WorldWideScience

Sample records for actinium 233

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

    International Nuclear Information System (INIS)

    available at Fermi National Accelerator Laboratory. Targets will be processed at Argonne National Laboratory to separate and purify the actinium-225 that will subsequently be transferred to NorthStar laboratory facilities for product quality testing and comparison to the product quality of ORNL produced actinium-225, which is currently the industry standard. The test irradiations at FNAL will produce 1-20 mCi per day which is more than sufficient for quantitative evaluation of the proposed production process. The beneficial outcome of this effort will be a new production route for actinium-225 that does not use or require any uranium-233 materials owned by DOE or use any radium-226 as an irradiation target but can supply the medical community's needs for actinium-225 now and in the future.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-12-30

    V protons available at Fermi National Accelerator Laboratory. Targets will be processed at Argonne National Laboratory to separate and purify the actinium-225 that will subsequently be transferred to NorthStar laboratory facilities for product quality testing and comparison to the product quality of ORNL produced actinium-225, which is currently the industry standard. The test irradiations at FNAL will produce 1-20 mCi per day which is more than sufficient for quantitative evaluation of the proposed production process. The beneficial outcome of this effort will be a new production route for actinium-225 that does not use or require any uranium-233 materials owned by DOE or use any radium-226 as an irradiation target but can supply the medical community's needs for actinium-225 now and in the future.

  3. Spectroscopic and computational investigation of actinium coordination chemistry

    Science.gov (United States)

    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.

    2016-08-01

    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, AcIII 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 AcIII and AmIII in HCl solutions indicate AcIII coordinates more inner-sphere Cl1- ligands (3.2+/-1.1) than AmIII (0.8+/-0.3). These results imply diverse reactivity for the +3 actinides and highlight the unexpected and unique AcIII chemical behaviour.

  4. Separation of Actinium 227 from the uranium minerals

    International Nuclear Information System (INIS)

    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)

  5. Spectroscopic and computational investigation of actinium coordination chemistry

    Science.gov (United States)

    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, AcIII 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 AcIII and AmIII in HCl solutions indicate AcIII coordinates more inner-sphere Cl1– ligands (3.2±1.1) than AmIII (0.8±0.3). These results imply diverse reactivity for the +3 actinides and highlight the unexpected and unique AcIII chemical behaviour. PMID:27531582

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

    CERN Document Server

    Fry, C

    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.

  7. Spectroscopic and computational investigation of actinium coordination chemistry.

    Science.gov (United States)

    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

  8. Thermal Stabilization of 233UO2, 233UO3, and 233U3O8

    International Nuclear Information System (INIS)

    This report identifies an appropriate thermal stabilization temperature for 233U oxides. The temperature is chosen principally on the basis of eliminating moisture and other residual volatiles. This report supports the U. S. Department of Energy (DOE) Standard for safe storage of 233U (DOE 2000), written as part of the response to Recommendation 97-1 of the Defense Nuclear Facilities Safety Board (DNFSB), addressing safe storage of 233U

  9. Excited levels of Pa-233; Niveles excitados del Pa-233

    Energy Technology Data Exchange (ETDEWEB)

    Vara Cuadrado, J. M.

    1969-07-01

    A study of Pa-233 excited levels from the alpha decay of Np-237 and from beta decay of Th-233 has been performed. The alpha decay spectrum was measured with a semiconductor spectrometer of 18 keV effective resolution (FWHM). Over 13 new lines were identified. The gamma ray spectra of Np-237 and Th-233 were obtained with a Ge-Li detector low and medium range energy lines, and with Si-Li detector for the low energy region. A continuous purification method of Np-237 from its comparatively short-lived daughter Pa-233 was applied. A high number of new lines were identified in both spectra. The gamma-gamma coincidence spectra were obtained with INa(T{sub 1}) detectors. (Author) 54 refs.

  10. Disposition Options for Uranium-233

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE) Fissile Materials Disposition Program (MD), in support of the U.S. arms-control and nonproliferation policies, has initiated a program to disposition surplus weapons-usable fissile material by making it inaccessible and unattractive for use in nuclear weapons. Weapons-usable fissile materials include plutonium, high-enriched uranium (HEU), and uranium-233 (sup 233)U. In support of this program, Oak Ridge National Laboratory led DOE's contractor efforts to identify and characterize options for the long-term storage and disposal of excess (sup 233)U. Five storage and 17 disposal options were identified and are described herein

  11. Excited levels of Pa-233

    International Nuclear Information System (INIS)

    A study of Pa-233 excited levels from the alpha decay of Np-237 and from beta decay of Th-233 has been performed. The alpha decay spectrum was measured with a semiconductor spectrometer of 18 keV effective resolution (FWHM). Over 13 new lines were identified. The gamma ray spectra of Np-237 and Th-233 were obtained with a Ge-Li detector low and medium range energy lines, and with Si-Li detector for the low energy region. A continuous purification method of Np-237 from its comparatively short-lived daughter Pa-233 was applied. A high number of new lines were identified in both spectra. The gamma-gamma coincidence spectra were obtained with INa(T1) detectors. (Author) 54 refs

  12. 8 CFR 233.1 - Contracts.

    Science.gov (United States)

    2010-01-01

    ... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Contracts. 233.1 Section 233.1 Aliens and Nationality DEPARTMENT OF HOMELAND SECURITY IMMIGRATION REGULATIONS CONTRACTS WITH TRANSPORTATION LINES § 233.1 Contracts. The contracts with transportation lines referred to in section 233(c) of the Act may...

  13. 7 CFR 23.3 - Coordination.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 1 2010-01-01 2010-01-01 false Coordination. 23.3 Section 23.3 Agriculture Office of the Secretary of Agriculture STATE AND REGIONAL ANNUAL PLANS OF WORK State Program § 23.3 Coordination... designate an official who will be responsible for the overall coordination of the authorized programs...

  14. 15 CFR 23.3 - Plan.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 1 2010-01-01 2010-01-01 false Plan. 23.3 Section 23.3 Commerce and... MISSING CHILDREN § 23.3 Plan. (a) The Department of Commerce will supplement and expand the national... biannual meetings of departmental representatives to discuss the current plan and recommendations...

  15. 14 CFR 23.3 - Airplane categories.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Airplane categories. 23.3 Section 23.3... STANDARDS: NORMAL, UTILITY, ACROBATIC, AND COMMUTER CATEGORY AIRPLANES General § 23.3 Airplane categories. (a) The normal category is limited to airplanes that have a seating configuration, excluding...

  16. 49 CFR 233.13 - Criminal penalty.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Criminal penalty. 233.13 Section 233.13 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL RAILROAD ADMINISTRATION, DEPARTMENT OF TRANSPORTATION SIGNAL SYSTEMS REPORTING REQUIREMENTS § 233.13 Criminal penalty....

  17. 7 CFR 58.233 - Skim milk.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 3 2010-01-01 2010-01-01 false Skim milk. 58.233 Section 58.233 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Standards... Materials § 58.233 Skim milk. The skim milk shall be separated from whole milk meeting the requirements...

  18. 45 CFR 233.70 - Blindness.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 2 2010-10-01 2010-10-01 false Blindness. 233.70 Section 233.70 Public Welfare... FINANCIAL ASSISTANCE PROGRAMS § 233.70 Blindness. (a) State plan requirements. A State plan under title X or XVI of the Social Security Act must: (1) Contain a definition of blindness in terms of...

  19. 22 CFR 23.3 - Refunds.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Refunds. 23.3 Section 23.3 Foreign Relations DEPARTMENT OF STATE FEES AND FUNDS FINANCE AND ACCOUNTING § 23.3 Refunds. (a) Rectifications and readjustments. See § 22.6 of this chapter for outline of circumstances under which fees which have...

  20. 12 CFR 23.3 - Lease requirements.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 1 2010-01-01 2010-01-01 false Lease requirements. 23.3 Section 23.3 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY LEASING General Provisions § 23.3 Lease... connection with leasing that property, and may engage in activities incidental thereto, if the...

  1. 40 CFR 233.11 - Program description.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Program description. 233.11 Section... PROGRAM REGULATIONS Program Approval § 233.11 Program description. The program description as required under § 233.10 shall include: (a) A description of the scope and structure of the State's program....

  2. 12 CFR 233.4 - Exemptions.

    Science.gov (United States)

    2010-01-01

    ... FUNDING OF UNLAWFUL INTERNET GAMBLING (REGULATION GG) § 233.4 Exemptions. (a) Automated clearing house... business are exempt from this regulation's requirements for establishing written policies and...

  3. Dicty_cDB: SLD233 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available SL (Link to library) SLD233 (Link to dictyBase) sld233 - - Contig-U15622-1 SLD233P ...(Link to Original site) SLD233F 296 SLD233Z 383 SLD233P 679 - - Show SLD233 Library SL (Link to library) Clone ID SLD2...33 (Link to dictyBase) Atlas ID sld233 NBRP ID - dictyBase ID - Link to Contig Contig-U15622-1 Ori...ginal site URL http://dictycdb.biol.tsukuba.ac.jp/CSM/SL/SLD2-B/SLD233Q.Seq.d/ Re...presentative seq. ID SLD233P (Link to Original site) Representative DNA sequence >SLD233 (SLD233Q) /CSM/SL/SLD2-B/SLD2

  4. Dicty_cDB: SLB233 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available SL (Link to library) SLB233 (Link to dictyBase) slb233 - - Contig-U16290-1 SLB233P ...(Link to Original site) SLB233F 697 SLB233Z 631 SLB233P 1328 - - Show SLB233 Library SL (Link to library) Clone ID SLB...233 (Link to dictyBase) Atlas ID slb233 NBRP ID - dictyBase ID - Link to Contig Contig-U16290-1 Or...iginal site URL http://dictycdb.biol.tsukuba.ac.jp/CSM/SL/SLB2-B/SLB233Q.Seq.d/ R...epresentative seq. ID SLB233P (Link to Original site) Representative DNA sequence >SLB233 (SLB233Q) /CSM/SL/SLB2-B/SLB

  5. Dicty_cDB: SSC233 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available SS (Link to library) SSC233 (Link to dictyBase) - - - Contig-U09430-1 SSC233Z (Link... to Original site) - - SSC233Z 429 - - - - Show SSC233 Library SS (Link to library) Clone ID SSC233 (Link to...ycdb.biol.tsukuba.ac.jp/CSM/SS/SSC2-B/SSC233Q.Seq.d/ Representative seq. ID SSC23...3Z (Link to Original site) Representative DNA sequence >SSC233 (SSC233Q) /CSM/SS/SSC2-B/SSC233Q.Seq.d/ XXXXX...e E Sequences producing significant alignments: (bits) Value SSC233 (SSC233Q) /CSM/SS/SSC2-B/SSC233Q.Seq.d/

  6. 45 CFR 233.80 - Disability.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 2 2010-10-01 2010-10-01 false Disability. 233.80 Section 233.80 Public Welfare Regulations Relating to Public Welfare OFFICE OF FAMILY ASSISTANCE (ASSISTANCE PROGRAMS), ADMINISTRATION FOR... or XVI of the Social Security Act must: (1) Contain a definition of permanently and totally...

  7. 48 CFR 233.215 - Contract clause.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Contract clause. 233.215....215 Contract clause. Use Alternate I of the clause at FAR 52.233-1, Disputes, when— (1) The... (v) Tracked combat vehicles (vi) Related electronic systems; (2) The contracting officer...

  8. 25 CFR 23.3 - Policy.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false Policy. 23.3 Section 23.3 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR HUMAN SERVICES INDIAN CHILD WELFARE ACT Purpose, Definitions, and... unique values of Indian culture and promote the stability and security of Indian children,...

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

    International Nuclear Information System (INIS)

    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

  10. Workshop on Preserving High Purity Uranium-233

    Energy Technology Data Exchange (ETDEWEB)

    Krichinsky, Alan M [ORNL; Giaquinto, Joseph [ORNL; Canaan, R Douglas {Doug} [ORNL

    2016-01-01

    A workshop was held on at the MARC X conference to provide a forum for the scientific community to communicate needs for high-purity 233U and its by-products in order to preserve critical items otherwise slated for downblending and disposal. Currently, only a small portion of the U.S. holdings of separated 233U is being preserved. However, many additional kilograms of 233U (>97% pure) still are destined to be downblended which will permanently destroy their potential value for many other applications. It is not likely that this material will ever be replaced due to a lack of operating production capability. Summaries of information conveyed at the workshop and feedback obtained from the scientific community are presented herein.

  11. Preserving Ultra-Pure Uranium-233

    Energy Technology Data Exchange (ETDEWEB)

    Krichinsky, Alan M [ORNL; Goldberg, Dr. Steven A. [DOE SC - Chicago Office; Hutcheon, Dr. Ian D. [Lawrence Livermore National Laboratory (LLNL)

    2011-10-01

    Uranium-233 ({sup 233}U) is a synthetic isotope of uranium formed under reactor conditions during neutron capture by natural thorium ({sup 232}Th). At high purities, this synthetic isotope serves as a crucial reference material for accurately quantifying and characterizing uranium-bearing materials assays and isotopic distributions for domestic and international nuclear safeguards. Separated, high purity {sup 233}U is stored in vaults at Oak Ridge National Laboratory (ORNL). These materials represent a broad spectrum of {sup 233}U from the standpoint of isotopic purity - the purest being crucial for precise analyses in safeguarding uranium. All {sup 233}U at ORNL is currently scheduled to be disposed of by down-blending with depleted uranium beginning in 2015. This will reduce safety concerns and security costs associated with storage. Down-blending this material will permanently destroy its potential value as a certified reference material for use in uranium analyses. Furthermore, no credible options exist for replacing {sup 233}U due to the lack of operating production capability and the high cost of restarting currently shut down capabilities. A study was commissioned to determine the need for preserving high-purity {sup 233}U. This study looked at the current supply and the historical and continuing domestic need for this crucial isotope. It examined the gap in supplies and uses to meet domestic needs and extrapolated them in the context of international safeguards and security activities - superimposed on the recognition that existing supplies are being depleted while candidate replacement material is being prepared for disposal. This study found that the total worldwide need by this projection is at least 850 g of certified {sup 233}U reference material over the next 50 years. This amount also includes a strategic reserve. To meet this need, 18 individual items totaling 959 g of {sup 233}U were identified as candidates for establishing a lasting supply of

  12. 28 CFR 23.3 - Applicability.

    Science.gov (United States)

    2010-07-01

    ... Administration DEPARTMENT OF JUSTICE CRIMINAL INTELLIGENCE SYSTEMS OPERATING POLICIES § 23.3 Applicability. (a) These policy standards are applicable to all criminal intelligence systems operating through support...-647). (b) As used in these policies: (1) Criminal Intelligence System or Intelligence System means...

  13. 233-S plutonium concentration facility hazards assessment

    International Nuclear Information System (INIS)

    This document establishes the technical basis in support of Emergency Planning activities for the 233-S Plutonium Concentration Facility on the Hanford Site. The document represents an acceptable interpretation of the implementing guidance document for DOE ORDER 5500.3A. Through this document, the technical basis for the development of facility specific Emergency Action Levels and the Emergency Planning Zone is demonstrated

  14. Star formation in the S233 region

    CERN Document Server

    Ladeyschikov, D A; Parfenov, S Yu; Alexeeva, S A; Bieging, J H

    2015-01-01

    The main objective of this paper is to study the possibility of triggered star formation on the border of the HII region S233, which is formed by a B-star. Using high-resolution spectra we determine the spectral class of the ionizing star as B0.5 V and the radial velocity of the star to be -17.5(1.4) km/s. This value is consistent with the velocity of gas in a wide field across the S233 region, suggesting that the ionizing star was formed from a parent cloud belonging to the S233 region. By studying spatial-kinematic structure of the molecular cloud in the S233 region, we detected an isolated clump of gas producing CO emission red-shifted relative to the parent cloud. In the UKIDSS and WISE images, the clump of gas coincides with the infrared source containing a compact object and bright-rimmed structure. The bright-rimmed structure is perpendicular to the direction of the ionizing star. The compact source coincides in position with IRAS source 05351+3549. All these features indicate a possibility of triggeri...

  15. Dicty_cDB: CHR233 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available CH (Link to library) CHR233 (Link to dictyBase) - - - Contig-U16471-1 - (Link to Original site) - - CHR...233Z 789 - - - - Show CHR233 Library CH (Link to library) Clone ID CHR233 (Link to dicty...iol.tsukuba.ac.jp/CSM/CH/CHR2-B/CHR233Q.Seq.d/ Representative seq. ID - (Link to ...Original site) Representative DNA sequence >CHR233 (CHR233Q) /CSM/CH/CHR2-B/CHR233Q.Seq.d/ XXXXXXXXXXTATATGA...DNA Score E Sequences producing significant alignments: (bits) Value SHB457 (SHB457Q) /CSM/SH/SHB4-C/SHB457Q.Seq.d/ 747 0.0 CHR

  16. 40 CFR 233.4 - Conflict of interest.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Conflict of interest. 233.4 Section 233.4 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) OCEAN DUMPING 404 STATE PROGRAM REGULATIONS General § 233.4 Conflict of interest. Any public officer or employee who has a...

  17. 45 CFR 233.52 - Overpayment to aliens.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 2 2010-10-01 2010-10-01 false Overpayment to aliens. 233.52 Section 233.52... ELIGIBILITY IN FINANCIAL ASSISTANCE PROGRAMS § 233.52 Overpayment to aliens. A State Plan under title IV-A of the Social Security Act, shall provide that: (a) Any sponsor of an alien and the alien shall...

  18. 17 CFR 256.233 - Notes payable to associate companies.

    Science.gov (United States)

    2010-04-01

    ... companies. 256.233 Section 256.233 Commodity and Securities Exchanges SECURITIES AND EXCHANGE COMMISSION (CONTINUED) UNIFORM SYSTEM OF ACCOUNTS FOR MUTUAL SERVICE COMPANIES AND SUBSIDIARY SERVICE COMPANIES, PUBLIC UTILITY HOLDING COMPANY ACT OF 1935 7. Current and Accrued Liabilities § 256.233 Notes payable...

  19. 27 CFR 24.233 - Addition of spirits to wine.

    Science.gov (United States)

    2010-04-01

    ... wine. 24.233 Section 24.233 Alcohol, Tobacco Products and Firearms ALCOHOL AND TOBACCO TAX AND TRADE BUREAU, DEPARTMENT OF THE TREASURY LIQUORS WINE Spirits § 24.233 Addition of spirits to wine. (a) Prior to the addition of spirits. Wine will be placed in tanks approved for the addition of spirits....

