development of a spectrum-stripping program for analysis of HPGe gamma-ray spectra; Study of the helium-jet fission-fragment elemental transfer efficiency. This work has resulted in the publication of twelve BAPS abstracts of presentations at scientific meetings. There are currently four Ph.D. and two M.S. candidates working on dissertations associated with the project

  2. Exploratory study of fission product yields of neutron-induced fission of 235U , 238U , and 239Pu at 8.9 MeV

    Bhatia, C.; Fallin, B. F.; Gooden, M. E.; Howell, C. R.; Kelley, J. H.; Tornow, W.; Arnold, C. W.; Bond, E.; Bredeweg, T. A.; Fowler, M. M.; Moody, W.; Rundberg, R. S.; Rusev, G. Y.; Vieira, D. J.; Wilhelmy, J. B.; Becker, J. A.; Macri, R.; Ryan, C.; Sheets, S. A.; Stoyer, M. A.; Tonchev, A. P.

    2015-06-01

    Using dual-fission chambers each loaded with a thick (200 -400 -mg /c m2) actinide target of 235 ,238U or 239Pu and two thin (˜10 -100 -μ g /c m2) reference foils of the same actinide, the cumulative yields of fission products ranging from 92Sr to 147Nd have been measured at En= 8.9 MeV . The 2H(d ,n ) 3He reaction provided the quasimonoenergetic neutron beam. The experimental setup and methods used to determine the fission product yield (FPY) are described, and results for typically eight high-yield fission products are presented. Our FPYs for 235U(n ,f ) , 238U(n ,f ) , and 239Pu(n ,f ) at 8.9 MeV are compared with the existing data below 8 MeV from Glendenin et al. [Phys. Rev. C 24, 2600 (1981), 10.1103/PhysRevC.24.2600], Nagy et al. [Phys. Rev. C 17, 163 (1978), 10.1103/PhysRevC.17.163], Gindler et al. [Phys. Rev. C 27, 2058 (1983), 10.1103/PhysRevC.27.2058], and those of Mac Innes et al. [Nucl. Data Sheets 112, 3135 (2011), 10.1016/j.nds.2011.11.009] and Laurec et al. [Nucl. Data Sheets 111, 2965 (2010), 10.1016/j.nds.2010.11.004] at 14.5 and 14.7 MeV, respectively. This comparison indicates a negative slope for the energy dependence of most fission product yields obtained from 235U and 239Pu , whereas for 238U the slope issue remains unsettled.

  3. Daily intake of /sup 234,235,238/U, /sup 228,230,232/Th and /sup 226,228/Ra by New York City residents

    The daily intake of long-lived alpha-emitting members of the U, Th and Ac series by New York City residents has been estimated from measurements of diet, water and air samples. The total daily intakes from inhalation, food and water consumption in mBq are 18 (234U), 0.7 (235U), 16 (238U), 6 (230Th), 4 (232Th) and 52 (226Ra). From this, we infer that the total daily intakes of 228Th and 228Ra are 4 and 35 mBq, respectively

  4. Accurate measurements of fission-fragment yields in 234,235,236,238U(γ,f) with the SOFIA set-up

    Chatillon, A.; Taïeb, J.; Martin, J.-F.; Pellereau, E.; Boutoux, G.; Gorbinet, T.; Grente, L.; Bélier, G.; Laurent, B.; Alvarez-Pol, H.; Ayyad, Y.; Benlliure, J.; Caamaño, M.; Audouin, L.; Casarejos, E.; Cortina-Gil, D.; Farget, F.; Fernández-Domínguez, B.; Heinz, A.; Jurado, B.; Kelić-Heil, A.; Kurz, N.; Lindberg, S.; Löher, B.; Nociforo, C.; Paradela, C.; Pietri, S.; Ramos, D.; Rodriguez-Sanchez, J.-L.; Rodrìguez-Tajes, C.; Rossi, D.; Schmidt, K.-H.; Simon, H.; Tassan-Got, L.; Törnqvist, H.; Vargas, J.; Voss, B.; Weick, H.; Yan, Y.

    2016-03-01

    SOFIA (Studies On Fission with Aladin) is a new experimental set-up dedicated to accurate measurement of fission-fragments isotopic yields. It is located at GSI, the only place to use inverse kinematics at relativistic energies in order to study the (γ,f) electromagnetic-induced fission. The SOFIA set-up is a large-acceptance magnetic spectrometer, which allows to fully identify both fission fragments in coincidence on the whole fission-fragment range. This paper will report on fission yields obtained in 234,235,236,238U(γ,f) reactions.

  5. Measurement of the neutron-induced fission cross-section of 243Am relative to 235U from 0.5 to 20 MeV

    The ratio of the neutron-induced fission cross-sections of 243Am and 235U was measured in the energy range from 0.5 to 20 MeV with uncertainties of ∼ 4%. The experiment was performed at the CERN nTOF facility using a fast ionization chamber. With the good counting statistics that could be achieved thanks to the high instantaneous flux and the low backgrounds, the present results are useful for resolving discrepancies in previous data sets and are important for future reactors with improved fuel burn-up. (orig.)

  6. Coupling Reaction of 4-Chloro-7-H-Pyrrolo[2,3-d]Pyrimidine with 2,3,5-Tri-O-Acetyl-b-D-Ribofuranosyl Chloride

    2001-01-01

    Coupling reaction of 4-chloro-7-H-pyrrolo[2,3-d]pyrimidine with 2,3,5-tri-O-acetyl -β-D-ribofuranosyl chloride under the basic condition was investigated.An abnormal coupling reaction,in which the heterocyclic base attacked at the carbon of 1,2-O-methylidene moiety instead of anomeric carbon of ribose was observed and the structure of products 5a,5b were identified by NMR and X-Ray diffraction.