  20. Thorium and actinium polyphosphonate compounds as bone-seeking alpha particle-emitting agents.

    Science.gov (United States)

    Henriksen, Gjermund; Bruland, Oyvind S; Larsen, Roy H

    2004-01-01

    The present study explores the use of alpha-particle-emitting, bone-seeking agents as candidates for targeted radiotherapy. Actinium and thorium 1,4,7,10 tetraazacyclododecane N,N',N'',N''' 1,4,7,10-tetra(methylene) phosphonic acid (DOTMP) and thorium-diethylene triamine N,N',N'' penta(methylene) phosphonic acid (DTMP) were prepared and their biodistribution evaluated in conventional Balb/C mice at four hours after injection. All three bone-seeking agents showed a high uptake in bone and a low uptake in soft tissues. Among the soft tissue organs, only kidney had a relatively high uptake. The femur/kidney ratios for 227Th-DTMP, 228-Ac-DOTMP and 227Th-DOTMP were 14.2, 7.6 and 6.0, respectively. A higher liver uptake of 228Ac-DOTMP was seen than for 227Th-DTMP and 227Th-DOTMP. This suggests that some demetallation of the 228Ac-DOTMP complex had occurred. The results indicate that 225Ac-DOTMP, 227Th-DOTMP and 227Th-DTMP have promising properties as potential therapeutic bone-seeking agents.

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

    Science.gov (United States)

    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.

  2. Uranium-233 analysis of biological samples

    International Nuclear Information System (INIS)

    Two liquid scintillation techniques were compared for 233U analysis: a two-phase extraction system (D2EHPA) developed by Keough and Powers, 1970, for Pu analysis; and a single-phase emulsion system (TT21) that holds the total sample in suspension with the scintillator. The first system (D2EHPA) was superior in reducing background (two- to threefold) and in accommodating a larger sample volume (fivefold). Samples containing > 50 mg/ml of slats were not extracted quantitatively by D2EHPA

  3. Evaluation of resonance parameters of U-233

    International Nuclear Information System (INIS)

    Compilation of nuclear data is in progress in Japan, and the second edition of Japanese Evaluated Nuclear Data Library (JENDL-2) will be published. The evaluation of the resonance parameters of U-233, which will be included in JENDL-2, has been made. The measured values of the resonance parameters after the publication of BNL-325 (second edition) were collected, and searched by using CINDA-78. The data by Blons, Kolar, Ryabov, and Bergen were used for the present evaluation. Complete set of the data was made for each measurement. Fission and capture areas integrated over energy intervals were obtained. The total, fission and capture cross-sections of U-233 were calculated from the various sets of complete resonance parameters, and shown in figures. The calculated values of total, fission and capture cross-sections based on the parameters by Blons were compared with the measured values. Correction of the resonance parameters with poor reproducibility was able to be made with the NDES system by Nakagawa. The final parameters which will be included in JENDL are shown in tables. (Kato, T.)

  4. 40 CFR 86.233-94-86.234-94 - [Reserved

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 18 2010-07-01 2010-07-01 false 86.233-94-86.234-94 Section 86.233-94-86.234-94 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS... 1994 and Later Model Year Gasoline-Fueled New Light-Duty Vehicles, New Light-Duty Trucks and New...

  5. 40 CFR 233.12 - Attorney General's statement.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Attorney General's statement. 233.12... STATE PROGRAM REGULATIONS Program Approval § 233.12 Attorney General's statement. (a) Any State that seeks to administer a program under this part shall submit a statement from the State Attorney...

  6. Extraction of 229Th From 233U Solution

    Institute of Scientific and Technical Information of China (English)

    XIAO; Guo-ping; ZHAO; Li-fei

    2013-01-01

    A two-step separation procedure for preparation of 229Th tracer from 233U was developed using CL-TBP and TEVA extraction chromatography.The decontamination factor of uranium from thorium is larger than 4.6×106.After separation,the content of 233U in uranium fraction was measured by ID-ICP-MS,

  7. 40 CFR 233.61 - Determination of Tribal eligibility.

    Science.gov (United States)

    2010-07-01

    .... 233.61 Section 233.61 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) OCEAN..., such as, but not limited to, the exercise of police powers affecting (or relating to) the health... environmental or public health programs administered by the Tribal governing body, and a copy of related...

  8. 29 CFR 1952.233 - Compliance staffing benchmarks.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Compliance staffing benchmarks. 1952.233 Section 1952.233... Compliance staffing benchmarks. Under the terms of the 1978 Court Order in AFL-CIO v. Marshall compliance staffing levels (benchmarks) necessary for a “fully effective” enforcement program were required to...

  9. 40 CFR 233.30 - Application for a permit.

    Science.gov (United States)

    2010-07-01

    ... level of environmental degradation. Note: EPA encourages States to provide permit applicants guidance... Section 233.30 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) OCEAN DUMPING 404... assist in the evaluation of the application. Such additional information may include environmental...

  10. Feasibility to produce uranium-233 from thorium in PHWR

    International Nuclear Information System (INIS)

    Uranium-233 is a fissile isotope of uranium that is bred from thorium-232 as part of the thorium fuel cycle. It is used as fuel in nuclear reactor. 233U is produced by irradiating thorium in fast reactor or thermal reactor. In this paper feasibility to produce 233U by irradiation of fuel bundles of thorium mixed with plutonium or irradiation of thorium bundles along with slightly enriched Uranium bundles in 220 MWe and 540 MWe PHWRs has been studied. Study shows that production of 233U is possible by irradiating few fuel bundles of PuTh or Thorium bundles along with SEU bundles without affecting the power operation and the safety related parameters. (author)

  11. 12 CFR 233.5 - Policies and procedures required.

    Science.gov (United States)

    2010-01-01

    ... SYSTEM PROHIBITION ON FUNDING OF UNLAWFUL INTERNET GAMBLING (REGULATION GG) § 233.5 Policies and... otherwise refuses to honor a transaction, shall not be liable to any party for such action if— (1)...

  12. 39 CFR 233.4 - Withdrawal of mail privileges.

    Science.gov (United States)

    2010-07-01

    ... § 233.4 Withdrawal of mail privileges. (a) False representation and lottery orders—(1) Issuance... by means of a false-representation or lottery scheme. Such orders provide for return of mail...

  13. 12 CFR 233.3 - Designated payment systems.

    Science.gov (United States)

    2010-01-01

    ... PROHIBITION ON FUNDING OF UNLAWFUL INTERNET GAMBLING (REGULATION GG) § 233.3 Designated payment systems. The... remotely from a location other than a physical office of the money transmitting business; and (e)...

  14. Repository criticality control for {sup 233}U using depleted uranium

    Energy Technology Data Exchange (ETDEWEB)

    Forsberg, C.W.; Elam, K.R.; Hopper, C.M.

    1999-07-01

    The US is evaluating methods for the disposition of excess weapons-usable {sup 233}U, including disposal in a repository. Isotopic dilution studies were undertaken to determine how much depleted uranium (DU) would need to be added to the {sup 233}U to minimize the potential for nuclear criticality in a repository. Numerical evaluations were conducted to determine the nuclear equivalence of different {sup 235}U enrichments to {sup 233}U isotopically diluted with DU containing 0.2 wt% {sup 235}U. A homogeneous system of silicon dioxide, water, {sup 233}U, and DU, in which the ratio of each component was varied, was used to determine the conditions of maximum nuclear reactivity. In terms of preventing nuclear criticality in a repository, there are three important limits from these calculations. 1. Criticality safe in any nonnuclear system: The required isotopic dilution to ensure criticality under all conditions, except in the presence of man-made nuclear materials (beryllium, etc.), is {approximately}1.0% {sup 235}U in {sup 238}U. The equivalent {sup 233}U enrichment level is 0.53 wt% {sup 233}U in DU. 2. Critically safe in natural systems: The lowest {sup 235}U enrichment found in a natural reactor at shutdown was {approximately}1.3%. French studies, based on the characteristics of natural uranium ore bodies, indicate that a minimum enrichment of {approximately}1.28% {sup 235}U is required for criticality. These data suggest that nuclear criticality from migrating uranium is not realistic unless the {sup 235}U enrichments exceed {approximately}1.3%, which is a result that is equivalent to 0.72% {sup 233}U in DU. 3. Criticality safety equivalent to light water reactor (LWR) spent nuclear fuel (SNF): The {sup 233}U can be diluted with DU so that the uranium criticality characteristics match SNF uranium. Whatever repository criticality controls are used for SNF can then be used for {sup 233}U. The average LWR SNF assay (after decay of plutonium isotopes to uranium

  15. Repository criticality control for 233U using depleted uranium

    International Nuclear Information System (INIS)

    The US is evaluating methods for the disposition of excess weapons-usable 233U, including disposal in a repository. Isotopic dilution studies were undertaken to determine how much depleted uranium (DU) would need to be added to the 233U to minimize the potential for nuclear criticality in a repository. Numerical evaluations were conducted to determine the nuclear equivalence of different 235U enrichments to 233U isotopically diluted with DU containing 0.2 wt% 235U. A homogeneous system of silicon dioxide, water, 233U, and DU, in which the ratio of each component was varied, was used to determine the conditions of maximum nuclear reactivity. In terms of preventing nuclear criticality in a repository, there are three important limits from these calculations. 1. Criticality safe in any nonnuclear system: The required isotopic dilution to ensure criticality under all conditions, except in the presence of man-made nuclear materials (beryllium, etc.), is ≅1.0% 235U in 238U. The equivalent 233U enrichment level is 0.53 wt% 233U in DU. 2. Critically safe in natural systems: The lowest 235U enrichment found in a natural reactor at shutdown was approximately1.3%. French studies, based on the characteristics of natural uranium ore bodies, indicate that a minimum enrichment of approximately1.28% 235U is required for criticality. These data suggest that nuclear criticality from migrating uranium is not realistic unless the 235U enrichments exceed approximately1.3%, which is a result that is equivalent to 0.72% 233U in DU. 3. Criticality safety equivalent to light water reactor (LWR) spent nuclear fuel (SNF): The 233U can be diluted with DU so that the uranium criticality characteristics match SNF uranium. Whatever repository criticality controls are used for SNF can then be used for 233U. The average LWR SNF assay (after decay of plutonium isotopes to uranium isotopes) is 1.5% 235U equivalent in 238U. This is equivalent to diluting 233U to 0.81% in DU

  16. Experimental 233U nondestructive assay with a random driver

    International Nuclear Information System (INIS)

    Nondestructive assay (NDA) of 233U in quantities up to 15 grams containing 7 ppM 232U age 2 years was investigated with a random driver. A passive singles counting technique showed a reproducibility within 0.2% at the 95% confidence level. This technique would be applicable throughout a process in which all of the 233U had the same 232U content at the same age. Where the 232U content varies, determination of 233U fissile content would require active NDA. Active coincidence counting utilizing a 238Pu, Li neutron source and a plastic scintillator detector system showed a reproducibility limit within 15% at the 95% confidence limit. The active technique was found to be very dependent on the detector system resolving time in order to make proper random coincidence corrections associated with the high gamma activity from the 232U decay chain

  17. 16 CFR 233.5 - Miscellaneous price comparisons.

    Science.gov (United States)

    2010-01-01

    ... DECEPTIVE PRICING § 233.5 Miscellaneous price comparisons. The practices covered in the provisions set forth above represent the most frequently employed forms of bargain advertising. However, there are many... principles. For example, retailers should not advertise a retail price as a “wholesale” price. They...

  18. 16 CFR 233.1 - Former price comparisons.

    Science.gov (United States)

    2010-01-01

    ... DECEPTIVE PRICING § 233.1 Former price comparisons. (a) One of the most commonly used forms of bargain advertising is to offer a reduction from the advertiser's own former price for an article. If the former price... a reasonably substantial period of time, it provides a legitimate basis for the advertising of...

  19. 7 CFR 1209.233 - Regional caucus chairpersons.

    Science.gov (United States)

    2010-01-01

    ... chairpersons will coordinate the entire nomination process. In conducting the nominations process, each... PROMOTION, RESEARCH, AND CONSUMER INFORMATION ORDER Rules and Regulations Nomination Procedures § 1209.233..., and voting for importer nominees is limited to importers; and (2) Producer candidates for...

  20. 48 CFR 1852.233-70 - Protests to NASA.

    Science.gov (United States)

    2010-10-01

    ... 1852.233-70 Protests to NASA. As prescribed in 1833.106-70, insert the following provision: Protests to NASA (OCT 2002) Potential bidders or offerors may submit a protest under 48 CFR part 33 (FAR part 33... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Protests to NASA....

  1. The 233Pa fission cross-section measurement and evaluation

    International Nuclear Information System (INIS)

    233Pa is a conspicuous example of strongly discrepant data in the accepted nuclear data evaluations. The precise knowledge of the neutron-induced reaction cross-section of this highly β-active nuclide (T1/2 = 27.0 d) is essential for the successful implementation of the thorium-based fuel cycle in advanced nuclear applications. The reactions involving 233Pa are responsible for the balance of nuclei as well as the average number of prompt fission neutrons in a contemplated reactor scenario. In an IAEA report, it is stated that there is a need to know the 233Pa(n, f) cross-section with an accuracy of 20%. The different evaluated neutron data libraries show, however, a difference of a factor of two for this cross-section. It has previously been deemed not feasible to measure this reaction directly due to its short half-life, high radioactivity and the in-growth of the daughter product 233U. Hence, the entries in the neutron libraries are based on theoretical predictions, which explains the large discrepancies. As reported recently the neutron-induced fission cross-section of 233Pa has been measured for the first time directly with mono-energetic neutrons from 1.0 to 3.0 MeV at the Van-de-Graaff facility of the IRMM. In the meantime, during two further measurement campaigns, the energy range has been extended up to 8.5 MeV. The experimental results will be presented together with recent model calculations of the fission cross-section applying the statistical model code STATIS, which improve the cross-section evaluation up to the second chance fission threshold. (authors)

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

    International Nuclear Information System (INIS)

    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

  3. 47 CFR 51.233 - Significant degradation of services caused by deployment of advanced services.

    Science.gov (United States)

    2010-10-01

    ... presumption that it is acceptable for deployment under § 51.230, the degraded service shall not prevail... deployment of advanced services. 51.233 Section 51.233 Telecommunication FEDERAL COMMUNICATIONS COMMISSION... § 51.233 Significant degradation of services caused by deployment of advanced services. (a) Where...

  4. 42 CFR 23.3 - What entities are eligible to apply for assignment?

    Science.gov (United States)

    2010-10-01

    ...? 23.3 Section 23.3 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES PERSONNEL NATIONAL HEALTH SERVICE CORPS Assignment of National Health Service Corps Personnel § 23.3 What... assignment of National Health Service Corps personnel....

  5. 40 CFR 23.3 - Timing of Administrator's action under Clean Air Act.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Timing of Administrator's action under Clean Air Act. 23.3 Section 23.3 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY GENERAL JUDICIAL REVIEW UNDER EPA-ADMINISTERED STATUTES § 23.3 Timing of Administrator's action under Clean Air...

  6. Updated and revised neutron reaction data for 233U

    Institute of Scientific and Technical Information of China (English)

    YU Bao-Sheng; CHEN Guo-Chang; ZHANG Hua; CAO Wen-Tian; TANG Guo-You; TAO Xi

    2013-01-01

    A complete set of n+233U neutron reaction data from 10-5 eV-20 MeV is updated and revised based on the evaluated experimental data and the feedback information of various benchmark tests.The main revised quantities are nubars,cross sections as well as angular distributions,etc.The benchmark tests indicate that the present evaluated data achieve very promising results.

  7. Strategy for the future use and disposition of uranium-233: Technical information

    International Nuclear Information System (INIS)

    This document provides a summary of technical information on the synthetic radioisotope 233U. It is one of a series of four reports that map out a national strategy for the future use and disposition of 233U. The technical information on 233U in this document falls into two main areas. First, material characteristics are presented along with the contrasts of 233U to the more well known strategic fissile materials, 235U and plutonium (Pu). Second, information derived from the scientific information, such as safeguards, waste classifications, material form, and packaging, is presented. Throughout, the effects of isotopically diluting 233U with nonfissile, depleted uranium (DU) are examined

  8. History of Uranium-233(233U)Processing at the Rocky Flats Plant. In support of the RFETS Acceptable Knowledge Program

    International Nuclear Information System (INIS)

    This report documents the processing of Uranium-233 at the Rocky Flats Plant (Rocky Flats Environmental Technology Site). The information may be used to meet Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC)and for determining potential Uranium-233 content in applicable residue waste streams

  9. Th/U-233 multi-recycle in PWRs.

    Energy Technology Data Exchange (ETDEWEB)

    Yun, D.; Kim, T. K.; Taiwo, T. A.; Nuclear Engineering Division

    2010-09-07

    The use of thorium in current or advanced light water reactors (LWRs) has been of interest in recent years. These interests have been associated with the need to increase nuclear fuel resources and the perceived non-proliferation advantages of the utilization of thorium in the fuel cycle. Various options have been considered for the use of thorium in the LWR fuel cycle including: (1) its use in a once-through fuel cycle to replace non-fissile uranium or to extend fuel burnup due to its attractive fertile material conversion, (2) its use for fissile plutonium burning in limited recycle cores, and (3) its advantage in limiting the transuranic elements to be disposed off in a repository (if only Th/U-233 fuel is used). The possibility for thorium utilization in multirecycle system has also been considered by various researchers, primarily because of the potential for near breeders with Th/U-233 in the thermal energy range. The objective of this project is to evaluate the potential of the Th/U-233 fuel multirecycle in current LWRs, with focus this year on pressurized water reactors (PWRs). In this work, approaches for ensuring a sustainable multirecycle without the need for external source of makeup fissile material have been investigated. The intent is to achieve a design that allows existing PWRs to be used with minimal modifications. In all cases including homogeneous and heterogeneous assembly designs, the assembly pitch is kept consistent with that of the current PWRs (21.5 cm used). Because of design difficulties associated with using the same geometry and dimensions as a PWR core, the potential modifications (other than assembly pitch) that would be needed for PWRs to ensure a sustainable multirecycle system have been investigated and characterized. Additionally, the implications of the use of thorium on the LWR fuel cycle are discussed. In Section 2, background information on studies evaluating the use of thorium in the fuel cycle is provided, but focusing on

  10. Nuclear reactor for breeding U.sup.233

    Science.gov (United States)

    Bohanan, Charles S.; Jones, David H.; Raab, Jr., Harry F.; Radkowsky, Alvin

    1976-01-01

    A light-water-cooled nuclear reactor capable of breeding U.sup.233 for use in a light-water breeder reactor includes physically separated regions containing U.sup.235 fissile material and U.sup.238 fertile material and Th.sup.232 fertile material and Pu.sup.239 fissile material, if available. Preferably the U.sup.235 fissile material and U.sup.238 fertile material are contained in longitudinally movable seed regions and the Pu.sup.239 fissile material and Th.sup.232 fertile material are contained in blanket regions surrounding the seed regions.

  11. Safety analysis for the 233-S decontamination and decommissioning project

    International Nuclear Information System (INIS)

    Decommissioning of the 233-S Plutonium Concentration Facility (REDOX) is a proposed expedited response action that is regulated by the Comprehensive Environmental Response Compensation and Liability Act of 1980 and the Hanford Federal Facility Agreement and Consent Order. Due to progressive physical deterioration of this facility, a decontamination and decommissioning plan is being considered for the immediate future. This safety analysis describes the proposed actions involved in this D ampersand D effort; identifies the radioactive material inventories involved; reviews site specific environmental characteristics and postulates an accident scenario that is evaluated to identify resultant effects

  12. Passive neutron survey of the 233-S Plutonium Concentration Facility

    International Nuclear Information System (INIS)

    A passive neutron survey was performed at the 233-S Plutonium Concentration Facility (located at the Hanford Site in Richland, Washington) during late 1994 and early 1995. Four areas were surveyed: an abandoned filter box and pipe trench, column laydown trench, load-out hood, and process hood. The primary purpose of the survey was to identify locations that had plutonium to help direct decontamination and decommissioning activities. A secondary purpose of the survey was to determine the quantity of material when its presence was identified

  13. Isotopic dilution of 233U with depleted uranium for criticality safety in processing and disposal

    International Nuclear Information System (INIS)

    The disposal of excess 233U as waste is being considered. Because 233U is a fissile material, a key requirement for processing 233U to a final waste form and disposing of it is the avoidance of nuclear criticality. For many processing and disposal options, isotopic dilution is the most feasible and preferred option to avoid nuclear criticality. Isotopic dilution is dilution of fissile 233U with nonfissile 238U. The use of isotopic dilution removes any need to control nuclear criticality in process or disposal facilities through geometry or chemical composition. Isotopic dilution allows the use of existing waste management facilities that are not designed for significant quantities of fissile materials to be used for processing and disposing of 233U. The amount of isotopic dilution required to reduce criticality concerns to reasonable levels was determined in this study to be approximately 0.53 wt % 233U. The numerical calculations used to define this limit consisted of a homogeneous system of silicon dioxide (SiO2), water (H2O), 233U and depleted uranium (DU) in which the ratio of each component was varied to learn the conditions of maximum nuclear reactivity. About 188 parts of DU (0.2 wt % 235U) are required to dilute 1 part of 233U to this limit in a water-moderated system with no SiO2 present. Thus for the U.S. inventory of 233U, several hundred metric tons of DU would be required for isotopic dilution

  14. Study on the adsorption of 233Pa in glass

    International Nuclear Information System (INIS)

    It is intended to examine the adsorption of protactinium on glass in relation to pH, presence of complexing agents concentration and type of electrolytes. The study was made by using carrier-free 233Pa solution and Pyrex glass tube was selected as adsorbent glass material surface. The adsorption curve of protactinium on glass surface as a function of the pH of the tracer solution showed the existence of two pronounced adsorption regions. It was found that this adsorption can be reduced by using electrolytes or complexing agents. Desorption of protactinium previously adsorbed on the Pyrex glass tube was also studied. Hidrochloric, oxalic and hydrofluoric acid solutions were used for the desorption experiments. (Author)

  15. Renewal and Modified Evaluation Data of ~(233)U in CENDL_-3.1

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    A complete set of evaluated neutron nuclear data of 233U was preformed before 2000, and released in 2009. The status of the published nuclear data 233U in CENDL-3.1 is in some cases not up to the requirements. As the recent experimental data

  16. 9 CFR 2.33 - Attending veterinarian and adequate veterinary care.

    Science.gov (United States)

    2010-01-01

    ... animal health, behavior, and well-being is conveyed to the attending veterinarian; (4) Guidance to... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Attending veterinarian and adequate veterinary care. 2.33 Section 2.33 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION...

  17. 45 CFR 233.106 - Denial of AFDC benefits to strikers.

    Science.gov (United States)

    2010-10-01

    ...” by using the National Labor Relations Board definition (29 U.S.C. 142(2)) or another definition of... 45 Public Welfare 2 2010-10-01 2010-10-01 false Denial of AFDC benefits to strikers. 233.106 Section 233.106 Public Welfare Regulations Relating to Public Welfare OFFICE OF FAMILY...

  18. 20 CFR 702.233 - Penalty for failure to pay without an award.

    Science.gov (United States)

    2010-04-01

    .... 702.233 Section 702.233 Employees' Benefits EMPLOYMENT STANDARDS ADMINISTRATION, DEPARTMENT OF LABOR LONGSHOREMEN'S AND HARBOR WORKERS' COMPENSATION ACT AND RELATED STATUTES ADMINISTRATION AND PROCEDURE Claims... the same time as, but in addition to, such installment unless the employer files notice...

  19. 24 CFR 5.233 - Mandated use of HUD's Enterprise Income Verification (EIV) System.

    Science.gov (United States)

    2010-04-01

    ...) Project-based Voucher program under 24 CFR part 983; (v) Project-based Section 8 programs under 24 CFR... noncompliance. Failure to use the EIV system in its entirety may result in the imposition of sanctions and/or... Income Verification (EIV) System. 5.233 Section 5.233 Housing and Urban Development Office of...

  20. Separation and estimation of 229Th and 233U by alpha and gamma ray spectrometric technique

    International Nuclear Information System (INIS)

    The individual estimation of 233U and 229Th in a plancheted source made out of liquid sample were done by using an alpha and γ-ray spectrometric techniques. Estimation of 229Th in the plancheted source was done by γ-ray spectrometry and 233U by alpha spectrometry after subtracting the estimated amount of 229Th. In spite of the same alpha energy of 4.8 MeV, the individual estimation of 233U and 229Th based on present technique is superior to conventional techniques and important in the 232Th-233U fuel reprocessing cycle of AHWR and ADSs. The activity of 229Th was also radiochemically separated from its parent activity of 233U by using an ion exchange resin and the purity was checked by the above mentioned technique. (author)

  1. Statistical analysis of 233 cases in cerebovascular Diseases

    Institute of Scientific and Technical Information of China (English)

    Hu Hao-Yu; Zhejiang; Jlnhua

    2000-01-01

    Objection:Monitoring Clinical in-patient constituent ratio in cerebral vasscular diseases. Methods: we monitored 233 cases of CVD in clinical in--patient 13170 cases for three years with unique registry card accroding to ICD--9. These pepole′s data was putted in computer. Age, sex, constituent ratio of each disease in CVD was observed and number of death and rank order of cases of death as well. Results: In our data, number of male is more than female(1.75:I). Constituent ratio of age is increasing at 40 years old. Main part of CH is middle age and senility, but CI age is senility. Constituent ratio of each disease is following :CI 67.74%, CH 22.13%, CT 6.06%, SAH 3.79% respectlvly. The rank order of death in CVD is third later in cardiovascular diseases and tumors. Conclusions: Our materials revealsed that it is improtant that intensiv′e care and treatment group in pead population of CVD and prevention high risk facters of CVD and health care education

  2. A 233 km Tunnel for Lepton and Hadron Colliders

    CERN Document Server

    Summers, D J; Datta, A; Duraisamy, M; Luo, T; Lyons, G T

    2012-01-01

    A decade ago, a cost analysis was conducted to bore a 233 km circumference Very Large Hadron Collider (VLHC) tunnel passing through Fermilab. Here we outline implementations of $e^+e^-$, $p \\bar{p}$, and $\\mu^+ \\mu^-$ collider rings in this tunnel using recent technological innovations. The 240 and 500 GeV $e^+e^-$ colliders employ Crab Waist Crossings, ultra low emittance damped bunches, short vertical IP focal lengths, superconducting RF, and low coercivity, grain oriented silicon steel/concrete dipoles. Some details are also provided for a high luminosity 240 GeV $e^+ e^-$ collider and 1.75 TeV muon accelerator in a Fermilab site filler tunnel. The 40 TeV $p \\bar{p}$ collider uses the high intensity Fermilab $\\bar{p}$ source, exploits high cross sections for $p \\bar{p}$ production of high mass states, and uses 2 Tesla ultra low carbon steel/YBCO superconducting magnets run with liquid neon. The 35 TeV muon ring ramps the 2 Tesla superconducting magnets at 9 Hz every 0.4 seconds, uses 250 GV of superconduct...

  3. A 233 km tunnel for lepton and hadron colliders

    Energy Technology Data Exchange (ETDEWEB)

    Summers, D. J.; Cremaldi, L. M.; Datta, A.; Duraisamy, M.; Luo, T.; Lyons, G. T. [Dept. of Physics and Astronomy, University of Mississippi-Oxford, University, MS 38677 (United States)

    2012-12-21

    A decade ago, a cost analysis was conducted to bore a 233 km circumference Very Large Hadron Collider (VLHC) tunnel passing through Fermilab. Here we outline implementations of e{sup +}e{sup -}, pp-bar , and {mu}{sup +}{mu}{sup -} collider rings in this tunnel using recent technological innovations. The 240 and 500 GeV e{sup +}e{sup -} colliders employ Crab Waist Crossings, ultra low emittance damped bunches, short vertical IP focal lengths, superconducting RF, and low coercivity, grain oriented silicon steel/concrete dipoles. Some details are also provided for a high luminosity 240 GeV e{sup +}e{sup -} collider and 1.75 TeV muon accelerator in a Fermilab site filler tunnel. The 40 TeV pp-bar collider uses the high intensity Fermilab p-bar source, exploits high cross sections for pp-bar production of high mass states, and uses 2 Tesla ultra low carbon steel/YBCO superconducting magnets run with liquid neon. The 35 TeV muon ring ramps the 2 Tesla superconducting magnets at 9 Hz every 0.4 seconds, uses 250 GV of superconducting RF to accelerate muons from 1.75 to 17.5 TeV in 63 orbits with 71% survival, and mitigates neutrino radiation with phase shifting, roller coaster motion in a FODO lattice.

  4. 45 CFR 233.35 - Computing the assistance payment under retrospective budgeting after the initial one or two...

    Science.gov (United States)

    2010-10-01

    ... retrospective budgeting after the initial one or two months (AFDC). 233.35 Section 233.35 Public Welfare... the initial one or two months (AFDC). The State plan for AFDC shall provide: (a) After the initial one or two payment months of assistance under § 233.34, the amount of each subsequent month's...

  5. 20 CFR 404.233 - Adjustment of your guaranteed alternative when you become entitled after age 62.

    Science.gov (United States)

    2010-04-01

    ... when you become entitled after age 62. 404.233 Section 404.233 Employees' Benefits SOCIAL SECURITY... Guaranteed Alternative for People Reaching Age 62 After 1978 But Before 1984 § 404.233 Adjustment of your guaranteed alternative when you become entitled after age 62. (a) If you do not become entitled to...

  6. 5 CFR 532.233 - Preparation for full-scale wage surveys.

    Science.gov (United States)

    2010-01-01

    ... the prevailing rate law for labor and agency representatives to participate in the wage survey process... REGULATIONS PREVAILING RATE SYSTEMS Prevailing Rate Determinations § 532.233 Preparation for full-scale...

  7. Uses for Uranium-233: What Should Be Kept for Future Needs?

    International Nuclear Information System (INIS)

    Since the end of the cold war, the United States has been evaluating what fissile materials to keep for potential uses and what fissile materials to declare excess. There are three major fissile materials: high-enriched uranium (HEU), plutonium, and uranium-233 (233U). Both HEU and plutonium were produced in large quantities for use in nuclear weapons and for reactor fuel. Uranium-233 was investigated for use in nuclear weapons and as a reactor fuel; however, it was never deployed in nuclear weapons or used commercially as a nuclear fuel. Uranium-233 has limited current uses, but it could have several future uses. Because of (1) the cost of storing 233U and (2) arms control considerations, the U.S. government must decide how much of the existing 233U inventory should be kept for future use and how much should be disposed of as waste. The objective of this report is to provide technical and economic input to make a use-or-dispose decision

  8. 药疹233例临床特征分析%Clinical analysis of 233 patients with drug eruption

    Institute of Scientific and Technical Information of China (English)

    吴伊旋; 冯欢; 刘怡文; 钱骋风; 陆平

    2001-01-01

    目的:了解当前药疹的主要临床特征,为其防治工作提供参考。方法:收集1999年全年确诊为药疹的病例233例,并对其发病年龄、主要致敏药物、皮疹类型等临床特征进行分析。结果:药疹的发病年龄有所提高,主要致敏药物以抗生素最常见,其次为解热镇痛抗炎药、血清及疫苗制剂、中成药。皮疹类型以猩红热样或麻疹样型最常见,其次为荨麻疹型、多型红斑型、固定型。结论:临床医生在用药时应详细询问病史,避免不必要用药,以减少药疹发生%AIM:To discuss the main clinical characteristics of current drug eruption for reference of prevention and treatment of drug eruption. METHODS: Two hundred and thirty-three with drug eruption in 1999 were collected, and their clinical characteristics, such as age, main causative drugs and eruption types, etc. were analysed. RESULTS: The age of current drug eruption increased. Antibiotics was the most common causative drug, while antiinflammatory analgestics, serum and vaccine, traditional Chinese medicine were next to it. Scarlet fever-like or measles-like type was the most common eruption type, while urticaria type, erythema multiforme type and fixed type were next to it. CONCLUSION: Clinical physicians shoud inquire alergic history of patients thoroughly and avoid unnecessary drugs, so as to decrease the occurrence of drug eruption.

  9. L233P mutation of the Tax protein strongly correlated with leukemogenicity of bovine leukemia virus.

    Science.gov (United States)

    Inoue, Emi; Matsumura, Keiko; Soma, Norihiko; Hirasawa, Shintaro; Wakimoto, Mayuko; Arakaki, Yoshihiro; Yoshida, Takashi; Osawa, Yoshiaki; Okazaki, Katsunori

    2013-12-27

    The bovine leukemia virus (BLV) Tax protein is believed to play a crucial role in leukemogenesis by the virus. BLV usually causes asymptomatic infections in cattle, but only one-third develop persistent lymphocytosis that rarely progress after a long incubation period to lymphoid tumors, namely enzootic bovine leucosis (EBL). In the present study, we demonstrated that the BLV tax genes could be divided into two alleles and developed multiplex PCR detecting an L233P mutation of the Tax protein. Then, in order to define the relationship between the Tax protein and leukemogenicity, we examined 360 tumor samples randomly collected from dairy or breeding cattle in Japan, of which Tax proteins were categorized, for age at the time of diagnosis of EBL. The ages of 288 animals (80.0%) associated with L233-Tax and those of 70 animals (19.4%) with P233-Tax individually followed log-normal distributions. Only the two earliest cases (0.6%) with L233-Tax disobeyed the log-normal distribution. These findings suggest that the animals affected by EBL were infected with the virus at a particular point in life, probably less than a few months after birth. Median age of those with P233-Tax was 22 months older than that with L233-Tax and geometric means exhibited a significant difference (PTax protein infect older cattle. Here, we conclude that BLV could be divided into two categories on the basis of amino acid at position 233 of the Tax protein, which strongly correlated with leukemogenicity.

  10. Compilation of criticality data involving thorium or 233U and light water moderation

    Energy Technology Data Exchange (ETDEWEB)

    Gore, B.F.

    1978-07-01

    The literature has been searched for criticality data for light water moderated systems which contain thorium or /sup 233/U, and data found are compiled herein. They are from critical experiments, extrapolations, and exponential experiments performed with homogeneous solutions and metal spheres of /sup 233/U; with lattices of fuel rods containing highly enriched /sup 235/UO/sub 2/ - ThO/sub 2/ and /sup 233/UO/sub 2/ - ThO/sub 2/; and with arrays of cyclinders of /sup 233/U solutions. The extent of existing criticality data has been compared with that necessary to implement a thorium-based fuel cycle. No experiments have been performed with any solutions containing thorium. Neither do data exist for homogeneous /sup 233/U systems with H/U < 34, except for solid metal systems. Arrays of solution cylinders up to 3 x 3 x 3 have been studied. Data for solutions containing fixed or soluble poisons are very limited. All critical lattices using /sup 233/UO/sub 2/ - ThO/sub 2/ fuels (LWBR program) were zoned radially, and in most cases axially also. Only lattice experiments using /sup 235/UO/sub 2/ - ThO/sub 2/ fuels have been performed using a single fuel rod type. Critical lattices of /sup 235/UO/sub 2/ - ThO/sub 2/ rods poisoned with boron have been measured, but only exponential experiments have been performed using boron-poisoned lattices of /sup 233/UO/sub 2/ - ThO/sub 2/ rods. No criticality data exist for denatured fuels (containing significant amounts of /sup 238/U) in either solution or lattice configurations.

  11. Interim assessment of the denatured 233U fuel cycle: feasibility and nonproliferation characteristics

    International Nuclear Information System (INIS)

    A fuel cycle that employs 233U denatured with 238U and mixed with thorium fertile material is examined with respect to its proliferation-resistance characteristics and its technical and economic feasibility. The rationale for considering the denatured 233U fuel cycle is presented, and the impact of the denatured fuel on the performance of Light-Water Reactors, Spectral-Shift-Controlled Reactors, Gas-Cooled Reactors, Heavy-Water Reactors, and Fast Breeder Reactors is discussed. The scope of the R, D and D programs to commercialize these reactors and their associated fuel cycles is also summarized and the resource requirements and economics of denatured 233U cycles are compared to those of the conventional Pu/U cycle. In addition, several nuclear power systems that employ denatured 233U fuel and are based on the energy center concept are evaluated. Under this concept, dispersed power reactors fueled with denatured or low-enriched uranium fuel are supported by secure energy centers in which sensitive activities of the nuclear cycle are performed. These activities include 233U production by Pu-fueled transmuters (thermal or fast reactors) and reprocessing. A summary chapter presents the most significant conclusions from the study and recommends areas for future work

  12. Interim assessment of the denatured /sup 233/U fuel cycle: feasibility and nonproliferation characteristics

    Energy Technology Data Exchange (ETDEWEB)

    Abbott, L.S.; Bartine, D.E.; Burns, T.J. (eds.)

    1978-12-01

    A fuel cycle that employs /sup 233/U denatured with /sup 238/U and mixed with thorium fertile material is examined with respect to its proliferation-resistance characteristics and its technical and economic feasibility. The rationale for considering the denatured /sup 233/U fuel cycle is presented, and the impact of the denatured fuel on the performance of Light-Water Reactors, Spectral-Shift-Controlled Reactors, Gas-Cooled Reactors, Heavy-Water Reactors, and Fast Breeder Reactors is discussed. The scope of the R, D and D programs to commercialize these reactors and their associated fuel cycles is also summarized and the resource requirements and economics of denatured /sup 233/U cycles are compared to those of the conventional Pu/U cycle. In addition, several nuclear power systems that employ denatured /sup 233/U fuel and are based on the energy center concept are evaluated. Under this concept, dispersed power reactors fueled with denatured or low-enriched uranium fuel are supported by secure energy centers in which sensitive activities of the nuclear cycle are performed. These activities include /sup 233/U production by Pu-fueled transmuters (thermal or fast reactors) and reprocessing. A summary chapter presents the most significant conclusions from the study and recommends areas for future work.