  7. Measurement of the neutron-induced fission cross-section of {sup 243}Am relative to {sup 235}U from 0.5 to 20 MeV

    Belloni, F.; Milazzo, P.M.; Abbondanno, U.; Fujii, K.; Moreau, C. [Istituto Nazionale di Fisica Nucleare, Trieste (Italy); Calviani, M. [Laboratori Nazionali di Legnaro, Istituto Nazionale di Fisica Nucleare, Legnaro (Italy); CERN, Geneva (Switzerland); Colonna, N.; Barbagallo, M.; Marrone, S.; Meaze, M.H.; Tagliente, G.; Terlizzi, R. [Istituto Nazionale di Fisica Nucleare, Bari (Italy); Mastinu, P.; Gramegna, F. [Lab. Nazionali di Legnaro, Istituto Nazionale di Fisica Nucleare, Legnaro (Italy); Aerts, G.; Andriamonje, S.; Berthoumieux, E.; Dridi, W.; Gunsing, F.; Pancin, J.; Perrot, L.; Plukis, A. [Irfu, CEA, Gif-sur-Yvette (France); Alvarez, H.; Cano-Ott, D.; Duran, I.; Embid-Segura, M.; Gonzalez-Romero, E.; Paradela, C.; Tarrio, D. [Univ. de Santiago de Compostela, Galicia (Spain); Alvarez-Velarde, F.; Guerrero, C.; Martinez, T.; Villamarin, D.; Vincente, M.C. [Centro de Investigaciones Energeticas Medioambientales y Technologicas, Madrid (Spain); Andrzejewski, J.; Marganiec, J. [Univ. of Lodz (Poland); Audouin, L.; Dillmann, I.; Heil, M.; Kaeppeler, F.; Mosconi, M.; Plag, R.; Voss, F.; Walter, S.; Wisshak, K. [Karlsruhe Inst. of Technology, Eggenstein-Leopoldshafen (Germany). Inst. fuer Kernphysik; Badurek, G.; Jericha, E.; Leeb, H.; Oberhummer, H. [Technische Univ. Wien, Atominstitut der Oesterreichischen Universitaeten, Wien (Austria); Baumann, P.; David, S.; Kerveno, M.; Lukic, S.; Rudolf, G. [IReS, Centre National de la Recherche Scientifique/IN2P3, Strasbourg (France); Becvar, F.; Krticka, M. [Charles Univ., Faculty of Mathematics and Physics, Prague (Czech Republic); Calvino, F.; Cortes, G.; Poch, A.; Pretel, C. [Univ. Politecnica de Catalunya, Barcelona (Spain); Capote, R. [NAPC/Nuclear Data Section, International Atomic Energy Agency, Vienna (Austria); Univ. de Sevilla (Spain); Carrapico, C.; Goncalves, I.; Salgado, J.; Santos, C.; Tavora, L.; Vaz, P. [Inst. Tecnologico e Nuclear, Lisbon (Portugal)] [and others

    2011-12-15

    The ratio of the neutron-induced fission cross-sections of {sup 243}Am and {sup 235}U was measured in the energy range from 0.5 to 20 MeV with uncertainties of {approx} 4%. The experiment was performed at the CERN n{sub T}OF facility using a fast ionization chamber. With the good counting statistics that could be achieved thanks to the high instantaneous flux and the low backgrounds, the present results are useful for resolving discrepancies in previous data sets and are important for future reactors with improved fuel burn-up. (orig.)

  8. Trace element distribution and {sup 235}U/{sup 238}U ratios in Euphrates waters and in soils and tree barks of Dhi Qar province (southern Iraq)

    Riccobono, Francesco; Perra, Guido; Pisani, Anastasia; Protano, Giuseppe, E-mail: protano@unisi.it

    2011-09-01

    To assess the quality of the environment in southern Iraq after the Gulf War II, a geochemical survey was carried out. The survey provided data on the chemistry of Euphrates waters, as well as the trace element contents, U and Pb isotopic composition, and PAH levels in soil and tree bark samples. The trace element concentrations and the {sup 235}U/{sup 238}U ratio values in the Euphrates waters were within the usual natural range, except for the high contents of Sr due to a widespread presence of gypsum in soils of this area. The trace element contents in soils agreed with the common geochemistry of soils from floodplain sediments. Some exceptions were the high contents of Co, Cr and Ni, which had a natural origin related to ophiolitic outcrops in the upper sector of the Euphrates basin. The high concentrations of S and Sr were linked to the abundance of gypsum in soils. A marked geochemical homogeneity of soil samples was suggested by the similar distribution pattern of rare earth elements, while the {sup 235}U/{sup 238}U ratio was also fairly homogeneous and within the natural range. The chemistry of the tree bark samples closely reflected that of the soils, with some notable exceptions. Unlike the soils, some tree bark samples had anomalous values of the {sup 235}U/{sup 238}U ratio due to mixing of depleted uranium (DU) with the natural uranium pool. Moreover, the distribution of some trace elements (such as REEs, Th and Zr) and the isotopic composition of Pb in barks clearly differed from those of the nearby soils. The overall results suggested that significant external inputs occurred implying that once formed the DU-enriched particles could travel over long distances. The polycyclic aromatic hydrocarbon concentrations in tree bark samples showed that phenanthrene, fluoranthene and pyrene were the most abundant components, indicating an important role of automotive traffic. - Highlights: {yields} This is a contribution to the knowledge of the Iraqi environment

  9. Trace element distribution and 235U/238U ratios in Euphrates waters and in soils and tree barks of Dhi Qar province (southern Iraq)