  13. Characteristics of Modular Fast Reactor SVBR-100 Using Thorium-Uranium (233) Fuel

    International Nuclear Information System (INIS)

    Conclusions: • The performed computations for three different types of fuel (oxide , nitride and metallic), have revealed that maximum of uranium-233 breeding ratio, which equals to 0.9, is achieved when nitride type of fuel is used. • Adding breeding zones or increasing of the core dimensions result in increasing uranium-233 breeding ratio (up to BR = 0,97 or BR = 0,96 respectively). • There is opportunity of using plutonium as initial fissile isotope to implement U-Th-Pu fuel cycle. Breeding ratio is assessed by 0,98 if nitride fuel composition (Th+Pu)N with effective density of 12.5 is used. • The obtained data have demonstrated that both for U-Th FC and U-Th-Pu FC there is an opportunity to achieve a value of U-233 BR to be over unity when using the breeding zones and slightly increased the core dimensions

  14. Uranium-233 waste definition: Disposal options, safeguards, criticality control, and arms control

    Energy Technology Data Exchange (ETDEWEB)

    Forsberg, C.W.; Storch, S.N. [Oak Ridge National Lab., TN (United States); Lewis, L.C. [Lockheed Martin Idaho Technology Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.

    1998-07-07

    The US investigated the use of {sup 233}U for weapons, reactors, and other purposes from the 1950s into the 1970s. Based on the results of these investigations, it was decided not to use {sup 233}U on a large scale. Most of the {sup 233}U-containing materials were placed in long-term storage. At the end of the cold war, the US initiated, as part of its arms control policies, a disposition program for excess fissile materials. Other programs were accelerated for disposal of radioactive wastes placed in storage during the cold war. Last, potential safety issues were identified related to the storage of some {sup 233}U-containing materials. Because of these changes, significant activities associated with {sup 233}U-containing materials are expected. This report is one of a series of reports to provide the technical bases for future decisions on how to manage this material. A basis for defining when {sup 233}U-containing materials can be managed as waste and when they must be managed as concentrated fissile materials has been developed. The requirements for storage, transport, and disposal of radioactive wastes are significantly different than those for fissile materials. Because of these differences, it is important to classify material in its appropriate category. The establishment of a definition of what is waste and what is fissile material will provide the guidance for appropriate management of these materials. Wastes are defined in this report as materials containing sufficiently small masses or low concentrations of fissile materials such that they can be managed as typical radioactive waste. Concentrated fissile materials are defined herein as materials containing sufficient fissile content such as to warrant special handling to address nuclear criticality, safeguards, and arms control concerns.

  15. Uranium-233 waste definition: Disposal options, safeguards, criticality control, and arms control

    International Nuclear Information System (INIS)

    The US investigated the use of 233U for weapons, reactors, and other purposes from the 1950s into the 1970s. Based on the results of these investigations, it was decided not to use 233U on a large scale. Most of the 233U-containing materials were placed in long-term storage. At the end of the cold war, the US initiated, as part of its arms control policies, a disposition program for excess fissile materials. Other programs were accelerated for disposal of radioactive wastes placed in storage during the cold war. Last, potential safety issues were identified related to the storage of some 233U-containing materials. Because of these changes, significant activities associated with 233U-containing materials are expected. This report is one of a series of reports to provide the technical bases for future decisions on how to manage this material. A basis for defining when 233U-containing materials can be managed as waste and when they must be managed as concentrated fissile materials has been developed. The requirements for storage, transport, and disposal of radioactive wastes are significantly different than those for fissile materials. Because of these differences, it is important to classify material in its appropriate category. The establishment of a definition of what is waste and what is fissile material will provide the guidance for appropriate management of these materials. Wastes are defined in this report as materials containing sufficiently small masses or low concentrations of fissile materials such that they can be managed as typical radioactive waste. Concentrated fissile materials are defined herein as materials containing sufficient fissile content such as to warrant special handling to address nuclear criticality, safeguards, and arms control concerns

  16. Numerical simulations of groundwater flow and solute transport in the Lake 233 aquifer

    International Nuclear Information System (INIS)

    A three-dimensional numerical flow model of the Lake 233 aquifer underlying the site of the proposed Intrusion Resistant Underground Structure (IRUS) for low level waste disposal is developed. A reference hydraulic conductivity distribution incorporating the key stratigraphic units and field estimates of recharge from Lake 233 are used as model input. The model was calibrated against the measured hydraulic head distribution, the flowpath of a historic 90Sr plume in the aquifer and measured groundwater velocities. (author). 23 refs., 4 tabs., 31 figs

  17. 16 CFR 233.2 - Retail price comparisons; comparable value comparisons.

    Science.gov (United States)

    2010-01-01

    ... GUIDES AGAINST DECEPTIVE PRICING § 233.2 Retail price comparisons; comparable value comparisons. (a) Another commonly used form of bargain advertising is to offer goods at prices lower than those being... business). This may be done either on a temporary or a permanent basis, but in either case the...

  18. D2.3.3 Evaluation results of the LinkedUp VICI competition

    NARCIS (Netherlands)

    Drachsler, Hendrik

    2014-01-01

    This document D2.3.3 is the final report of Task 2.4 – Evaluation of challenge submissions. Task 2.4 is about the actual assessment of the participating projects within the LinkedUp Veni, Vidi and Vici competition on the basis of the LinkedUp Evaluation Framework (D2.2.1). The main objective of Task

  19. 78 FR 18232 - Amendment of VOR Federal Airway V-233, Springfield, IL

    Science.gov (United States)

    2013-03-26

    ... depiction of the airway. When V- 233 was amended in the Federal Register of August 8, 2005 (70 FR 45527... Department of Transportation (DOT) Regulatory Policies and Procedures (44 FR 11034; February 26, 1979); and..., 40113, 40120; E.O. 10854, 24 FR 9565, 3 CFR, 1959-1963 Comp., p. 389. Sec. 71.1 0 2. The...

  20. Investigations on production of 233U using few pin thoria in existing PHWRs

    International Nuclear Information System (INIS)

    Thorium is not a fissile material and cannot be used to either start or sustain the chain reaction. Therefore, a reactor using thorium would also need either enriched uranium or plutonium to sustain the chain reaction until enough of the thorium has converted to fissile 233U. In order to retrieve and reprocess the irradiated fuel, the bundle is designed with few thoria pins and rest SEU pins. In the present study, different pin configurations of thoria in 19 and 37 element fuel clusters of Indian PHWRs have been considered. The lattice calculations have been done using the multi-group transport theory code CLUB. The variations of k∞ versus burn up are depicted in the paper. The production of 233U (considering also the decay of 233Pa into 233U) is also shown. Average discharge burn ups of the order 20 and 17 GWd/Te can be achieved with the use of thoria pins in 19 and 37 element fuel clusters respectively with appropriate bundle shift scheme. Derating of power is required during operation because of bundle power restrictions. It is found that 1 pin thoria configuration is preferable from the point of view of fuel requirements and power reduction consideration. Since 37 element fuel cluster used in 540 MWe PHWR fuel has large margins in bundle power, the restriction in power operation is much less than 19 element fuel cluster used in 220 MWe PHWR

  1. Study of electrodeposition technique to prepare alpha-counting plates of uranium 233

    International Nuclear Information System (INIS)

    The electrodeposition technique to prepare alpha-counting plates of 233U for its determination is presented. To determine the optimum conditions for plating 233U the effects of such parameters as current density, pH of eletrotype, salt concentration, time of electrolysis and distance electrodes were studied. A carrier method was developed to attain a quantitative electrodeposition of 233U from aqueous solutions into alpha counting paltes. A single and incremental addition of natural uranium and thorium as carrier were studied. All samples were prepared using a electrodeposition cell manufactured at the IPEN, especially for use in electroplating tracer actinides. This cell is made of a metal-lucite to contain the electrolyte, which bottom is a polished brass disk coated with a Ni film serving as the cathode. A Pt wire anode is fixed on the top of the cell. The electroplated samples were alpha-counted using a surface barrier detector. A recovery of more than 99% was obtained in specific conditions. The plating procedure produced deposits which were firmly distributed over the plate area. The method was applied to determine tracer amounts of 233U from oxalate and nitrate solutions coming from chemical processing irradiated thorium. (Author)

  2. Sampling and Analysis Plan for the 233-S Plutonium Concentration Facility

    International Nuclear Information System (INIS)

    This Sampling and Analysis Plan (SAP) provides the information and instructions to be used for sampling and analysis activities in the 233-S Plutonium Concentration Facility. The information and instructions herein are separated into three parts and address the Data Quality Objective (DQO) Summary Report, Quality Assurance Project Plan (QAP), and SAP

  3. 48 CFR 52.233-4 - Applicable Law for Breach of Contract Claim.

    Science.gov (United States)

    2010-10-01

    ... Provisions and Clauses 52.233-4 Applicable Law for Breach of Contract Claim. As prescribed in 33.215(b), insert the following clause: Applicable Law for Breach of Contract Claim (OCT 2004) United States law... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Applicable Law for...

  4. 29 CFR 779.233 - Independent contractors performing work “for” an enterprise.

    Science.gov (United States)

    2010-07-01

    ... Apply; Enterprise Coverage Leased Departments, Franchise and Other Business Arrangements § 779.233... section 3(r) has reference to an independent business which performs services for other businesses as an established part of its own business activities. The term “independent contractor” as used in 3(r) thus...

  5. 46 CFR 153.233 - Separation of tanks from machinery, service and other spaces.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 5 2010-10-01 2010-10-01 false Separation of tanks from machinery, service and other... Design and Equipment Cargo Containment Systems § 153.233 Separation of tanks from machinery, service and... joint: (1) Machinery spaces. (2) Service spaces. (3) Accommodation spaces. (4) Spaces for...

  6. Breeding of 233U in the thorium–uranium fuel cycle in VVER reactors using heavy water

    International Nuclear Information System (INIS)

    A method is proposed for achieving optimal neutron kinetics and efficient isotope transmutation in the 233U–232Th oxide fuel of water-moderated reactors with variable water composition (D2O, H2O) that ensures breeding of the 233U and 235U isotopes. The method is comparatively simple to implement

  7. Breeding of {sup 233}U in the thorium–uranium fuel cycle in VVER reactors using heavy water

    Energy Technology Data Exchange (ETDEWEB)

    Marshalkin, V. E., E-mail: marshalkin@vniief.ru; Povyshev, V. M. [Russian Federal Nuclear Center All-Russian Research Institute of Experimental Physics (VNIIEF) (Russian Federation)

    2015-12-15

    A method is proposed for achieving optimal neutron kinetics and efficient isotope transmutation in the {sup 233}U–{sup 232}Th oxide fuel of water-moderated reactors with variable water composition (D{sub 2}O, H{sub 2}O) that ensures breeding of the {sup 233}U and {sup 235}U isotopes. The method is comparatively simple to implement.

  8. 77 FR 67394 - Gulf of Mexico (GOM), Outer Continental Shelf (OCS), Western Planning Area (WPA) Lease Sale 233...

    Science.gov (United States)

    2012-11-09

    ... Area (WPA) Lease Sale 233 and Central Planning Area (CPA) Lease Sale 231, Oil and Gas Lease Sales... Supplemental EIS for oil and gas lease sales tentatively scheduled in 2013 and 2014 in the WPA and CPA offshore... environmental and socioeconomic analyses for proposed WPA Lease Sale 233 and proposed CPA Lease Sale 231,...

  9. Breeding of 233U in the thorium-uranium fuel cycle in VVER reactors using heavy water

    Science.gov (United States)

    Marshalkin, V. E.; Povyshev, V. M.

    2015-12-01

    A method is proposed for achieving optimal neutron kinetics and efficient isotope transmutation in the 233U-232Th oxide fuel of water-moderated reactors with variable water composition (D2O, H2O) that ensures breeding of the 233U and 235U isotopes. The method is comparatively simple to implement.

  10. Technical Competencies for the Safe Interim Storage and Management of 233U at U.S. Department of Energy Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, D.O.; Krichinsky, A.M.; Laughlin, S.S.; Van Essen, D.C.; Yong, L.K.

    1999-02-17

    Uranium-233 (with concomitant {sup 232}U) is a man-made fissile isotope of uranium with unique nuclear characteristics which require high-integrity alpha containment biological shielding, and remote handling. The special handling considerations and the fact that much of the {sup 233}U processing and large-scale handling was performed over a decade ago underscore the importance of identifying the people within the DOE complex who are currently working with or have worked with {sup 233}U. The availability of these key personnel is important in ensuring safe interim storage, management and ultimate disposition of {sup 233}U at DOE facilities. Significant programs are ongoing at several DOE sites with actinides. The properties of these actinide materials require many of the same types of facilities and handling expertise as does {sup 233}U.

  11. Strategy for the future use and disposition of Uranium-233: History, inventories, storage facilities, and potential future uses

    International Nuclear Information System (INIS)

    This document provides background information on the man-made radioisotope 233U. It is one of a series of four reports that map out potential national strategies for the future use and disposition of 233U pending action under the National Environmental Policy Act (NEPA). The scope of this report is separated 233U, where separated refers to nonwaste 233U or 233U that has been separated from fission products. Information on other 233U, such as that in spent nuclear fuel (SNF), is included only to recognize that it may be separated at a later date and then fall under the scope of this report. The background information in this document includes the historical production and current inventory of 233U, the uses of 233U, and a discussion of the available facilities for storing 233U. The considerations for what fraction of the current inventory should be preserved for future use depend on several issues. First, 233U always contains a small amount of the contaminant isotope 232U. The decay products of 232U are highly radioactive and require special handling. The current inventory has a variety of qualities with regard to 232U content, ranging from 1 to about 200 ppm (on a total uranium basis). It is preferable to use 233U with the minimum amount of 232U in all applications. The second issue pertains to other isotopes of uranium mixed in with the 233U, specifically 235U and 238U. A large portion of the inventory has a high quantity of 235U associated with it. The presence of bulk amounts of 235U complicates storage because of the added volume needing safeguards and criticality controls. Isotopic dilution using DU may remove safeguards and criticality concerns, but it increases the overall mass and may limit applications that depend on the fissile nature of 233U. The third issue concerns the packaging of the material. There is no standard packaging (although one is being developed); consequently, the inventory exists in a variety of packages. For some applications, the

  12. ALARA Review for the Decontamination, Deactivation and Housekeeping of the 233-S Viewing Room

    International Nuclear Information System (INIS)

    A formal as low as reasonably achievable (ALARA) review is required by BHI-SH-02, Vol. 1, Safety and Health Procedures, Procedure 1.22, 'Planning Radiological Work', when radiological conditions exceed trigger level. The level of contamination inside the viewing room of the 233-S Facility meets this criterion. This ALARA review is for task instructions 1997-03-18-005-8.3.1, 'Instructions for Routine Entries and Minor Maintenance Work at 233-S,' and 8.3.2, 'Instructions for Deactivation, Decon, and Housekeeping in Viewing Room.' The radiological work permit (RWP) request broke the two task instructions into nine separate tasks. The nine tasks identified in the RWP request were used to estimate airborne concentrations and the total exposure

  13. Study of the excited levels of 233Pa by the 237Np alpha decay

    International Nuclear Information System (INIS)

    The excited levels in 233Pa following the 237Np alpha decay have been studied, by performing different experiences to complete available data and supply new information. Thus, two direct alpha spectrum measurement, one alpha-gamma bidimensional coincidence experiment, three gamma-gamma and gamma-X ray coincidences and some other measurements of the gamma spectrum, direct and coincident with alpha-particles have been made. These last experiences have allowed to obviate usual radiochemical separation methods, the 233Pa radioactive descendent interferences being eliminated by means of the coincidence technic. As a result, a primary decay scheme has been elaborated, including 15 new gamma transitions and two new levels, not observed in the most recent works. (Author) 60 refs

  14. Final purification of 233U from thorium by Dowex 50x4 in Thorex process

    International Nuclear Information System (INIS)

    The 233U product obtained after a single cycle 5% tributyl phosphate/shell sol T extraction, scrubbing and stripping often contains significant amount of thorium as impurity. Further purification is normally carried out using ion exchange. The present paper summarises the results of the studies carried out to find out the various factors responsible for the extraordinary binding of thorium ion at the exchanger site while exploring the possibility of eluting total thorium using HNO3 alone

  15. Characteristics of Modular Fast Reactor SVBR-100 Using Thorium-Uranium (233) Fuel

    International Nuclear Information System (INIS)

    Natural reserves of thorium are three times as much as those of uranium. For that reason, thorium is a very promising raw material for manufacturing an artificial fissionable isotope of uranium-233 that is formed when neutrons are absorbed by thorium. Many countries are investigating characteristics of reactors using thorium-uranium (233) fuel. First, breeding ratio (BR) is of interest because only when BR = 1, the reactor can operate in a closed fuel cycle in a mode of fuel self-providing without makeup by other fissionable isotopes. The report presents the results of calculations of neutron-physical and thermal-hydraulic characteristics of SVBR-100 - lead-bismuth cooled small power modular fast reactor using thorium-uranium (233) fuel. Reactor SVBR-100 has specific properties of inherent self-protection and passive safety. The NPP modular power-units, which power equals to a value divisible by 100 MWe, can be constructed on the basis of reactor modules SVBR-100. (author)

  16. ALARA review for the decontamination and decommissioning of the 233-S pipe trench

    International Nuclear Information System (INIS)

    The 233-S Facility was completed in 1955 to expand plutonium production by further concentrating the plutonium nitrate product solution from the Reduction Oxidation (REDOX) Plant. The facility is radiologically contaminated because of operations and accidents. Isolation from REDOX and removal of the product transfer lines from the pipe trench is the second step in the decontamination and decommissioning of the entire 233-S Facility. The work scope is to isolate all piping from REDOX and then to remove all the piping/equipment from the pipe trench. The building is presently a Hazard Category 2 Nuclear Facility. A formal as low as reasonably achievable (ALARA) review is required by BHI-SH-02, Vol. 1, Procedure No. 1.22, Planning Radiological Work, when radiological conditions exceed trigger levels. The level of contamination inside the pipe trench and the process fluid piping is unknown. The potential exists to exceed the level of loose surface contamination, which requires a formal ALARA review when opening the pipe trench and cutting of piping commences. This ALARA review is for task instruction 1997-03-18-009 Revision 1, 233-S Pipe Trench Decon and Pipe Removal

  17. Criticality safety validation: Simple geometry, single unit {sup 233}U systems

    Energy Technology Data Exchange (ETDEWEB)

    Putman, V.L.

    1997-06-01

    Typically used LMITCO criticality safety computational methods are evaluated for suitability when applied to INEEL {sup 233}U systems which reasonably can be modeled as simple-geometry, single-unit systems. Sixty-seven critical experiments of uranium highly enriched in {sup 233}U, including 57 aqueous solution, thermal-energy systems and 10 metal, fast-energy systems, were modeled. These experiments include 41 cylindrical and 26 spherical cores, and 41 reflected and 26 unreflected systems. No experiments were found for intermediate-neutron-energy ranges, or with interstitial non-hydrogenous materials typical of waste systems, mixed {sup 233}U and plutonium, or reflectors such as steel, lead, or concrete. No simple geometry experiments were found with cubic or annular cores, or approximating infinite sea systems. Calculations were performed with various tools and methodologies. Nine cross-section libraries, based on ENDF/B-IV, -V, or -VI.2, or on Hansen-Roach source data, were used with cross-section processing methods of MCNP or SCALE. The k{sub eff} calculations were performed with neutral-particle transport and Monte Carlo methods of criticality codes DANT, MCNP 4A, and KENO Va.

  18. Effect of electrolyte concentration on low-temperature electrochemical properties of LaNi5 alloy electrodes at 233 K

    Institute of Scientific and Technical Information of China (English)

    ZHANG Xiaoyan; CHEN Yungui; TAO Mingda; WU Chaoling

    2008-01-01

    The effect of KOH electrolyte concentration on low-temperature electrochemical properties of LaNi5 alloy electrodes at 233 K was studied. The results indicated that the electrolyte concentration had great influence on discharge capacity and discharge voltage plateau of LaNi5 alloy electrode at 233 K, and the highest discharge capacity and discharge voltage plateau were both obtained at 6 mol/L KOH. When the KOH electrolyte concentration changed from 5 to 9 mol/L at 233 K, the high rate discharge ability (HRD) had the same change tendency as the diffusion coefficient, but the exchange current density did not change significantly, which implied that hydrogen diffusion was the control step at low temperature 233 K for discharge process of LaNi5 alloy electrode.

  19. 16 CFR 23.3 - Misuse of the terms “hand-made,” “hand-polished,” etc.

    Science.gov (United States)

    2010-01-01

    ... RULES GUIDES FOR THE JEWELRY, PRECIOUS METALS, AND PEWTER INDUSTRIES § 23.3 Misuse of the terms “hand... bulk sheet, strip, wire, and similar items that have not been cut, shaped, or formed into jewelry...

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

    International Nuclear Information System (INIS)

    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

  1. Simultaneous measurement of the neutron capture and fission yields of {sup 233}U

    Energy Technology Data Exchange (ETDEWEB)

    Berthoumieux, E.; Abbondanno, U.; Aerts, G.; Alvarez, H.A.; Alvarez-Velarde, F.A.; Andriamonje, S.; Andrzejewski, J.; Assimakopoulos, P.; Audouin, L.; Badurek, G.; Baumann, P.; Becvar, F.; Calvino, F.; Calviani, M.; 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.; Karadimos, D.; 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

    We have measured the neutron capture and fission cross section of {sup 233}U at the neutron time-of-flight facility n-TOF at CERN in the energy range from 1 eV to 1 MeV with high accuracy by using a high performance 4{pi} BaF{sub 2} Total Absorption Calorimeter (TAC) as a detection device. The method, based on the shape analysis of the TAC energy response, allowing to disentangle between {gamma}'s originating from fission and capture will be presented as well as the first very preliminary results. (authors)

  2. Gastrointestinal absorption and retention of plutonium-238 and uranium-233 in neonatal swine

    International Nuclear Information System (INIS)

    Newborn swine absorbed as much as one-half of a gavaged dose of 238Pu nitrate within 6 to 12 hr, and another one-fourth of the dose was retained in the stomach for up to 24 hr after intragastric administration. The small intestine accumulated one-third of the dose within 36 hr. Animals gavaged between 5 and 21 days of age absorbed decreasing amounts, especially at 14 and 21 days. Absorption of 233Pu (gavaged as the nitrate) by day-old pigs was similar to that of 238Pu

  3. Clinically abnormal case with paternally derived partial trisomy 8p23.3 to 8p12 including maternal isodisomy of 8p23.3: a case report

    Directory of Open Access Journals (Sweden)

    Thieme Heike

    2009-06-01

    Full Text Available Abstract Background Because of low copy repeats (LCRs and common inversion polymorphisms, the human chromosome 8p is prone to a number of recurrent rearrangements. Each of these rearrangements is associated with several phenotypic features. We report on a patient with various clinical malformations and developmental delay in connection with an inverted duplication event, involving chromosome 8p. Methods Chromosome analysis, multicolor banding analysis (MCB, extensive fluorescence in situ hybridization (FISH analysis and microsatellite analysis were performed. Results The karyotype was characterized in detail by multicolor banding (MCB, subtelomeric and centromere-near probes as 46,XY,dup(8(pter->p23.3::p12->p23.3::p23.3->qter. Additionally, microsatellite analysis revealed the paternal origin of the duplication and gave hints for a mitotic recombination involving about 6 MB in 8p23.3. Conclusion A comprehensive analysis of the derivative chromosome 8 suggested a previously unreported mechanism of formation, which included an early mitotic aberration leading to maternal isodisomy, followed by an inverted duplication of the 8p12p23.3 region.

  4. Process bases and specifications thorium---U-233 separations at the Purex Plant

    Energy Technology Data Exchange (ETDEWEB)

    Nielson, S.M.

    1965-07-26

    The Purex Plant was originally designed for the chemical processing of irradiated natural uranium. It has been used nearly exclusively for this purpose during its approximately ten-year operating lifetime. However, during the winter of 1964--1965, a special processing campaign was planned and accomplished in which approximately 6 tons of irradiated thoria targets were introduced to the plant, and the thorium-232 and uranium-233 were successfully separated and purified on a demonstration basis. For the demonstration thorium processing operation (6-ton test) of the winter of 1964--1965, process specifications were issued. These specifications were necessarily specific to the particular campaign inasmuch as a rather unusual processing scheme was required, by virtue of the small tonnage involved and the equipment limitations of the plant. Thus, for the relatively large operation subsequently planned, other process specifications are required. The purpose of this present document is to provide these specifications. Depending on the manner and extent of thorium -- uranium-233 production developments, these present specifications may have future application, at least in part. In addition to the process specifications, this document includes a section describing the flowsheet, and a section in which the technological bases for good process control are presented. In conjunction with the specifications, these sections are intended to provide the bases for the processing operations required to accomplish the processing objectives in a safe manner, and with minimum effect on equipment service life. All sections are organized in a manner to provide for relatively simple additions or revisions.

  5. Shutdown margin for high conversion BWRs operating in Th-{sup 233}U fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Shaposhnik, Y., E-mail: shaposhy@bgu.ac.il [NRCN – Nuclear Research Center Negev, POB 9001, Beer Sheva 84190 (Israel); Department of Nuclear Engineering, Ben-Gurion University of the Negev, POB 653, Beer Sheva 84105 (Israel); Shwageraus, E. [Department of Nuclear Engineering, Ben-Gurion University of the Negev, POB 653, Beer Sheva 84105 (Israel); Elias, E. [Faculty of Mechanical Engineering, Technion – Israel Institute of Technology, Technion City 32000, Haifa (Israel)

    2014-09-15

    Highlights: • BWR core operating in a closed self-sustainable Th-{sup 233}U fuel cycle. • Shutdown Margin in Th-RBWR design. • Fully coupled MC with fuel depletion and thermo-hydraulic feedback modules. • Thermal–hydraulic analysis includes MCPR observation. - Abstract: Several reactivity control system design options are explored in order to satisfy shutdown margin (SDM) requirements in a high conversion BWRs operating in Th-{sup 233}U fuel cycle (Th-RBWR). The studied core has an axially heterogeneous fuel assembly structure with a single fissile zone “sandwiched” between two fertile blanket zones. The utilization of an originally suggested RBWR Y-shape control rod in Th-RBWR is shown to be insufficient for maintaining adequate SDM to balance the high negative reactivity feedbacks, while maintaining fuel breeding potential, core power rating, and minimum Critical Power Ratio (CPR). Implementation of alternative reactivity control materials, reducing axial leakage through non-uniform enrichment distribution, use of burnable poisons, reducing number of pins as well as increasing pin diameter are also shown to be incapable of meeting the SDM requirements. Instead, an alternative assembly design, based on Rod Cluster Control Assembly with absorber rods was investigated. This design matches the reference ABWR core power and has adequate shutdown margin. The new concept was modeled as a single three-dimensional fuel assembly having reflective radial boundaries, using the BGCore system, which consists of the MCNP code coupled with fuel depletion and thermo-hydraulic feedback modules.

  6. Contribution to the study of 233U production with MOX-ThPu fuel in PWR reactor. Transition scenarios towards Th/233U iso-generating concepts in thermal spectrum. Development of the MURE fuel evolution code

    International Nuclear Information System (INIS)

    If nuclear power is to provide a significant fraction of the growing world energy demand, only through the breeding concept can the development of sustainable nuclear energy become a reality. The study of such a transition, from present-day nuclear technologies to future breeding concepts is therefore pertinent. Among these future concepts, those using the thorium cycle Th/U-233 in a thermal neutron spectrum are of particular interest; molten-salt type thermal reactors would allow for breeding while requiring comparatively low initial inventories of U-233. The upstream production of U-233 can be obtained through the use of thorium-plutonium mixed oxide fuel in present-day light water reactors. This work presents, firstly, the development of the MURE evolution code system, a C++ object-oriented code that allows the study, through Monte Carlo (M.C.) simulation, of nuclear reactors and the evolution of their fuel under neutron irradiation. The M.C. methods are well-suited for the study of any reactor, whether it'd be an existing reactor using a new kind of fuel or a future concept altogether, the simulation is only dependent on nuclear data. Exact and complex geometries can be simulated and continuous energy particle transport is performed. MURE is an interface with MCNP, the well-known and validated transport code, that allows, among other functionalities, to simulate constant power and constant reactivity evolutions. Secondly, the study of MOX ThPu fuel in a conventional light water reactor (REP) is presented; it explores different plutonium concentrations and isotopic qualities in order to evaluate their safety characteristics. Simulation of their evolution allows us to quantify the production of U-233 at the end of burnup. Last, different french scenarios validating a possible transition towards a park of thermal Th/U-233 breeders, are presented. In these scenarios, U-233 is produced in ThPu moxed light water reactors. (author)

  7. Calculation of the neutron induced fission cross-section of 233Pa up to 20 MeV

    International Nuclear Information System (INIS)

    Since very recently, direct measurements of the 233Pa(n,f) cross-section are available in the energy range from 1.0 to 8.5 MeV. This has stimulated a new, self-consistent, neutron cross-section evaluation for the n+233Pa system, in the incident neutron energy range 0.01-20 MeV. Since higher fission chances are involved also the lighter Pa-isotopes had to be re-evaluated in a consistent manner. The results are quite different compared to earlier evaluation attempts. Since 233Pa is a key isotope in the thorium based fuel cycle the quality of its reaction cross-sections is important for the modeling of future advanced fuel and reactor concepts. The present status of the evaluated libraries is that they differ by a factor of two in the absolute fission cross-section and also in the threshold energy value

  8. Shutdown Margin for High Conversion BWRs Operating in Th-233U Fuel Cycle

    CERN Document Server

    Shaposhnik, Yaniv; Elias, Ezra

    2013-01-01

    Several reactivity control system design options are explored in order to satisfy shutdown margin (SDM) requirements in a high conversion BWRs operating in Th-233U fuel cycle (Th-RBWR). The studied has an axially heterogeneous fuel assembly structure with a single fissile zone sandwiched between two fertile blanket zones. The utilization of an originally suggested RBWR Y-shape control rod in Th-RBWR is shown to be insufficient for maintaining adequate SDM to balance the high negative reactivity feedbacks, while maintaining fuel breeding potential, core power rating, and minimum Critical Power Ratio (CPR). Instead, an alternative assembly design, also relying on heterogeneous fuel zoning, is proposed for achieving fissile inventory ratio (FIR) above unity, adequate SDM and meeting minimum CPR limit at thermal core output matching the ABWR power. The new concept was modeled as a single 3-dimensional fuel assembly having reflective radial boundaries, using the BGCore system, which consists of the MCNP code coupl...

  9. Fuel utilization improvement in PWRs using the denatured /sup 233/U-Th cycle

    Energy Technology Data Exchange (ETDEWEB)

    Jones, H.M.; Schwenk, G.A.; Toops, E.C.; Yotinen, V.O.

    1980-06-01

    A number of changes in PWR core design and/or operating strategy were evaluated to assess the fuel utilization improvement achievable by their implementation in a PWR using thorium-based fuel and operating in a recycle mode. The reference PWR for this study was identical to the B and W Standard Plant except that the fuel pellets were of denatured (/sup 233/U//sup 238/U-Th)O/sub 2/. An initial scoping study identified the three most promising improvement concepts as (1) a very tight lattice, (2) thorium blankets, and (3) ThO/sub 2/ rods placed in available guide tubes. A conceptual core design incorporating these changes was then developed, and the fuel utilization of this modified design was compared with that of the reference case.

  10. Amster: a molten-salt reactor concept generating its own 233U and incinerating transuranium elements

    International Nuclear Information System (INIS)

    In the coming century, sustainable development of atomic energy will require the development of new types of reactors able to exceed the limits of the existing reactor types, be it in terms of optimum use of natural fuel resources, reduction in the production of long-lived radioactive waste, or economic competitiveness. Of the various candidates with the potential to meet these needs, molten-salt reactors are particularly attractive, in the light of the benefits they offer, arising from two fundamental features: - A liquid fuel does away with the constraints inherent in solid fuel, leading to a drastic simplification of the fuel cycle, in particular making in possible to carry out on-line pyrochemical reprocessing; - Thorium cycle and thermal spectrum breeding. The MSBR concept proposed by ORNL in the 1970's thus gave a breeding factor of 1.06, with a doubling time of about 25 years. However, given the tight neutron balance of the thorium cycle (the η of 233U is about 2.3), MSBR performance is only possible if there are strict constraints set on the in-line reprocessing unit: all the 233Pa must be removed from the core so that it can decay on the 233U in no more than about ten days (or at least 15 tonnes of salt to be extracted from the core daily), and the absorbing fission products, in particular the rare earths, must be extracted in about fifty days. With the AMSTER MSR concept, which we initially developed for incinerating transuranium elements, we looked to reduce the mass of salt to be reprocessed in order to minimise the size and complexity of the reprocessing unit coupled to the reactor, and the quantity of transuranium elements sent for disposal, as this is directly proportional to the mass of salt reprocessed for extraction of the fission products. Given that breeding was not an absolute necessity, because the reactor can be started by incinerating the transuranium elements from the spent fuel assemblies of current reactors, or if necessary by loading

  11. Yeast Interacting Proteins Database: YLR166C, YGL233W [Yeast Interacting Proteins Database

    Lifescience Database Archive (English)

    Full Text Available YLR166C SEC10 Essential 100kDa subunit of the exocyst complex (Sec3p, Sec5p, Sec6p,... Sec8p, Sec10p, Sec15p, Exo70p, and Exo84p), which has the essential function of mediating polarized targeti...s prey (0) YGL233W SEC15 Essential 113kDa subunit of the exocyst complex (Sec3p, ...ait ORF YLR166C Bait gene name SEC10 Bait description Essential 100kDa subunit of the exocyst complex (Sec3p..., Sec5p, Sec6p, Sec8p, Sec10p, Sec15p, Exo70p, and Exo84p), which has the essential function of mediating po

  12. Final characterization report for the non-process areas of the 233-S Plutonium Concentration Facility

    International Nuclear Information System (INIS)

    This report addresses the 233-S Plutonium Concentration Facility characterization survey data collected from January 21, 1997 through February 3, 1997. The characterization activities evaluated the radiological status and identified the hazardous materials locations. The scope of this report is limited to the nonprocess areas in the facility, which include the special work permit (SWP) change room, toilet, equipment room, electrical cubicle, control room, and pipe gallery. A portion of the roof (excluding the roof over the process hood and viewing room) was also included. Information in this report will be used to identify waste streams, provide specific chemical and radiological data to aid in planning decontamination and demolition activities, and allow proper disposal of the demolition debris, as required by the Comprehensive Environmental Response, Compensation, and Liability Act of 1980

  13. 233U mass yield measurements around and within the symmetry region with the ILL Lohengrin spectrometer

    Science.gov (United States)

    Chebboubi, A.; Kessedjian, G.; Sage, C.; Bernard, D.; Blanc, A.; Faust, H.; Köster, U.; Litaize, O.; Mutti, P.; Serot, O.

    2016-03-01

    The study of fission yields has a major impact on the characterization and understanding of the fission process and is mandatory for reactor applications. The LPSC in collaboration with ILL and CEA has developed a measurement program on fission fragment distributions at the Lohengrin spectrometer of the ILL, with a special focus on the masses constituting the heavy peak. We will present in this paper our measurement of the very low fission yields in the symmetry mass region and the heavy mass wing of the distribution for 233U thermal neutron induced fission. The difficulty due to the strong contamination by other masses with much higher yields will be addressed in the form of a new analysis method featuring the required contaminant correction. The apparition of structures in the kinetic energy distributions and possible interpretations will be discussed, such as a possible evidence of fission modes.

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

    International Nuclear Information System (INIS)

    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)

  15. 25 CFR 900.233 - When must an Indian tribe or tribal organization regulate its employees or subcontractors to...

    Science.gov (United States)

    2010-04-01

    ... Conflicts of Interest § 900.233 When must an Indian tribe or tribal organization regulate its employees or subcontractors to avoid a personal conflict of interest? An Indian tribe or tribal organization must maintain... 25 Indians 2 2010-04-01 2010-04-01 false When must an Indian tribe or tribal organization...

  16. 45 CFR 233.34 - Computing the assistance payment in the initial one or two months (AFDC).

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 2 2010-10-01 2010-10-01 false Computing the assistance payment in the initial... § 233.34 Computing the assistance payment in the initial one or two months (AFDC). A State shall compute...) If the initial month is computed prospectively as in paragraph (a) of this section, the second...

  17. 29 CFR 2.33 - Responsibilities of DOL, DOL social service providers and State and local governments...

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 1 2010-07-01 2010-07-01 true Responsibilities of DOL, DOL social service providers and... Organizations; Protection of Religious Liberty of Department of Labor Social Service Providers and Beneficiaries § 2.33 Responsibilities of DOL, DOL social service providers and State and local...