    To assess the quality of the environment in southern Iraq after the Gulf War II, a geochemical survey was carried out. The survey provided data on the chemistry of Euphrates waters, as well as the trace element contents, U and Pb isotopic composition, and PAH levels in soil and tree bark samples. The trace element concentrations and the 235U/238U ratio values in the Euphrates waters were within the usual natural range, except for the high contents of Sr due to a widespread presence of gypsum in soils of this area. The trace element contents in soils agreed with the common geochemistry of soils from floodplain sediments. Some exceptions were the high contents of Co, Cr and Ni, which had a natural origin related to ophiolitic outcrops in the upper sector of the Euphrates basin. The high concentrations of S and Sr were linked to the abundance of gypsum in soils. A marked geochemical homogeneity of soil samples was suggested by the similar distribution pattern of rare earth elements, while the 235U/238U ratio was also fairly homogeneous and within the natural range. The chemistry of the tree bark samples closely reflected that of the soils, with some notable exceptions. Unlike the soils, some tree bark samples had anomalous values of the 235U/238U ratio due to mixing of depleted uranium (DU) with the natural uranium pool. Moreover, the distribution of some trace elements (such as REEs, Th and Zr) and the isotopic composition of Pb in barks clearly differed from those of the nearby soils. The overall results suggested that significant external inputs occurred implying that once formed the DU-enriched particles could travel over long distances. The polycyclic aromatic hydrocarbon concentrations in tree bark samples showed that phenanthrene, fluoranthene and pyrene were the most abundant components, indicating an important role of automotive traffic. - Highlights: → This is a contribution to the knowledge of the Iraqi environment after Gulf War II. → In fluvial waters

  10. Calculation of K{sub {infinity}} for homogeneous {sup 235}U metal mixtures: Will the real K{sub {infinity}} please stand up?

    Jordan, W.C.; Petrie, L.M.; Wright, R.Q.; Parks, C.V. [Oak Ridge National Lab., TN (United States)

    1997-06-01

    This paper very briefly analyzes a journal article about calculating k{sub {infinity}} for metals mixed with uranium 235, and compares the article results with other calculation methods. The article suggested that continuous energy cross sections gave more accurate results than groupwise cross sections. The mixtures described in the article were dry, fast systems with several unusual characteristics; however, the majority of multigroup libraries used for analysis were developed for well moderated thermal systems. The results of calculations performed using several different codes and cross sections for three uranium/metal mixtures are presented in this paper. 1 tab.

  11. Evaluation of fission cross sections and covariances for {sup 233}U, {sup 235}U, {sup 238}U, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu

    Kawano, Toshihiko [Kyushu Univ., Fukuoka (Japan); Matsunobu, Hiroyuki [Data Engineering, Inc. (Japan); Murata, Toru [AITEL Corporation, Tokyo (JP)] [and others

    2000-02-01

    A simultaneous evaluation code SOK (Simultaneous evaluation on KALMAN) has been developed, which is a least-squares fitting program to absolute and relative measurements. The SOK code was employed to evaluate the fission cross sections of {sup 233}U, {sup 235}U, {sup 238}U, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu for the evaluated nuclear data library JENDL-3.3. Procedures of the simultaneous evaluation and the experimental database of the fission cross sections are described. The fission cross sections obtained were compared with evaluated values given in JENDL-3.2 and ENDF/B-VI. (author)

  12. Accurate measurements of fission-fragment yields in 234,235,236,238U(γ,f with the SOFIA set-up

    Chatillon A.

    2016-01-01

    Full Text Available SOFIA (Studies On Fission with Aladin is a new experimental set-up dedicated to accurate measurement of fission-fragments isotopic yields. It is located at GSI, the only place to use inverse kinematics at relativistic energies in order to study the (γ,f electromagnetic-induced fission. The SOFIA set-up is a large-acceptance magnetic spectrometer, which allows to fully identify both fission fragments in coincidence on the whole fission-fragment range. This paper will report on fission yields obtained in 234,235,236,238U(γ,f reactions.

  13. Energy dependence of the neutron multiplicity P/sub nu/ in fast neutron induced fission of /sup 235,238/U and 239Pu

    Certain applications require knowledge of the higher moments of the neutron multiplicity probability. It can be shown that the second factorial moment is proportional to the fission rate in the sample, and that the third factorial moment can be of use in disentangling spontaneous fission from induced fission. Using a source of unpublished work in which neutron multiplicities were derived for the fast neutron induced fission of U-235, U-238, and Pu-239, the multiplicity probability has been calculated as a function of neutron energy for the energy range 0 to 10 MeV

  14. Uranium contents and {sup 235}U/{sup 238}U atom ratios in soil and earthworms in western Kosovo after the 1999 war

    Di Lella, L.A.; Nannoni, F.; Protano, G.; Riccobono, F. [Dipartimento di Scienze Ambientali ' G. Sarfatti' -Sezione di Geochimica Ambientale, University of Siena, Via del Laterino 8, I-53100, Siena (Italy)

    2005-01-20

    The uranium content and {sup 235}U/{sup 238}U atom ratio were determined in soils and earthworms of an area of Kosovo (Djakovica garrison), heavily shelled with depleted uranium (DU) ammunition during the 1999 war. The aim of the study was to reconstruct the small-scale distribution of uranium and assess the influence of the DU added to the surface environment. The total uranium concentration and the {sup 235}U/{sup 238}U ratio of topsoils showed great variability and were inversely correlated. The highest uranium levels (up to 31.47 mg kg{sup -1}) and lowest {sup 235}U/{sup 238}U ratios (minimum 0.002147) were measured in topsoils collected inside, or very close to, the clusters of DU penetrator holes. Regarding the fractionation of uranium in the surface soils, the uranium concentrations in the soluble and exchangeable fractions increased as the total uranium concentration of the topsoils increased. High and rather uniform percentage contents of uranium (24-36%) were associated with the poorly crystalline iron oxide phases of soils. In the U-enriched soils the elevated levels of the element were probably due to the presence of very small, unevenly distributed oxidized DU particles. The total uranium concentration in earthworms was in the range 0.142-0.656 mg kg{sup -1}, with the highest concentrations in Lumbricus terrestris. The juveniles of all three studied species seemed to accumulate uranium more than adults, probably due to age-related differences in metabolism. The {sup 235}U/{sup 238}U ratio in the earthworms was variable (0.005241-0.007266) and independent of both the total uranium contents in soils and the absolute uranium levels in the animals. Bioconcentration was greater at lower U concentrations in soil, probably due to an increasing rate of elimination of uranium by the earthworms as the soil contents of the element increase. The results of this study clearly indicate that DU was added to the soil of the study area. Nevertheless, the phenomenon was