  18. Characterization of the HBB: c.*233G > C Variant: No Evidence of a β-Thalassemic Phenotype.

    Science.gov (United States)

    Smith, Debra L; Mitui, Midori; Park, Jason Y; Luu, Hung S; Timmons, Charles F

    2016-01-01

    β-Thalassemia (β-thal) results from homozygous or compound heterozygous inheritance of β-globin alleles that yield decreased or absent synthesis of the β chain. Disease is frequently severe, requiring lifelong transfusion therapy. Heterozygosity for a β-thal allele results in an asymptomatic carrier state with mild but characteristic hematological findings. More than 200 β-globin alleles have been demonstrated to produce β-thal. For populations with a high prevalence of β-thal, screening for carrier status, genetic counseling and prenatal diagnosis are important components of efforts to both reduce disease incidence and provide early diagnosis and treatment. It is therefore important to define and characterize potential β-thal alleles. We sought to further characterize the previously reported β-thal allele, HBB: c.*233G > C. This variant is provisionally included in the HbVar database based on a study of Palestinians in the Gaza Strip with β-thal disease or carrier status (known or suspected) where 4.2% of subjects were found to have HBB: c.*233G > C. In our patient population, we detected the HBB: c.*233G > C variant in 17.3% of individuals (17 heterozygotes, one homozygote) undergoing β hemoglobin (Hb) gene sequencing at our laboratory over a 25-month period. Hematological parameters were analyzed to determine if these individuals demonstrated findings consistent with inheritance of a β-thal allele. Individuals with the HBB: c.*233G > C variant did not demonstrate any abnormalities in hematological parameters characteristic of β-thal carrier state (17 heterozygotes) or clinical evidence of disease (homozygote). Our data demonstrate no evidence for pathogenicity of the HBB: c.*233G > C variant but rather demonstrate that this variant is a common benign polymorphism.

  19. Analysis of evolution and virological characteristics of rtI233V mutations in the hepatitis B virus reverse transcriptase domain

    Directory of Open Access Journals (Sweden)

    Xiao-ling YE

    2015-04-01

    Full Text Available Objective To analyze the evolution of rtI233V mutation in the reverse transcriptase domain of hepatitis B virus (HBV and its association with adefovir dipivoxil (ADV resistance. Methods The rate of detection of rtI233V mutation in 9830 patients with chronic HBV infection was analyzed. HBV reverse transcriptase genes isolated from serial serum samples of two patients were amplified by nested PCR, and clonal sequencing (>20 clones/sample was performed to analyze the evolution of rtI233V mutations. The replica of pTriEx-HBV1.1 vectors harboring wild-type and mutant strains (rtI233V, rtN236T, rtI233V+rtN236T were respectively constructed and transiently transfected into HepG2 cells. Media containing serial concentrations of lamivudine (LAM, ADV, entecavir (ETV, or tenofovir (TDF were used to treat the cells. Then HBV DNA in the supernatants was quantitatively determined by real-time PCR in order to analyze HBV mutants' replication competence and phenotypic characteristics under the drug pressures. Results The detection rate of rtI233V mutation in 9830 nucleos(tide analogues-treated patients was 0.28% (28/9830, including 0.19% (19 patients with rtI233V individual mutation and 0.09% (9 patients with rtI233V mutation combining with rtN236T or other mutations. All of the patients had rtI233V had ADV exposure history: 16 (57.1% of them received ADV monotherapy for over six months, and 12(42.9% of them received ADV combined sequential therapy for over 12 months. Replication competence and phenotypic resistance analysis showed rtI233V and wild-type strains had similar viral replication competence, while rtN236T exhibited significantly lower replication competence compared with wild-type strains. rtI233V strains remained sensitive to LAM, ADV, ETV, and TDF and showed little influence on drug resistance when combined with rtN236T, but it showed ability to restore the defected replication capacity of rtN236T strains. Conclusions  The rtI233V mutation

  20. Measurements of neutron induced capture and fission reactions on $^{233}$ U (EAR1)

    CERN Multimedia

    The $^{233}$U plays the essential role of ssile nucleus in the Th-U fuel cycle, which has been proposed as a safer and cleaner alternative to the U-Pu fuel cycle. Considered the scarce data available to assess the capture cross section, a measurement was proposed and successfully performed at the n_TOF facility at CERN using the 4$\\pi$ Total Absorp- tion Calorimeter (TAC). The measurement was extremely dicult due to the need to accurately distinguish between capture and fission $\\gamma$-rays without any additional discrim-ination tool and the measured capture cross section showed a signicant disagreement in magnitude when compared with the ENDF/B-VII.1 library despite the agreement in shape. We propose a new measurement that is aimed at providing a higher level of dis-crimination between competing nuclear reactions, to extend the neutron energy range and to obtain more precise and accurate data, thus fullling the demands of the "NEA High Priority Nuclear Data Request List". The setup is envisaged as a combin...

  1. Site-Specific Health and Safety Plan, 233-S Decontamination and Decommissioning

    International Nuclear Information System (INIS)

    The 233-S Facility operated from January 1952 until July 1967, at which time the building entered the U.S. Department of Energy's Surplus Facility Management Program as a retired facility. The facility has since undergone severe degradation due to exposure to extreme weather conditions. A freeze and thaw cycle occurred at the Hanford Site during February 1996, which caused cracking failure of portions of the building roof. This resulted in significant infiltration of water into the facility, which creates a pathway for potential release of radioactive material into the environment (air and/or ground). Additionally, the weather caused existing cracks in concrete structures of the building to lengthen, thereby increasing the potential for failed confinement of the building's radioactive material. Differential settlement has also occurred, causing portions of the facility to separate from the main building structure, increasing the potential for release of radioactive material to the environment. An expedited response is proposed to remove this threat and ensure protection of human health and the environment

  2. Nylon and teflon scribe effect on NBR to Chemlok 233 and NBR to NBR bond interfaces

    Science.gov (United States)

    Jensen, S. K.

    1990-01-01

    A study was requested by Manufacturing Engineering to determine what effects marking with nylon (6/6) and Teflon scribes may have on subsequent bonding. Witness panel bond specimens were fabricated by the development lab to test both acrylonitrile butadiene rubber (NBR) to Chemlok and NBR to NBR after controlled exposure. The nylon rod used as a scribe tool demonstrates virtually no bond deterioration when used to scribe lines on either the Chemlok to NBR surfaces or the NBR to NBR interface. Lab test results indicate that the nylon rod-exposed samples produce tensile and peel values very similar to the control samples and the Teflon exposed samples produce tensile and peel values much lower than the control samples. Visual observation of the failure surfaces of the tested samples shows that Teflon scribing produces an obvious contamination to the surface and the nylon produces no effect. Photographs of test samples are provided. It is concluded that Teflon stock used as a scribe tool on a Chemlok 233 to NBR surface or an NBR to NBR surface has a detrimental effect on the bond integrity on either of these bond interfaces. Therefore, it is recommended that the nylon rod continue to be used where a scribe line is required in the redesigned solid rocket motor segment insulation layup operations. The use of Teflon scribes should not be considered.

  3. Rapid oxygenation of Earth's atmosphere 2.33 billion years ago.

    Science.gov (United States)

    Luo, Genming; Ono, Shuhei; Beukes, Nicolas J; Wang, David T; Xie, Shucheng; Summons, Roger E

    2016-05-01

    Molecular oxygen (O2) is, and has been, a primary driver of biological evolution and shapes the contemporary landscape of Earth's biogeochemical cycles. Although "whiffs" of oxygen have been documented in the Archean atmosphere, substantial O2 did not accumulate irreversibly until the Early Paleoproterozoic, during what has been termed the Great Oxygenation Event (GOE). The timing of the GOE and the rate at which this oxygenation took place have been poorly constrained until now. We report the transition (that is, from being mass-independent to becoming mass-dependent) in multiple sulfur isotope signals of diagenetic pyrite in a continuous sedimentary sequence in three coeval drill cores in the Transvaal Supergroup, South Africa. These data precisely constrain the GOE to 2.33 billion years ago. The new data suggest that the oxygenation occurred rapidly-within 1 to 10 million years-and was followed by a slower rise in the ocean sulfate inventory. Our data indicate that a climate perturbation predated the GOE, whereas the relationships among GOE, "Snowball Earth" glaciation, and biogeochemical cycling will require further stratigraphic correlation supported with precise chronologies and paleolatitude reconstructions.

  4. Comparison on Decay Process of Explosive Products for 233U and Weapon-grade Plutonium%233U 和武器级钚的爆炸产物放射性衰变过程的比较

    Institute of Scientific and Technical Information of China (English)

    沈姚崧; 刘成安

    2000-01-01

    233U 模型和武器级钚模型核爆炸后爆炸产物的放射性活度、生物潜在危害因子和能量沉积等量进行了比较, 分析了武器级钚模型中上述各量的演化情况.

  5. Qualification and initial characterization of a high-purity 233U spike for use in uranium analyses

    International Nuclear Information System (INIS)

    Several high-purity 233U items potentially useful as isotope dilution mass spectrometry standards for safeguards, non-proliferation, and nuclear forensics measurements are identified and rescued from downblending. By preserving the supply of 233U materials of different pedigree for use as source materials for certified reference materials (CRMs), it is ensured that the safeguards community has high quality uranium isotopic standards required for calibration of the analytical instruments. One of the items identified as a source material for a high-purity CRM is characterized for the uranium isotope-amount ratios using thermal ionization mass spectrometry (TIMS). Additional verification measurements on this material using quadrupole inductively coupled plasma mass spectrometry (ICPMS) are also performed. As a result, the comparison of the ICPMS uranium isotope-amount ratios with the TIMS data, with much smaller uncertainties, validated the ICPMS measurement practices. ICPMS is proposed for the initial screening of the purity of items in the rescue campaign

  6. ALARA Review of the Activation/Repair of Fire Detectors in Zone Three at the 233-S Facility

    International Nuclear Information System (INIS)

    A formal as low as reasonably achievable (ALARA) review is required by BHI-SH-02, Vol. 1, Procedure 1.22, 'Planning Radiological Work', when radiological conditions exceed trigger levels. The level of contamination inside the viewing room meets this criterion. This ALARA review is for task instruction 1997-03-18-005-8.3.3 (mini task instruction to a living work package), 'Instructions for D ampersand D Support of Fire Detector Troubleshooting and Minor Maintenance Work at 233-S,' and DynCorp 2G-98-7207C, '233-S Reconnect Smoke Detectors Zone 3.' The Radiological Work Permit (RWP) request broke these two task instructions into four separate tasks. The four tasks identified in the RWP request were used to estimate airborne concentrations and the total exposure

  7. Photofission cross sections of U-233 and Pu-239 near threshold induced by gamma-rays from thermal neutron capture

    International Nuclear Information System (INIS)

    The photofission cross sections of U-233 and PU-239 have been studied using monochromatic photons produced by thermal neutron capture in several materials placed in a radial beam hole of the IEA-R1, 2 MW pool type research reactor, in the energy interval from 5.43 MeV to 9.72 MeV. The gamma flux incident on the samples were measured using a (3X3) inch. NaI(Tl) crystal. The photofission fragments were detected in MAKROFOL-KG (solid state nuclear track detector) etched 30 min. in a KOH (35%wt) solution at 600C. The efficiency of the detector was obtained using a Californium-252 calibrated source and its value was (0.4323 ± 3%). The tracks were counted by means of an automatic spark counting. Analyzing the photofission data we have observed similarities between the cross sections obtained for the two samples in comparison with other authors. A structure was also observed in the U-233 cross section near the energy of 7.23 MeW. Acoording to the liquid drop model the height of the simple fission barrier were determined: (5.6 ± 0.2) MeV and (5.7 ± 0.2) MeV for U-233 and Pu-239 respectively. The relative fissionability of the samples to U-238 were also determined in each excitation energy and showed to be energy independent: (2.12 +-0.25) for U-233, and (3.32+-0.41) for Pu-239. (author)

  8. Defense In-Depth Accident Analysis Evaluation of Tritium Facility Bldgs. 232-H, 233-H, and 234-H

    International Nuclear Information System (INIS)

    'The primary purpose of this report is to document a Defense-in-Depth (DID) accident analysis evaluation for Department of Energy (DOE) Savannah River Site (SRS) Tritium Facility Buildings 232-H, 233-H, and 234-H. The purpose of a DID evaluation is to provide a more realistic view of facility radiological risks to the offsite public than the bounding deterministic analysis documented in the Safety Analysis Report, which credits only Safety Class items in the offsite dose evaluation.'

  9. Molecular Gas and Dust in the Massive Star Forming Region S 233 IR

    Institute of Scientific and Technical Information of China (English)

    Rui-Qing Mao; Qin Zeng

    2004-01-01

    The massive star forming region S 233 IR is observed in the molecular lines CO J = 2-1, 3-2, NH3 (1,1), (2,2) and the 870μm dust continuum. Four submillimeter continuum sources, labelled SMM 1-4, are revealed in the 870μm dust emission. The main core, SMM1, is found to be associated with a deeply embedded near infrared cluster in the northeast; while the weaker source SMM2 coincides with a more evolved cluster in the southwest. The best fit spectral energy distribution of SMM1 gives an emissivity ofβ = 1.6, and temperatures of 32 K and 92 K for the cold- and hot-dust components. An SMM1 core mass of 246 M⊙ and a total mass of 445 M⊙ are estimated from the 870 μm dust continuum emission.SMM1 is found to have a temperature gradient decreasing from inside out, indicative of the presence of interior heating sources. The total outflow gas mass as traced by the CO J - 3-2 emission is estimated to be 35 M⊙. Low velocity outflows are also found in the NH3 (1,1) emission. The non-thermal dominant NH3 line width as well as the substantial core mass suggest that the SMM1 core is a "turbulent,massive dense core", in the process of forming a group or a cluster of stars. The much higher star formation efficiency found in the southwest cluster supports the suggestion that this cluster is more evolved than the northeast one. Large near infrared photometric variations found in the source PCS-IR93, a previously found highly polarized nebulosity, indicate an underlying star showing the FU Orionis type of behavior.

  10. Fc Gamma Receptor 3B (FCGR3Bc.233C>A-rs5030738) Polymorphism Modifies the Protective Effect of Malaria Specific Antibodies in Ghanaian Children

    DEFF Research Database (Denmark)

    Adu, Bright; Jepsen, Micha Phill Grønholm; Gerds, Thomas A;

    2014-01-01

    Immunoglobulin G (IgG) cross-linking with Fc gamma receptor IIIB (FcγRIIIB) triggers neutrophil degranulation, releasing reactive oxygen species with high levels associated with protection against malaria. The FCGR3B-c.233C>A polymorphism thought to influence the interaction between IgG and FcγRI...... compared with 233CC children. This genotype related effect modification may significantly influence malaria sero-epidemiological and vaccine trial studies....

  11. Autoimmune diseases induced by TNF-targeted therapies: analysis of 233 cases.

    Science.gov (United States)

    Ramos-Casals, Manuel; Brito-Zerón, Pilar; Muñoz, Sandra; Soria, Natalia; Galiana, Diana; Bertolaccini, Laura; Cuadrado, Maria-Jose; Khamashta, Munther A

    2007-07-01

    Tumor necrosis factor (TNF)-targeted therapies are increasingly used for a rapidly expanding number of rheumatic and autoimmune diseases. With this use and longer follow-up periods of treatment, there are a growing number of reports of the development of autoimmune processes related to anti-TNF agents. We have analyzed the clinical characteristics, outcomes, and patterns of association with the different anti-TNF agents used in all reports of autoimmune diseases developing after TNF-targeted therapy found through a MEDLINE search of articles published between January 1990 and December 2006. We identified 233 cases of autoimmune diseases (vasculitis in 113, lupus in 92, interstitial lung diseases in 24, and other diseases in 4) secondary to TNF-targeted therapies in 226 patients. The anti-TNF agents were administered for rheumatoid arthritis (RA) in 187 (83%) patients, Crohn disease in 17, ankylosing spondylitis in 7, psoriatic arthritis in 6, juvenile RA in 5, and other diseases in 3. The anti-TNF agents administered were infliximab in 105 patients, etanercept in 96, adalimumab in 21, and other anti-TNF agents in 3. We found 92 reported cases of lupus following anti-TNF therapy (infliximab in 40 cases, etanercept in 37, and adalimumab in 15). Nearly half the cases fulfilled 4 or more classification criteria for systemic lupus erythematosus (SLE), which fell to one-third after discarding preexisting lupus-like features. One hundred thirteen patients developed vasculitis after receiving anti-TNF agents (etanercept in 59 cases, infliximab in 47, adalimumab in 5, and other agents in 2). Leukocytoclastic vasculitis was the most frequent type of vasculitis, and purpura was the most frequent cutaneous lesion. A significant finding was that one-quarter of patients with vasculitis related to anti-TNF agents had extracutaneous involvement. Twenty-four cases of interstitial lung disease associated with the use of anti-TNF agents were reported. In these patients, 2 specific

  12. Photonuclear reactions of U-233 and Pu-239 near threshold induced by thermal neutron capture gamma rays

    International Nuclear Information System (INIS)

    The photonuclear cross sections of U-293 and Pu-239 have been studied by using monochromatic and discrete photons, in the energy interval from 5.49 to 9.72 MeV, produced by thermal neutron capture. The gamma fluxes incident on the samples were measured using a ( 3 x 3 )'' NaI (TI) crystal. The photofission fragments were detected in Makrofol-Kg (SSNTD). A possible structure was observed in the U-233 cross sections, near 7.23 MeV. The relative fissionability of the nuclides was determined at each excitation energy and shown to be energy independent: ( 2.12 ± 0.25) for U-233 and ( 3.32 ± 0.41 ) for Pu-239. The angular distribution of photofission fragments of Pu-239 were measured at two mean excitation energies of 5.43 and 7.35 MeV. An anisotropic distribution of ( 12.2 ± 3.6 ) % was observed at 5.43 MeV. The total neutron cross sections were measured by using a long counter detector. The photoneutron cross sections were calculated by using energy dependent neutron multiplicities values, γ(E), obtained in the literature. The competition Γn/γf was also determined at each excitation energy, and shown to be energy independent: ( 0.54 ± 0.05 ) for U-233 and ( 0.44 ± 0.05 ) for Pu-239, and were correlated to the parameters Z sup(2)/A, ( Ef'-Bn'), A. According to the FUJIMOTO-YAMAGUCHI and CONSTANT NUCLEAR TEMPERATURE models, the nuclear temperatures were calculated. The total photoabsorption cross sections were also calculated as a sum of the photofission and photoneutron cross sections at each energy excitation. From these results the competition Γf/ΓA, called fission probability Pf, were obtained: ( 0.66 ± 0.02) for U-233 and ( 0.70 ± 0.02 ) for Pu-239. (author)

  13. Fractional independent yields of 141La and 142La from thermal-neutron-induced fission of 233U

    International Nuclear Information System (INIS)

    The fractional independent yields of 141La and 142La from thermal-neutron-induced fission of 233U were found to be 0.026 +- 0.006 and 0.068 +- 0.010, respectively. These yields are consistent with charge distributions for which σ = 0.56 +- 0.02 and 0.52 +- 0.02, respectively. These results are in good agreement with similar yields measured for fission of 235U, but not with those from fission of 249Cf. (author)

  14. Measurement of the ionization yield of nuclear recoils in liquid argon at 80 and 233 keV

    CERN Document Server

    Bondar, A; Dolgov, A; Grishnyaev, E; Polosatkin, S; Shekhtman, L; Shemyakina, E; Sokolov, A

    2014-01-01

    The energy calibration of nuclear recoil detectors is of primary importance to rare-event experiments such as those of direct dark matter search and coherent neutrino-nucleus scattering. In particular, such a calibration is performed by measuring the ionization yield of nuclear recoils in liquid Ar and Xe detection media, using neutron elastic scattering off nuclei. In the present work, the ionization yield for nuclear recoils in liquid Ar has for the first time been measured in the higher energy range, at 80 and 233 keV, using a two-phase Cryogenic Avalanche Detector (CRAD) and DD neutron generator. The ionization yield in liquid Ar at an electric field of 2.3 kV/cm amounted to 7.8+/-1.1 and 9.7+/-1.3 e-/keV at 80 and 233 keV respectively. Neither Jaffe model for nuclear recoil-induced ionization nor that of Thomas-Imel can consistently describe the energy dependence of the ionization yield.

  15. Calculation of Prompt Fission Neutron from 233U(n, f) Reaction by Multi-Modal Los Alamos Model%Calculation of Prompt Fission Neutron from 233U(n, f) Reaction by Multi-Modal Los Alamos Model

    Institute of Scientific and Technical Information of China (English)

    郑娜; 钟春来; 樊铁栓

    2012-01-01

    An attempt is made to improve the evaluation of the prompt fission neutron emis- sion from 233U(n, f) reaction for incident neutron energies below 6 MeV. The multi-modal fission approach is applied to the improved version of Los Alamos model and the point by point model. The prompt fission neutron spectra and the prompt fission neutron as a function of fragment mass (usually named "sawtooth" data) v(A) are calculated independently for the three most dominant fission modes (standard I, standard II and superlong), and the total spectra and v(A) are syn- thesized. The multi-modal parameters are determined on the basis of experimental data of fission fragment mass distributions. The present calculation results can describe the experimental data very well, and the proposed treatment is thus a useful tool for prompt fission neutron emission prediction.

  16. Contribution to the study of {sup 233}U production with MOX-ThPu fuel in PWR reactor. Transition scenarios towards Th/{sup 233}U iso-generating concepts in thermal spectrum. Development of the MURE fuel evolution code; Contribution a l'etude de la production d'{sup 233}U en combustible MOX-ThPu en reacteur a eau sous pression. Scenarios de transition vers des concepts isogenerateurs Th/{sup 233}U en spectre thermique. Developpement du code MURE d'evolution du combustible

    Energy Technology Data Exchange (ETDEWEB)

    Michel-Sendis, F

    2006-12-15

    If nuclear power is to provide a significant fraction of the growing world energy demand, only through the breeding concept can the development of sustainable nuclear energy become a reality. The study of such a transition, from present-day nuclear technologies to future breeding concepts is therefore pertinent. Among these future concepts, those using the thorium cycle Th/U-233 in a thermal neutron spectrum are of particular interest; molten-salt type thermal reactors would allow for breeding while requiring comparatively low initial inventories of U-233. The upstream production of U-233 can be obtained through the use of thorium-plutonium mixed oxide fuel in present-day light water reactors. This work presents, firstly, the development of the MURE evolution code system, a C++ object-oriented code that allows the study, through Monte Carlo (M.C.) simulation, of nuclear reactors and the evolution of their fuel under neutron irradiation. The M.C. methods are well-suited for the study of any reactor, whether it'd be an existing reactor using a new kind of fuel or a future concept altogether, the simulation is only dependent on nuclear data. Exact and complex geometries can be simulated and continuous energy particle transport is performed. MURE is an interface with MCNP, the well-known and validated transport code, that allows, among other functionalities, to simulate constant power and constant reactivity evolutions. Secondly, the study of MOX ThPu fuel in a conventional light water reactor (REP) is presented; it explores different plutonium concentrations and isotopic qualities in order to evaluate their safety characteristics. Simulation of their evolution allows us to quantify the production of U-233 at the end of burnup. Last, different french scenarios validating a possible transition towards a park of thermal Th/U-233 breeders, are presented. In these scenarios, U-233 is produced in ThPu moxed light water reactors. (author)

  17. Investigation of the fission yields of the fast neutron-induced fission of {sup 233}U; Mesure de la distribution en masse et en charge des produits de la fission rapide de l'{sup 233}U

    Energy Technology Data Exchange (ETDEWEB)

    Galy, J

    1999-09-01

    As a stars, a survey of the different methods of investigations of the fission product yields and the experimental data status have been studied, showing advantages and shortcomings for the different approaches. An overview of the existing models for the fission product distributions has been as well intended. The main part of this thesis was the measurement of the independent yields of the fast neutron-induced fission of{sup 233}U, never investigated before this work. The experiment has been carried out using the mass separator OSIRIS (Isotope Separator On-Line). Its integrated ion-source and its specific properties required an analysis of the delay-parameter and ionisation efficiency for each chemical species. On the other hand, this technique allows measurement of independent yields and cumulative yields for elements from Cu to Ba, covering most of the fission yield distribution. Thus, we measured about 180 independent yields from Zn (Z=30) to Sr (Z=38) in the mass range A=74-99 and from Pd (Z=46) to Ba (Z=56) in the mass range A=113-147, including many isomeric states. An additional experiment using direct {gamma}-spectroscopy of aggregates of fission products was used to determine more than 50 cumulative yields of element with half-life from 15 min to a several days. All experimental data have been compared to estimates from a semi-empirical model, to calculated values and to evaluated values from the European library JEF 2.2. Furthermore, a study of both thermal and fast neutron-induced fission of {sup 233}U measured at Studsvik, the comparison of the OSIRIS and LOHENGRIN facilities and the trends in new data for the Reactors Physics have been discussed. (author)

  18. Cost-based optimizations of power density and target-blanket modularity for {sup 232}Th/{sup 233}U-based ADEP

    Energy Technology Data Exchange (ETDEWEB)

    Krakowski, R.A.

    1995-07-01

    A cost-based parametric systems model is developed for an Accelerator-Driven Energy Production (ADEP) system based on a {sup 232}Th/{sup 233}U fuel cycle and a molten-salt (LiF/BeF{sub 2}/ThF{sub 3}) fluid-fuel primary system. Simplified neutron-balance, accelerator, reactor-core, chemical-processing, and balance-of-plant models are combined parametrically with a simplified costing model. The main focus of this model is to examine trade offs related to fission power density, reactor-core modularity, {sup 233}U breeding rate, and fission product transmutation capacity.

  19. Multiplicity and energy of neutrons from {sup 233}U(n{sub th},f) fission fragments

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-03-01

    The correlation between fission fragments and prompt neutrons from the reaction {sup 233}U(n{sub th},f) was measured with improved accuracy. The results determined the neutron multiplicity and emission energy as a function of fragment mass and total kinetic energy. The average energy as a function of fragment mass followed a nearly symmetric distribution centered about the equal mass-split and formed a remarkable contrast with the saw-tooth distribution of the average neutron multiplicity. The neutron multiplicity from the specified fragment decreases linearly with total kinetic energy, and the slope of multiplicity with kinetic energy had the minimum value at about 130 u. The level density parameter versus mass determined from the neutron data showed a saw-tooth structure with the pronounced minimum at about 128 and generally followed the formula by Gilbert and Cameron, suggesting that the neutron emission process was very much affected by the shell-effect of the fission fragment. (author)

  20. Within the framework of the new fuel cycle {sup 232}Th/{sup 233}U, determination of the {sup 233}Pa(n.{gamma}) radiative capture cross section for neutron energies ranging between 0 and 1 MeV; Dans le cadre du nouveau cycle de combustible {sup 232}Th/{sup 233}U, determination de la section efficace de capture radiative {sup 233}Pa(n,{gamma}) pour des energies de neutrons comprises entre 0 et 1 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Boyer, S

    2004-10-15

    The Thorium cycle Th{sup 232}/U{sup 233} may face brilliant perspectives through advanced concepts like molten salt reactors or accelerator driven systems but it lacks accurate nuclear data concerning some nuclei. Pa{sup 233} is one of these nuclei, its high activity makes the direct measurement of its radiative neutron capture cross-section almost impossible. This difficulty has been evaded by considering the transfer reaction Th{sup 232}(He{sup 3},p)Pa{sup 234}* in which the Pa{sup 234} nucleus is produced in various excited states according to the amount of energy available in the reaction. The first chapter deals with the thorium cycle and its assets to contribute to the quenching of the fast growing world energy demand. The second chapter gives a detailed description of the experimental setting. A scintillation detector based on deuterated benzene (C{sub 6}D{sub 6}) has been used to counter gamma ray cascades. The third chapter is dedicated to data analysis. In the last chapter we compare our experimental results with ENDF and JENDL data and with computed values from 2 statistical models in the 0-1 MeV neutron energy range. Our results disagree clearly with evaluated data: our values are always above ENDF and JENDL data but tend to near computed values. We have also perform the measurement of the radiative neutron cross-section of Pa{sup 231} for a 110 keV neutron: {sigma}(n,{gamma}) 2.00 {+-} 0.14 barn. (A.C.)

  1. Utilization of non-weapons-grade plutonium and highly enriched uranium with breeding of the 233U isotope in the VVER reactors using thorium and heavy water

    Science.gov (United States)

    Marshalkin, V. E.; Povyshev, V. M.

    2015-12-01

    A method for joint utilization of non-weapons-grade plutonium and highly enriched uranium in the thorium-uranium—plutonium oxide fuel of a water-moderated reactor with a varying water composition (D2O, H2O) is proposed. The method is characterized by efficient breeding of the 233U isotope and safe reactor operation and is comparatively simple to implement.

  2. Utilization of non-weapons-grade plutonium and highly enriched uranium with breeding of the 233U isotope in the VVER reactors using thorium and heavy water

    International Nuclear Information System (INIS)

    A method for joint utilization of non-weapons-grade plutonium and highly enriched uranium in the thorium–uranium—plutonium oxide fuel of a water-moderated reactor with a varying water composition (D2O, H2O) is proposed. The method is characterized by efficient breeding of the 233U isotope and safe reactor operation and is comparatively simple to implement

  3. Measurement of the fission cross section induced by fast neutrons of the {sup 232}Th/{sup 233}U nuclei within the innovating fuel cycles framework; Mesure de la section efficace de fission induite par neutrons rapides des noyaux {sup 232}Th/{sup 233}U dans le cadre des cycles de combustible innovants

    Energy Technology Data Exchange (ETDEWEB)

    Grosjean, C

    2005-03-15

    The thorium-U{sup 233} fuel cycle might provided safer and cleaner nuclear energy than the present Uranium/Pu fuelled reactors. Over the last 10 years, a vast campaign of measurements has been initiated to bring the precision of neutron data for the key nuclei (Th{sup 232}, Pa{sup 233} and U{sup 233}) at the level of those for the U-Pu cycle. This is the framework of these measurements, the energy dependent neutron induced fission cross section of Th{sup 232} and U{sup 233} has been measured from 1 to 7 MeV with a target accuracy lesser than 5 per cent. These measurements imply the accurate determination of the fission rate, the number of the target nuclei as well as the incident neutron flux impinging on the target, the latter has been obtained using the elastic scattering (n,p). The cross section of which is very well known in a large neutron energy domain ({approx} 0,5 % from 1 eV to 50 MeV) compared to the U{sup 235}(n,f) reaction. This technique has been applied for the first time to the Th{sup 232}(n,f) and U{sup 233}(n,f) cases. A Hauser-Feshbach statistical model has been developed. It consists of describing the different decay channels of the compound nucleus U{sup 234} from 0,01 to 10 MeV neutron energy. The parameters of this model were adjusted in order to reproduce the measured fission cross section of U{sup 233}. From these parameters, the cross sections from the following reactions could be extracted: inelastic scattering U{sup 233}(n,n'), radiative capture U{sup 233}(n,{gamma}) and U{sup 233}(n,2n). These cross sections are still difficult to measure by direct neutron reactions. The calculated values have allowed us to fill the lack of experimental data for the major fissile nucleus of the thorium cycle. (author)

  4. Reforma tributária: os efeitos macroeconômicos e setoriais da PEC 233/2008

    Directory of Open Access Journals (Sweden)

    Nelson Leitão Paes

    2011-06-01

    Full Text Available A despeito de um histórico desalentador, o atual governo enviou nova proposta de reforma tributária ao Congresso Nacional, a PEC 233/2008. A proposta unifica alguns tributos federais do consumo no IVA-F, simplifica e diminui drasticamente a legislação do ICMS, alivia a tributação sobre a folha de pagamento e bens essenciais e desonera investimentos. Para a análise do impacto destas mudanças, foi construído um modelo de equilíbrio geral, que contempla 55 firmas no lado produtivo da economia. Os resultados sugerem que do lado agregado haverá modesta expansão do produto, consumo, emprego e investimento, com pequena perda de arrecadação e aumento de bem-estar. Houve substanciais alterações no produto setorial, com uma tendência de aumento dos setores industrial e agropecuário em detrimento dos serviços.

  5. Genotype and phenotype of a new 2-bp deletion of hMSH2 at codon 233.

    Science.gov (United States)

    Müller, A; Beyser, K; Arps, H; Bolander, S; Becker, H; Rüschhoff, J

    2001-08-01

    Germline mutations within mismatch repair genes, such as hMSH2, hMLH1, and hMSH6, have been shown to be the hallmark of the hereditary nonpolyposis colorectal cancer (HNPCC) syndrome. The spectrum of tumors associated with mismatch repair gene defects and the possible relationship between genotype and phenotype are still unclear. Therefore, the spectrum of tumors and the possible genotype-phenotype relationship are still under discussion. Here, we report on a family with a new germline mutation in the hMSH2 gene with a 2-bp deletion at codons 232 and 233 leading to a frame shift and a stop at codon 254. Accordingly, immunohistochemistry revealed loss of hMSH2 expression in colorectal carcinomas of three affected family members. In this one family, there was a high penetrance. Interestingly, mutational screening of the family revealed a high penetrance of the mutation affecting four of five tested people at risk, with a high mortality rate and a trend toward lower age of onset in subsequent generations. Finally, a metachronous breast cancer in one patient turned out to be a tumor unrelated to microsatellite instability phenocopy, i.e., a sporadic tumor unrelated to HNPCC that expressed the hMSH2 gene and did not show any microsatellite instability.

  6. Ammonia excitation imaging of shocked gas towards the W28 gamma-ray source HESS J1801-233

    CERN Document Server

    Maxted, Nigel I; Rowell, Gavin P; Nicholas, Brent P; Burton, Michael G; Walsh, Andrew; Fukui, Yasuo; Kawamura, Akiko

    2016-01-01

    We present 12 mm Mopra observations of the dense (>10^3 cm^-3 ) molecular gas towards the north-east (NE) of the W28 supernova remnant (SNR). This cloud is spatially well-matched to the TeV gamma-ray source HESS J1801-233 and is known to be a SNR-molecular cloud interaction region. Shock-disruption is evident from broad NH3 (1,1) spectral line-widths in regions towards the W28 SNR, while strong detections of spatially-extended NH3(3,3), NH3(4,4) and NH3(6,6) inversion emission towards the cloud strengthen the case for the existence of high temperatures within the cloud. Velocity dispersion measurements and NH3(n,n)/(1,1) ratio maps, where n=2, 3, 4 and 6, indicate that the source of disruption is from the side of the cloud nearest to the W28 SNR, suggesting that it is the source of cloud-disruption. Towards part of the cloud, the ratio of ortho to para-NH3 is observed to exceed 2, suggesting gas-phase NH3 enrichment due to NH3 liberation from dust grain mantles. The measured NH3 abundance with respect to H2 i...

  7. A 233 km Circumference Tunnel for $e^+$$e^-$, $p$$\\bar {p}$, and $\\mu^{+} \\mu^{-}$ Colliders

    CERN Document Server

    Lyons, George T

    2011-01-01

    In 2001 a cost analysis survey was conducted to build a 233km circumference tunnel in northern Illinois in which to build a Very Large Hadron Collider. Ten years later I have reexamined the proposal, taking into consideration the technological advancements in all the aspects of construction cost analysis. I outline the implementations of $e^+ e^-$, $p{\\bar{p}}$, and $\\mu^+\\mu^-$ collider rings in the tunnel using 21${\\rm{st}}$ century technology. The $e^+e^-$ collider employs a Crab Waist Crossing, ultra low emittance damped bunches, 12 GV of superconducting RF, and 0.026 Tesla low coercivity grain oriented silicon steel/concrete dipoles. The $p{\\bar{p}}$ collider uses the high intensity Fermilab $\\bar{p}$ source, exploits high cross sections for $p\\bar{p}$ production of high mass states, and uses 2 Tesla ultra low carbon steel/YBCO superconductor magnets run with liquid neon. The $\\mu^+\\mu^-$ ring ramps the $p{\\bar{p}}$ magnets at 8 Hz every 0.4 seconds, uses 250 GV of SRF, and mitigates neutrino radiation w...

  8. Dissolution of unirradiated UO{sub 2} and UO{sub 2} doped with {sup 233}U under reducing conditions

    Energy Technology Data Exchange (ETDEWEB)

    Ollila, K. [VTT Processes (Finland); Oversby, V.M. [VMO Konsult (Sweden)

    2005-01-01

    Experiments have been conducted to determine an upper limit to the dissolution rate of UO{sub 2} under reducing conditions appropriate to those in a geologic repository for spent fuel disposal in Finland and Sweden. Test duration ranged from 52 to 140 days. The total amount of U recovered in each test was converted into a dissolution rate per year for the sample. The dissolution rate was then used to calculate an expected lifetime for the samples under the test conditions. The dissolution rate did not depend on the length of the testing period. Rather, the dissolution rate appeared to decrease as the samples were exposed to sequential testing periods. This indicates that the results are still influenced by transient effects such as high-energy surface sites, which implies that the dissolution rates measured are upper limits. The sample lifetimes calculated from the last two testing periods, which had a total of 269 days, ranged from 7 to 10 million years. There was no indication of an effect of alpha radiolysis on the dissolution rate results for samples with doping levels of 0, 5, and 10% {sup 233}U.

  9. Mutation S233L in the 1B domain of keratin 1 causes epidermolytic palmoplantar keratoderma with "tonotubular" keratin.