  15. Beta-decay half-lives of neutron rich Cu and Ni isotopes produced by thermal fission of 235U and 239Pu

    The half-lives of very neutron rich isotopes of Ni and Cu have been measured. The isotopes are produced in very asymmetric thermal fission of 235U and 239Pu at the I.L.L. high flux reactor. They are separated by means of the Lohengrin spectrometer. They are identified with a ΔE-E ionization chamber and implanted in one of the 8 Si planar detectors where the β- particles are also detected. The time correlations between the implantation and the detection of β- particles provide the half-life. The values obtained are compared to current theoretical predictions

  16. Major Isoform of Zebrafish P0 Is a 23.5 KDa Myelin Glycoprotein Expressed in Selected White Matter Tracts of the Central Nervous System

    Bai, Qing; Sun, Ming; Stolz, Donna B.; Burton, Edward A.

    2011-01-01

    The zebrafish mpz gene, encoding the ortholog of mammalian myelin protein zero, is expressed in oligodendrocytes of the zebrafish central nervous system (CNS). The putative gene product, P0, has been implicated in promoting axonal regeneration in addition to its proposed structural functions in compact myelin. We raised novel zebrafish P0-specific antibodies and established that P0 is a 23.5 kDa glycoprotein containing a 3 kDa N-linked carbohydrate moiety. P0 was localized to myelin sheaths s...

  17. 热浸渗铝硅合金Q235钢的抗高温腐蚀性能研究%An Investigation on the High Temperature Resistant and Corrosion Resistant Properties of Q235 Steel Treated With Hot-Dip Aluminizing Silicon Alloy Layer

    曹银春; 丁毅; 魏无际; 石焕荣

    2004-01-01

    研究了Q235钢经热浸渗纯铝和不同硅含量的铝合金后的抗高温氧化和抗热腐蚀性能,比较了纯铝渗层和铝硅合金渗层的抗高温腐蚀性能,并分析了硅元素的作用.结果表明,Q235钢经热浸渗纯铝和铝硅合金后的抗氧化性能基本接近不锈钢,而抗热腐蚀性能则明显优于不锈钢.

  18. Use of delayed gamma rays for active non-destructive assay of 235U irradiated by pulsed neutron source (plasma focus)

    A pulsed neutron source based on plasma focus device has been used for active interrogation and assay of 235U by monitoring its delayed high energy γ-rays. The method involves irradiation of fissile material by thermal neutrons obtained after moderation of a burst of neutrons emitted upon fusion of deuterium in plasma focus (PF) device. The delayed gamma rays emitted from the fissile material as a consequence of induced fission were detected by a large volume sodium iodide (NaI(Tl)) detector. The detector is coupled to a data acquisition system of 2k input size with 2k ADC conversion gain. Counting was carried out in pulse height analysis mode for time integrated counts up to 100 s while the temporal profile of delayed gamma has been obtained by counting in multichannel scaling mode with dwell time of 50 ms. To avoid the effect of passive (natural) and active (from surrounding materials) backgrounds, counts have been acquired for gamma energy between 3 and 10 MeV. The lower limit of detection of 235U in the oxide samples with this set-up is estimated to be 14 mg

  19. Use of delayed gamma rays for active non-destructive assay of {sup 235}U irradiated by pulsed neutron source (plasma focus)

    Andola, Sanjay; Niranjan, Ram [Applied Physics Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Kaushik, T.C., E-mail: tckk@barc.gov.in [Applied Physics Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Rout, R.K. [Applied Physics Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Kumar, Ashwani; Paranjape, D.B.; Kumar, Pradeep; Tomar, B.S.; Ramakumar, K.L. [Radioanalytical Chemistry Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Gupta, S.C. [Applied Physics Division, Bhabha Atomic Research Centre, Mumbai 400085 (India)

    2014-07-01

    A pulsed neutron source based on plasma focus device has been used for active interrogation and assay of {sup 235}U by monitoring its delayed high energy γ-rays. The method involves irradiation of fissile material by thermal neutrons obtained after moderation of a burst of neutrons emitted upon fusion of deuterium in plasma focus (PF) device. The delayed gamma rays emitted from the fissile material as a consequence of induced fission were detected by a large volume sodium iodide (NaI(Tl)) detector. The detector is coupled to a data acquisition system of 2k input size with 2k ADC conversion gain. Counting was carried out in pulse height analysis mode for time integrated counts up to 100 s while the temporal profile of delayed gamma has been obtained by counting in multichannel scaling mode with dwell time of 50 ms. To avoid the effect of passive (natural) and active (from surrounding materials) backgrounds, counts have been acquired for gamma energy between 3 and 10 MeV. The lower limit of detection of {sup 235}U in the oxide samples with this set-up is estimated to be 14 mg.

  20. True ternary fission, the collinear decay into fragments of similar size in the 252Cf(sf) and 235U(nth, f) reactions

    The collinear cluster decay in 252Cf(sf, fff), with three cluster fragments of different masses (e.g. 132Sn, 52–48Ca, 68–72Ni), which has been observed by the FOBOS group in JINR, has established a new decay mode of heavy nuclei, the collinear cluster tripartition (CCT). The same type of ternary fission decay has been observed in the reaction 235U(nth, fff). This kind of “true ternary fission” of heavy nuclei has been predicted many times in theoretical works during the last decades. In the present note we discuss true ternary fission (TFFF) into three nuclei of almost equal size (e.g. Z=98→Zi=32, 34, 32) in the same systems. The possible fission channels are predicted from potential-energy (PES) calculations. These PES's show pronounced minima for several ternary fragmentation decays, e.g. for 252Cf(sf) and for 235U(nth, f). They suggest the existence of a variety of collinear ternary fission modes. The TFFF-decays chosen in this letter have very similar dynamical features as the previously observed collinear CCT-decays. The data obtained in the above mentioned experiments allow us to extract the yield for these TFFF-decays in both systems by using specific gates on the measured parameters. These yields are a few 1.0⋅10−6/(binary fission)

  1. R-matrix analysis of 235U neutron transmission and cross sections in the energy range 0 to 2.25 keV

    This document describes a new R-matrix analysis of 235U cross section data in the energy range from 0 to 2,250 eV. The analysis was performed with the computer code SAMMY, that has recently been updated to permit, for the first time, inclusion of both differential and integral data within the analysis process. Fourteen differential data sets and six integral quantities were used in this evaluation: two measurements of fission plus capture, one of fission plus absorption, six of fission alone, two of transmission, and one of eta, plus standard values of thermal cross sections for fission, capture, and scattering, and of K1 and the Westcott g-factors for both fission and absorption. An excellent representation was obtained for the high-resolution transmission, fission, and capture cross-section data as well as for the integral quantities. The result is a single set of resonance parameters spanning the entire range up to 2,250 eV, a decided improvement over the present ENDF/VI evaluation, in which eleven discrete resonance parameter sets are required to cover that same energy range. This new evaluation is expected to greatly improve predictability of the criticality safety margins for nuclear systems in which 235U is present

  2. Synthesis of imidazoline-based dissymmetric bis-quaternary ammonium gemini surfactant and its inhibition mechanism on Q235 steel in hydrochloric acid medium

    Zhang, J.; Gong, X.L.; Song, W.W.; Jiang, B.; Du, M. [Key Laboratory of Marine Chemistry Theory and Technology, Ministry of Education, College of Chemistry and Chemical Engineering, Ocean University of China, Qingdao, Shandong Province (China)

    2012-07-15

    An imidazoline-based dissymmetric bis-quaternary ammonium gemini surfactant has been synthesized. Its surface active properties at equilibrium in water at 25 C were determined. The inhibitive effect of the compound on Q235 steel in 1 M hydrochloric solution was investigated by the weight-loss method, potentiodynamic polarization, electrochemical impedance spectroscopy (EIS), scanning electron microscopy (SEM) analysis, and quantum chemical calculations. The results indicate that the compound has high surface properties and the inhibition efficiency (IE) increases with the increase in inhibitor concentration, which attain the maximum value around the CMC value. The imidazoline-based dissymmetric bis-quaternary ammonium acts as a mixed type inhibitor mainly inhibiting the cathodic processes and does not change the mechanism of either hydrogen evolution reaction or mild steel dissolution. The best IE is obtained at the immersion time of 144 h. The adsorption of the studied inhibitor on Q235 steel can be fitted to a Langmuir isotherm and the adsorption process is a spontaneous chemical adsorption. Quantum chemistry calculation results show that the imidazoline ring and heteroatoms of N, O, are the active sites of the inhibitors. (Copyright copyright 2012 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  3. Measurements of neutron-induced capture and fission reactions on $^{235}$ U: cross sections and ${\\alpha}$ ratios, photon strength functions and prompt ${\\gamma}$-ray from fission

    We propose to measure the neutron-induced capture cross section of the fissile isotope $^{235}$U using a fission tagging set-up. This new set-up has been tested successfully in 2010 and combines the n_TOF 4${\\pi}$ Total Absorption Calorimeter (TAC) with MicroMegas (MGAS) fission detectors. It has been proven that such a combination of detectors allows distinguishing with very good reliability the electromagnetic cascades from the capture reactions from dominant ${\\gamma}$-ray background coming from the fission reactions. The accurate discrimination of the fission background is the main challenge in the neutron capture cross section measurements of fissile isotopes. The main results from the measurement will be the associated capture cross section and ${\\alpha}$ ratio in the resolved (0.3-2250 eV) and unresolved (2.25-30 keV) resonance regions. According to the international benchmarks and as it is mentioned in the NEA High Priority Request List (HPRL), the 235U(n,${\\gamma}$) cross section is of utmost impo...

  4. On the energy balance and on dynamical aspects of proton induced fission of 235,236,238U by coincident spectroscopy of neutrons and fragments

    An improved experimental set up has been developed and applied to the measurement of neutrons in coincidence with fragments originating in proton induced fission of heavy nuclei. The reaction systems studied were p+235,236,238U for Ep = 12.84 MeV and Ep = 20.4 MeV. Data interpretation focuses on the following aspects: 1. Neutron multiplicities and average kinetic energies were studied as a function of fragment mass and total kinetic energies of these fragments. 2. The isotropic (i.e. the prefission plus scission) neutrons reveal a dependence of their multiplicities on the primary excitation energy E*CN that indicates a preference of the neutron over the fission exit channel with increasing E*CN not found in statistical model calculations. 3. A consistent analysis of all existing data for p+235,236,238U covering the interval 18 MeV ≤ E*CN ≤ 30 MeV in terms of neutron multiplicities and nuclear temperatures yields that pre- and postfission neutrons carry away comparable fractions of the additional energy ΔE*CN. 4. The total energy released in neutron and fragment emission is shown for p+238U (Ep = 20.4 MeV) to compare with the energy expected from mass tables for the fragmentations selected to within 2-3%. (orig.)

  5. Fuel cycle cost, reactor physics and fuel manufacturing considerations for Erbia-bearing PWR fuel with > 5 wt% U-235 content

    The efforts to reduce fuel cycle cost have driven LWR fuel close to the licensed limit in fuel fissile content, 5.0 wt% U-235 enrichment, and the acceptable duty on current Zr-based cladding. An increase in the fuel enrichment beyond the 5 wt% limit, while certainly possible, entails costly investment in infrastructure and licensing. As a possible way to offset some of these costs, the addition of small amounts of Erbia to the UO2 powder with >5 wt% U-235 has been proposed, so that its initial reactivity is reduced to that of licensed fuel and most modifications to the existing facilities and equipment could be avoided. This paper discusses the potentialities of such a fuel on the US market from a vendor's perspective. An analysis of the in-core behavior and fuel cycle performance of a typical 4-loop PWR with 18 and 24-month operating cycles has been conducted, with the aim of quantifying the potential economic advantage and other operational benefits of this concept. Subsequently, the implications on fuel manufacturing and storage are discussed. While this concept has certainly good potential, a compelling case for its short-term introduction as PWR fuel for the US market could not be determined. (authors)

  6. Effects of Fission Yield Data in the Calculation of Antineutrino Spectra for 235U (n ,fission) at Thermal and Fast Neutron Energies

    Sonzogni, A. A.; McCutchan, E. A.; Johnson, T. D.; Dimitriou, P.

    2016-04-01

    Fission yields form an integral part of the prediction of antineutrino spectra generated by nuclear reactors, but little attention has been paid to the quality and reliability of the data used in current calculations. Following a critical review of the thermal and fast ENDF/B-VII.1 235U 235 fission yields, deficiencies are identified and improved yields are obtained, based on corrections of erroneous yields, consistency between decay and fission yield data, and updated isomeric ratios. These corrected yields are used to calculate antineutrino spectra using the summation method. An anomalous value for the thermal fission yield of 86Ge generates an excess of antineutrinos at 5-7 MeV, a feature which is no longer present when the corrected yields are used. Thermal spectra calculated with two distinct fission yield libraries (corrected ENDF/B and JEFF) differ by up to 6% in the 0-7 MeV energy window, allowing for a basic estimate of the uncertainty involved in the fission yield component of summation calculations. Finally, the fast neutron antineutrino spectrum is calculated, which at the moment can only be obtained with the summation method and may be relevant for short baseline reactor experiments using highly enriched uranium fuel.

  7. Recent Experiments on the Beta Activity of Fission Products from the Thermal-Neutron Fission of U233, U235 and Pu239

    The build-up of beta-activity of fission products from the low-energy fission of U233 and U235 has been measured as a function of the lime t after starting the irradiation of the fissionable material with thermal neutrons. By differentiating the beta-activity divided by the constant fission product rate one obtains the mean beta-decay rate β(t) per fission as a function of the time t after fission. The uranium targets were mounted within a 4π proportional counter, coincident conversion electrons and γ-rays being thereby eliminated. The background of fast neutrons and γ-rays was strongly reduced by using a neutron beam tube with a liquid nitrogen-cooled bismuth single crystal filter. The fission product rate was measured with the same counter. The measurements cover the time interval from 0.01 s to 10 h. The results are compared with other experimental data and existing theories. The total number of beta-decays per fission was found to be 5.25 ± 0.2 and 5.93 ± 0.2 for U233 and U235 respectively compared with theoretical values of 5.27 and 6.10 respectively. (author)

  8. Characterisation of airborne uranium and thorium contamination in northern England through measurement of U, Th and 235U/238U in tree bark.

    Bellis, D J; Ma, R; McLeod, C W

    2001-02-01

    Samples of tree bark were collected from four locations in Northern England (a typical rural site, a coal-fired power station, a uranium (isotopic) enrichment plant and a nuclear fuel fabrication facility), to assess the nature and extent of airborne uranium and thorium contamination. The U and Th concentrations of bark were determined by inductively coupled plasma mass spectrometry after conventional nebulisation of bark digests, whilst measurement of 235U/238U isotopic ratio utilised high efficiency nebulisation. Uranium concentrations varied between and within the sites (range, 0.01-12 micrograms g-1), with maximum values recorded within 1 km of the nuclear fuel fabrication plant (Springfields). In comparison, the concentration of Th in bark was low (mean, 0.018 microgram g-1) at all sites with the exception of the area affected by coal combustion (0.2-0.8 microgram g-1). The U/Th ratio varied from 0.5 to 3900 compared with the average crustal ratio of 0.3. Low values (< 2) were recorded at the 'coal' and 'rural' sites whilst Capenhurst and Springfields showed high values indicating the relative magnitude of uranium elevation. Significant enrichment of the natural 235U/238U ratio (0.00725) was observed near the nuclear installations, in particular, the enrichment plant (Capenhurst). PMID:11354728

  9. Separation And Purification Of Radioiodine 131I by Means of wet Distillation Method From By-Product of U-235 Fission Produced 99Mo Process

    The production of 99Mo from 235U fission also produces radioiodine fraction as by product. The radioiodine fraction can be expected to be a complement for radioiodine 131I produced by neutron activation on TeO2 target. Separation and purification were therefore carried out from radioiodine fraction obtained from production process of 99Mo fission product. The radioiodine 131I fraction was separated and purified by means of wet distillation method that is often used for separating 131I from post-neutron activated TeO2. The quality control of the resulting products indicates that the resulting radioiodine 131I solution was suitable to be used for labelling or synthesis of 131I labelled compounds. Although the efficiencies of separation and purification were found to be low ranging between 25 to 37%, the result of the presented experiment generally affirm the consideration to exploit the 131I fission product for labelling or synthesis of 131I radiopharmaceuticals. Key word : distillation, radioiodine 131I , 235U

  10. PSR B0329+54: Substructure in the scatter-broadened image discovered with RadioAstron on baselines of up to 235,000 km

    Popov, M V; Bartel, N; Gwinn, C R; Johnson, M D; Joshi, B C; Kardashev, N S; Karuppusamy, R; Kovalev, Y Y; Kramer, M; Rudnitskii, A G; Safutdinov, E R; Shishov, V I; Smirnova, T V; Soglasnov, V A; Zensus, J A; Zhuravlev, V I

    2015-01-01

    We studied scattering properties of the pulsar PSR B0329+54 with a ground-space radio interferometer RadioAstron which included the 10-m Space Radio Telescope, the 110-m Green Bank Telescope, the 14x25-m Westerbork Synthesis Radio Telescope, and the 64-m Kalyazin Radio Telescope. The observations were performed at 324 MHz on baselines of up to 235,000 km in November 2012 and January 2014. At short ground-space baselines of less than about 20,000 km, the visibility amplitude decreases with the projected baseline length, providing a direct measurement of the diameter of the scattering disk of 4.7$\\pm$0.9 mas. The size of the diffraction spot near Earth is 15,000$\\pm$3,000 km. At longer baselines of up to 235,000 km, where no interferometric detection of the scattering disk would be expected, significant visibilities were observed with amplitudes scattered around a constant value. These detections result in a discovery of a substructure in the completely resolved scatter-broadened image of the pointlike source, ...

  11. R-matrix analysis of {sup 235}U neutron transmission and cross sections in the energy range 0 to 2.25 keV

    Leal, L.C.; Derrien, H.; Larson, N.M.; Wright, R.Q.

    1997-11-01

    This document describes a new R-matrix analysis of {sup 235}U cross section data in the energy range from 0 to 2,250 eV. The analysis was performed with the computer code SAMMY, that has recently been updated to permit, for the first time, inclusion of both differential and integral data within the analysis process. Fourteen differential data sets and six integral quantities were used in this evaluation: two measurements of fission plus capture, one of fission plus absorption, six of fission alone, two of transmission, and one of eta, plus standard values of thermal cross sections for fission, capture, and scattering, and of K1 and the Westcott g-factors for both fission and absorption. An excellent representation was obtained for the high-resolution transmission, fission, and capture cross-section data as well as for the integral quantities. The result is a single set of resonance parameters spanning the entire range up to 2,250 eV, a decided improvement over the present ENDF/VI evaluation, in which eleven discrete resonance parameter sets are required to cover that same energy range. This new evaluation is expected to greatly improve predictability of the criticality safety margins for nuclear systems in which {sup 235}U is present.

  12. Development of self-interrogation neutron resonance densitometry (SINRD) to measure U-235 and Pu-239 content in a PWR spent fuel assembly

    Lafleur, Adrienne M [Los Alamos National Laboratory; Charlton, William S [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory

    2009-01-01

    The use of Self-Interrogation Neutron Resonance Densitometry (SINRD) to measure the {sup 235}U and {sup 239}Pu content in a PWR spent fuel assembly was investigated via Monte Carlo N-Particle eXtended transport code (MCNPX) simulations. The sensitivity of SINRD is based on using the same fissile materials in the fission chambers as are present in the fuel because the effect of resonance absorption lines in the transmitted flux is amplified by the corresponding (n, f) reaction peaks in fission chamber. These simulations utilize the {sup 244}Cm spontaneous fission neutrons to self-interrogate the fuel pins. The amount of resonance absorption of these neutrons in the fuel can be measured using {sup 235}U and {sup 239}Pu fission chambers placed adjacent to the assembly. We used ratios of different fission chambers to reduce the sensitivity of the measurements to extraneous material present in fuel. The development of SINRD to measure the fissile content in spent fuel is of great importance to the improvement of nuclear safeguards and material accountability. Future work includes the use of this technique to measure the fissile content in FBR spent fuel and heavy metal product from reprocessing methods.

  13. The 235U(n,2n(gamma)) Yrast Partial Gamma-Ray Cross Sections: A Report on the 1998 -- 1999 GEANIE Data and Analysis Techniques

    Younes, W; Becker, J A; Bernstein, L A; Garret, P E; McGrath, C A; McNabb, D P; Nelson, R O; Devlin, M; Fotiades, N; Johns, G D

    2000-09-01

    Measurements of partial {sup 235}U(n,2n{gamma}) {gamma}-ray cross sections have been carried out as a function of incident neutron energy using the GEANIE spectrometer at LANSCE/WNR. The yields of {gamma} rays resulting from the population of discrete levels in the residual nucleus {sup 234}U have been measured at incident neutron energies in the 1-20-MeV range. These data provide, with the aid of nuclear reaction modeling, a measurement of the {sup 235}U(n,2n) reaction cross section and serve as a proof of principle of the y-ray technique for the parallel 23gPu(n,2n) measurement [l]. This paper presents the analysis of the {gamma}-ray data and the extraction of partial {gamma}-ray cross sections as a function of incident neutron energy. Uncertainties associated with the spectroscopic analysis of the data and validation of the results are discussed in detail.

  14. Measurements of the ratio fo 239Pu and 235U fission cross sections in the 0.024-7.4 MeV neutron energy range

    Aimed at improving the accuracy of available nuclear data 239Pu-to-235U fission cross section ratios were measured in a broad range of neutron energies. The measurements were taken in electrostatic accelerators with the Li(p,n)-,T(p,n)- and D(d,n) reactions used as neutron sources. The fission fragments were registered by a twin ionization chamber. The measured energy dependence curve of the fission cross section ratios was calibrated by means of an auxiliary technique employing glass detectors. The quantity ratio of the fissioning nuclei in 239Pu- and 235U layers was determined by two independent methods: from the alpha-activity in the layers and by taking measurements in the reactor thermal column. The total errors in the measured results makes up 1.4 to 1.5% for the most portion of the investigated neutron energy range, while rowing up to 1.7 to 2% in the range below 100 keV

  15. Fast evaluation of 235U/238U ratio in nuclear spent fuel safe guard by thermal ionization mass spectrometry by using refractory metal oxides

    A direct simple and fast method was established, to overcome the influence of low and high level impurities on the measurement of 235U/238U isotopic ratio in nuclear spent fuel safeguard by thermal ionization mass spectrometry (TIMS), by using refractory metal oxide. The addition of refractory metal oxides forming solution (RMOFS), in certain proportions alongside with the spent fuel solution on the sample filaments were found to be useful during the analysis of uranium isotopic ratio by TIMS. RMOFS (with oxide melting point exceeding 2,000 deg C), and particularly that of magnesium, were found to be very effective in improving the quality of the ion signal of 235U and 238U, when added without the need for prior purification. Solutions of chromium, cerium, thorium, and magnesium were investigated, to select the more convenient one, and it was found that magnesium was very useful to start with. The method was very simple, improve both the accuracy and precision of the collected data, reduce the time required to achieve steady uranium pilot signal, and hence the over all time of the analysis, regardless of the level of impurities present. (author)

  16. Standard practice for the determination of 237Np, 232Th, 235U and 238U in urine by inductively coupled plasma-Mass spectrometry (ICP-MS) and gamma ray spectrometry.

    American Society for Testing and Materials. Philadelphia

    2005-01-01

    1.1 This practice covers the separation and preconcentration of neptunium-237 (237Np), thorium-232 (232Th), uranium-235 (235U) and uranium-238 (238U) from urine followed by quantitation using ICP-MS. 1.2 This practice can be used to support routine bioassay programs. The minimum detectable concentrations (MDC) for this method, taking the preconcentration factor into account, are approximately 1E-2Bq for 237Np (0.38ng), 2E-6Bq for 232Th (0.50ng), 4E-5Bq for 235U (0.50ng) and 6E-6Bq for 238U (0.48ng). 1.3 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  17. Estimation of uranium and cobalt-60 distribution coefficients and uranium-235 enrichment at the Combustion Engineering Company site in Windsor, Connecticut

    Site-specific distribution coefficients for uranium isotopes and cobalt-60 (Co-60) and the fraction of uranium-235 (U-235) enrichment by mass were estimated for environmental samples collected from the Combustion Engineering Company site in Windsor, CT. This site has been identified for remedial action under the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program. The authority of DOE at the Combustion Engineering site is limited to (1) Building 3; (2) other activities or areas associated exclusively with Building 3 (such as sewer lines); or (3) contamination that is exclusively highly enriched uranium. In this study, 16 samples were collected from the Combustion Engineering site, including 8 soil, 4 sediment, 3 water, and 1 water plus sludge sample. These samples were analyzed for isotopic uranium by alpha spectrometry and for Co-60 by gamma spectrometry. The site-specific distribution coefficient for each isotope was estimated as the ratio of extractable radionuclide activity in the solid phase to the activity in the contact solution following a 19-day equilibration. The uranium activity measurements indicate that uranium-234 (U-234) and uranium-238 (U-238) were in secular equilibrium in two soil samples and that soil and sediment samples collected from other sampling locations had higher U-234 activity than U-238 activity in both the solid and solution phases. The site-specific distribution coefficient (Kd) ranged from 82 to 44,600 mL/g for U-238 and from 102 to 65,900 mL/g for U-234. Calculation of U-235 enrichment by mass indicated that four soil samples had values greater than 0.20; these values were 0.37, 0.38, 0.46, and 0.68. Cobalt-60 activity was detected in only three sediment samples. The measured Co-60 activity in the solid phase ranged from 0.15 to 0.45 pCi/g and that in the water phase of all three samples combined was 4 pCi/L. The Kd value for Co-60 in the site brook sediment was calculated to be 70 mL/g

  18. Delayed neutron and delayed photon characteristics from photofission of 232Th, 235,238U, and 237Np with endpoint Bremsstrahlung photons in the giant dipole resonance region

    A renewed interest in photonuclear reactions was stimulated by applications as radioactive ion beam production, irradiation stations by high energy photons, shielding of electron accelerators, etc. Today, a particular attention is paid to the non-destructive characterization of waste barrels and the detection of nuclear materials, both based on photofission process and the associated delayed neutron (DN) and delayed photon (DP) emissions. The need of accurate and complete data for DN and DP yields and time characteristics of actinides was the motivation for an experimental campaign, started in 2004. In this paper, the experimental setup and the data analysis method will be presented and the modeling work will be described. Experimental results for DN and DP characteristics will be compared to calculations in the case of photofission of 232Th, 235,238U, and 237Np. (authors)

  19. Investigation of the prompt neutron emission mechanism in low energy fission of 235,233U(nth, f and 252Cf(sf

    Val’ski G.V.

    2010-10-01

    Full Text Available A series of experiments has been performed to measure prompt neutron angular and energy distributions from thermal neutron-induced fission of 235,233U in correlation with the fission fragments. These distributions have been analyzed with the assumption of neutron isotropic emission from accelerated fission fragments. The performed analysis demonstrates that all obtained results can be described within 5% accuracy using this assumption. This discrepancy is approximately constant and doesn’t depend on fragment mass and the total kinetic energy (TKE. Some minor peculiarities of angular distribution may be interpreted as a result of anisotropy of the fission neutron angular distribution in the fragment center-of-mass system.

  20. Standard specification for uranium oxides with a 235U content of less than 5 % for dissolution prior to conversion to nuclear-grade uranium dioxide

    American Society for Testing and Materials. Philadelphia

    2005-01-01

    1.1 This specification covers uranium oxides, including processed byproducts or scrap material (powder, pellets, or pieces), that are intended for dissolution into uranyl nitrate solution meeting the requirements of Specification C788 prior to conversion into nuclear grade UO2 powder with a 235U content of less than 5 %. This specification defines the impurity and uranium isotope limits for such urania powders that are to be dissolved prior to processing to nuclear grade UO2 as defined in Specification C753. 1.2 This specification provides the nuclear industry with a general standard for such uranium oxide powders. It recognizes the diversity of conversion processes and the processes to which such powders are subsequently to be subjected (for instance, by solvent extraction). It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between the buyer and seller. 1.3 The scope of this specification does not comprehensively cover all provisions for prevent...