    Science.gov (United States)

    Terron-Kwiatkowski, Ana; van Steensel, Maurice A M; van Geel, Michel; Lane, E Birgitte; McLean, W H Irwin; Steijlen, Peter M

    2006-03-01

    Epidermolytic palmoplantar keratoderma (EPPK) is an autosomal dominant genodermatosis characterized by epidermolytic hyperkeratosis restricted to the palm and sole epidermis. The disorder is normally associated with dominant-negative mutations in the keratin 9 (K9) gene; however, a small number of cases have been reported where causative mutations were identified in the K1 gene. Here, we present two unrelated Dutch EPPK families with striking ultrastructural findings: tubular keratin structures in the cytoplasm of suprabasal cells. Similar structures were reported previously in a German EPPK family and were termed "tonotubular" keratin. After excluding the involvement of the K9 gene by complete sequencing, we identified a novel mutation, S233L, at the beginning of the 1B domain of K1 in both families. Protein expression studies in cultured cells indicated pathogenicity of this mutation. This is the first report of a genetic defect in this domain of K1. The unusual gain-of-function mutation points to a subtle role of the 1B domain in mediating filament-filament interactions with regular periodicity.

  10. Measurement of the $^{233}$U neutron capture cross section at the n_TOF facility at CERN

    CERN Document Server

    Carrapiço, Carlos; Berthoumieux, Eric; Gonçalves, Isabel; Gunsing, Frank

    2012-12-12

    The Thorium-Uranium (Th-U) fuel cycle has been envisaged as an alternative to the Uranium-Plutonium (U-Pu) fuel cycle for electricity generation using nuclear power reactors. Indeed, thorium can be used as a nuclear fuel, and several studies and R&D programs seem to provide evidence on the sustainability of the Th-U fuel cycle, due to (i) the natural abundance of Thorium, (ii) the improved proliferation resistance offered by the Th-U fuel cycle relative to the U-Pu fuel cycle, (iii) the better neutronics performance of the Th-U fuel cycle throughout the whole neutron energy range compared to the U-Pu fuel cycle, (iv) the lower radiotoxicity of the generated spent fuel in reactors with Th-U fuel cycle and, consequently (v) better economics and public acceptance of the reactors operated using the Th-U fuel cycle compared to those using the U-Pu fuel cycle (prior to the Generation IV nuclear reactors). In a nuclear reactor operated using the Th-U fuel cycle, $^{233}$U is a key nuclide governing the neutr...

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

    International Nuclear Information System (INIS)

    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

  12. Storage and disposition of weapons usable fissile materials (FMD) PEIS: Blending of U-233 to <12% or <5% enrichment at the Idaho National Engineering Laboratory. Data report, Draft: Version 1

    International Nuclear Information System (INIS)

    Uranium-233 (U-233), a uranium isotope, is a fissionable material capable of fueling nuclear reactors or being utilized in the manufacturing of nuclear weapons. As such, it is controlled as a special nuclear material. The Idaho National Engineering Laboratory (INEL) and Oak Ridge National Laboratory (ORNL) currently store the Department of Energy's (DOE's) supply of unirradiated U-233 fuel materials. Irradiated U-233 is covered by the national spent nuclear fuel (SNF) program and is not in the scope of this report. The U-233 stored at ORNL is relatively pure uranium oxide in the form of powder or monolithic solids. This material is currently stored in stainless steel canisters of variable lengths measuring about 3 inches in diameter. The ORNL material enrichment varies with some material containing considerable amounts of U-235. The INEL material is fuel from the Light Water Breeder Reactor (LWBR) Program and consists of enriched uranium and thorium oxides in zircaloy cladding. The DOE inventory of U-233 contains trace quantities of U-232, and daughter products from the decay of U-232 and U-233, resulting in increased radioactivity over time. These increased levels of radioactivity generally result in the need for special handling considerations

  13. 我院药物临床试验中严重不良事件报告233例分析%Analysis of 233 Cases of Severe Adverse Events in Drug Clinical Trials of Our Hospital

    Institute of Scientific and Technical Information of China (English)

    张田香; 陆明莹; 张彩霞; 袁祖贻

    2016-01-01

    目的:为药物临床试验中进行质控和保护受试者权益提供参考。方法:收集我院2012年1月-2015年6月上报的药物临床试验中的233例严重不良事件(SAE)报告,按照受试者性别、年龄、上报科室、药物/器械种类、药物/器械名称、SAE的类型、SAE与药物/器械的相关性、受试者合并疾病情况等进行统计分析。结果:男性SAE发生率高于女性(71.2%vs.28.8%);SAE主要发生在50岁以上的人群中(189例,81.1%);心内科SAE发生率最高(137例,58.8%);主要的SAE类型是导致住院(183例,78.5%);大部分SAE与研究药物肯定无关(164例,70.4%);发生SAE的受试者中一半以上自身合并有其他疾病(128例,54.9%)。结论:为确保药物临床试验数据的质量和受试者的安全,临床试验过程中研究者应重点加强对老年和自身合并疾病受试者的管理,确保每例SAE得到及时处理,并如实记录和报告。%OBJECTIVE:To provide reference for performing quality control and protecting the subjects’rights and interests. METHODS:233 severe adverse events (SAE) cases reported by our hospital during Jan. 2012-Jun. 2015 were collected and ana-lyzed statistically in respects of subjects’gender and age,department,drug/equipment types,SAE types,relationship of SAE with drug/equipment,comorbidities,etc. RESULTS:The incidence of SAE in male was higher than female(71.2% vs. 28.8%);SAE mainly occurred in people over the age of 50(189 cases,81.1%);the incidence of SAE in cardiology department was the highest (137 cases,58.8%);main SAE type was hospitalization(183 cases,78.5%);most of SAE had nothing to do with studied drugs (164 cases,70.4%);more than half of the subjects suffered from other comorbidities(128 cases,54.9%). CONCLUSIONS:In order to ensure the quality of drug clinical trial data and safety of subjects,the investigator should strengthen the management of the

  14. Simultaneous trace detection of carbon monoxide and methane at 2.33 μm%中心波长2.33μm附近CO和CH4分子的同时探测

    Institute of Scientific and Technical Information of China (English)

    赵辉; 刘锟; 蔡廷栋; 谈图; 汪磊; 高晓明

    2011-01-01

    The spectrum of a series of low concentration carbon monoxide and mixed gas (carbon monoxide, methane and nitrogen) was obtained around 2. 33 fim using a tunable distributed feedback semiconductor laser with an astigmatic mirror multipass absorption cell (optical path length 100 m) at room temperature through direct absorption technique. The absorption lines of carbon monoxide at 4 288. 289 8 cm-1 and methane at 4 287. 650 15 cm-1 were chosen for trace detection. At the total pressure of 40 698 Pa, the detection limits of carbon monoxide and methane were gotten respectively, I. E. 8. 15 × 10-6 for carbon monoxide (signal-to-noise ratio is about 216) and 18. 48 × 10-6 for methane (signal-to-noise ratio is about 147).%采用分布反馈式半导体激光器作为探测光源,结合程长为100m的离散型多通吸收池,采用直接吸收光谱技术,对室温下中心波长2.33 μm附近各种低体积分数的CO及混合气体(CO,CH4和N2)的直接吸收光谱进行了测量.选择CO在4 288.289 8 cm-1位置的吸收谱线和CH4在4 287.650 15 cm-1处的吸收谱线进行痕量探测,在40 698 Pa的总压力下,实验测得CO的探测极限为8.15×10-6(信噪比约为216),CH4的探测极限为18.48×10-6(信噪比约为147).

  15. Interstitial 1q23.3q24.1 deletion in a patient with renal malformation, congenital heart disease, and mild intellectual disability.

    Science.gov (United States)

    Mackenroth, Luisa; Hackmann, Karl; Klink, Barbara; Weber, Julia Sara; Mayer, Brigitte; Schröck, Evelin; Tzschach, Andreas

    2016-09-01

    Interstitial deletions including chromosome region 1q23.3q24.1 are rare. Only eight patients with molecularly characterized deletions have been reported to date. Their phenotype included intellectual disability/developmental delay, growth retardation, microcephaly, congenital heart disease, and renal malformations. We report on a female patient with mild developmental delay, congenital heart disease, and bilateral renal hypoplasia in whom an interstitial de novo deletion of approximately 2.7 Mb in 1q23.3q24.1 was detected by array CGH. This is the smallest deletion described in this region so far. Genotype-phenotype comparison with previously published patients allowed us to propose LMX1A and RXRG as potential candidate genes for intellectual disability, PBX1 as a probable candidate gene for renal malformation, and enabled us to narrow down a chromosome region associated with microcephaly. © 2016 Wiley Periodicals, Inc. PMID:27255444

  16. Determination of the extraction efficiency for $^{233}$U source $\\alpha$-recoil ions from the MLL buffer-gas stopping cell

    CERN Document Server

    von der Wense, Lars; Laatiaoui, Mustapha; Thirolf, Peter G

    2016-01-01

    Following the $\\alpha$ decay of $^{233}$U, $^{229}$Th recoil ions are shown to be extracted in a significant amount from the MLL buffer-gas stopping cell. The produced recoil ions and subsequent daughter nuclei are mass purified with the help of a customized quadrupole mass spectrometer. The combined extraction and mass-purification efficiency for $^{229}$Th$^{3+}$ is determined via MCP-based measurements and via the direct detection of the $^{229}$Th $\\alpha$ decay. A large value of $(10\\pm2)$\\% for the combined extraction and mass-purification efficiency of $^{229}$Th$^{3+}$ is obtained at a mass resolution of about 1 u/e. In addition to $^{229}$Th, also other $\\alpha$-recoil ions of the $^{233,232}$U decay chains are addressed.

  17. Neutron-induced fission cross-section of {sup 233}U in the energy range 0.5

    Energy Technology Data Exchange (ETDEWEB)

    Belloni, F.; Milazzo, P.M.; Abbondanno, U.; Fujii, K.; Moreau, C. [Istituto Nazionale di Fisica Nucleare (INFN), Trieste (Italy); Calviani, M. [Laboratori Nazionali di Legnaro, Istituto Nazionale di Fisica Nucleare (INFN), Legnaro (Italy); CERN, Geneva (Switzerland); Colonna, N.; Marrone, S.; Meaze, M.H.; Tagliente, G.; Terlizzi, R. [Istituto Nazionale di Fisica Nucleare (INFN), Bari (Italy); Mastinu, P.; Gramegna, F. [Laboratori 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. [CEA, Irfu, Gif-sur-Yvette (France); Alvarez, H.; Cano-Ott, D.; Duran, I.; Embid-Segura, M.; Gonzalez-Romero, E.; Paradela, C. [Univ. de Santiago de Compostela, Santiago (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, Lodz (Poland); Audouin, L.; Dillmann, I.; Heil, M.; Kaeppeler, F.; Mosconi, M.; Plag, R.; Voss, F.; Walter, S.; Wisshak, K. [Inst. fuer Kernphysik, Karlsruhe Inst. of Technology, Campus Nord, Karlsruhe (Germany); Badurek, G.; Jericha, E.; Leeb, H.; Oberhummer, H.; Pigni, M.T. [Technische Univ. Wien, Atominstitut der Oesterreichischen Univ., Wien (Austria); Baumann, P.; David, S.; Kerveno, M.; Lukic, S.; Rudolf, G. [Centre National de la Recherche Scientifique/IN2P3 - IReS, 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, Sevilla (Spain); Carrapico, C.; Goncalves, I.; Salgado, J.; Santos, C.; Tavora, L.; Vaz, P. [Inst. Tecnologico e Nuclear, Lisbon (Portugal)] [and others

    2011-01-15

    The neutron-induced fission cross-section of {sup 233}U has been measured at the CERN n-TOF facility relative to the standard fission cross-section of {sup 235}U between 0.5 and 20MeV. The experiment was performed with a fast ionization chamber for the detection of the fission fragments and to discriminate against {alpha} -particles from the natural radioactivity of the samples. The high instantaneous flux and the low background of the n-TOF facility result in data with uncertainties of {approx} 3%, which were found in good agreement with previous experiments. The high quality of the present results allows to improve the evaluation of the {sup 233}U (n,f) cross-section and, consequently, the design of energy systems based on the Th/U cycle. (orig.)

  18. Growth, optical, magnetic and electrical properties of CuFe2.33In9.67S17.33 single crystal

    Science.gov (United States)

    Bodnar, I. V.; Jaafar, M. A.; Pauliukavets, S. A.; Trukhanov, S. V.; Victorov, I. A.

    2015-08-01

    Studies of the optical, magnetic, and electrical properties of a CuFe2.33In9.67S17.33 single crystal in 5-300 K temperature and 0-14 T field ranges are carried out. The nature of the change of spectral dependence of the absorption coefficient is found. Bandgap is determined, which is equal 1.5 eV. It is established that the studied sample is paramagnetic. In the main state ferromagnetic correlations of a near order are found, which are characteristic for spin glass with a freezing temperature in an area of 9 K. The magnetic ordering temperature is about 11 K. The sample studied is a semiconductor with 15.2 kΩ · cm resistivity at room temperature. The magnetic and electrical states’ formation mechanism for a CuFe2.33In9.67S17.33 single crystal is proposed.

  19. Analysis of the Fission Cross-Section of U233 for Neutrons of Energies Between 1.7 and 30 eV

    International Nuclear Information System (INIS)

    The cross-section of U233 for resonance neutrons was analysed by the least-squares method. The paper discusses the need for using a multilevel formalism, and considers the statistical distributions of level spacing and partial widths. By the use of a study of level spacing as a starting point, particular attention is paid to the possibility of obtaining information on the relationship of populations of resonances of different spin. (author)

  20. Utilization of non-weapons-grade plutonium and highly enriched uranium with breeding of the {sup 233}U isotope in the VVER reactors using thorium and heavy water

    Energy Technology Data Exchange (ETDEWEB)

    Marshalkin, V. E., E-mail: marshalkin@vniief.ru; Povyshev, V. M. [Russian Federal Nuclear Center All-Russian Research Institute of Experimental Physics (Russian Federation)

    2015-12-15

    A method for joint utilization of non-weapons-grade plutonium and highly enriched uranium in the thorium–uranium—plutonium oxide fuel of a water-moderated reactor with a varying water composition (D{sub 2}O, H{sub 2}O) is proposed. The method is characterized by efficient breeding of the {sup 233}U isotope and safe reactor operation and is comparatively simple to implement.

  1. A HST study of the environment of the Herbig Ae/Be star LkHa 233 and its bipolar jet

    CERN Document Server

    Melnikov, Stanislav Yu; Eislöffel, Jochen; Bacciotti, Francesca; Locatelli, Ugo; Ray, Thomas P

    2008-01-01

    We present the results of HST/STIS and WFPC2 observations of LkHa 233 and its environment. LkHa233 is a Herbig Ae/Be star with a collimated bipolar jet. We investigate optical forbidden lines along the LkHa 233 jet to determine physical parameters of this jet (electron density n_e, hydrogen ionisation fraction x_e, electron temperature T_e, and mass density n_H). The knowledge of these parameters allows us a direct comparison of a jet from a Herbig star with those from T Tauri stars. The WFPC2 images in broad-band filters clearly show a dark lane caused either by a circumstellar disk or a dust torus. In the blueshifted lobe, n_e is close to or above the critical density for [SII] lines (2.5x10^4 cm^-3) in the first arcsecond and decreases with distance from the source. The ionisation x_e~0.2-0.6 gently rises for the first 500 AU of the flow and shows two re-ionisation events further away from the origin. The T_e varies along the flow between 10^4 K and 3x10^4 K. The (radial) outflow velocities are ~ 80-160 km...

  2. 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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  3. A MOLECULARLY CHARACTERIZED INTERSTITIAL DELETION ENCOMPASSING THE 11q14.1-q23.3 REGION IN A CASE WITH MULTIPLE CONGENITAL ABNORMALITIES.

    Science.gov (United States)

    Cetin, Z; Altiok-Clark, O; Yakut, S; Guzel-Nur, B; Mihci, E; Berker-Karauzum, S

    2016-01-01

    Interstitial deletion of chromosome 11 long arm is a rare event. In most of the interstitial deletions on the long arm of chromosome 11 both the position and the size of these deletions are heterogeneous making a precise karyotype-phenotype correlation. In only a few of the reported cases has the deletion been molecularly characterized. Our patient was a 13-year-old male presented; mental motor retardation, strabismus, myopia, retinopathy, sensorineural hearing loss, a long and triangular face, a broad forehead, hypotelorism, nasal septal deviation, a beaked nose, hypoplastic ala nasie, bilateral low-set ears, a high arched palate, crowded teeth, retrognathia, thin lips, a long neck, and sloping shoulders, hyperactive behavior, pulmonary stenosis and lumbar scoliosis. Conventional cytogenetic analysis revealed 46,XY,del(11)(q14.1-q23.3) karyotype in the patient. Array-CGH analysis of the patient's DNA revealed an interstitial deletion encompassing 33.2 Mb in the 11q14.1-q23.3 genomic region (chr11: 83,161,443-116,401,751 ; Hg19). In this report, we present a patient with an interstitial deletion on the long arm of chromosome 11 that encompassed the 11q14.1-q23.3 region; and, using array-CGH analysis, we molecularly characterized the deleted region.

  4. Complications associated with transobturator sling procedures: analysis of 233 consecutive cases with a 27 months follow-up

    Directory of Open Access Journals (Sweden)

    Dubuisson Jean-Bernard

    2009-09-01

    Full Text Available Abstract Backround The transobturator tape procedure (TOT is an effective surgical treatment of female stress urinary incontinence. However data concerning safety are rare, follow-up is often less than two years, and complications are probably underreported. The aim of this study was to describe early and late complications associated with TOT procedures and identify risk factors for erosions. Methods It was a 27 months follow-up of a cohort of 233 women who underwent TOT with three different types of slings (Aris®, Obtape®, TVT-O®. Follow-up information was available for 225 (96.6% women. Results There were few per operative complications. Forty-eight women (21.3% reported late complications including de novo or worsening of preexisting urgencies (10.2%, perineal pain (2.2%, de novo dyspareunia (9%, and vaginal erosion (7.6%. The risk of erosion significantly differed between the three types of slings and was 4%, 17% and 0% for Aris®, Obtape® and TVT-O® respectively (P = 0.001. The overall proportion of women satisfied by the procedure was 72.1%. The percentage of women satisfied was significantly lower in women who experienced erosion (29.4% compared to women who did not (78.4% (RR 0.14, 95% CI 0.05-0.38, P Conclusion Late post operative complications are relatively frequent after TOT and can impair patient's satisfaction. Women should be informed of these potential complications preoperatively and require careful follow-up after the procedure. Choice of the safest sling material is crucial as it is a risk factor for erosion.

  5. Delayed Fission Gamma-ray Characteristics of Th-232 U-233 U-235 U-238 and Pu-239

    Energy Technology Data Exchange (ETDEWEB)

    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.

  6. Ammonia excitation imaging of shocked gas towards the W28 gamma-ray source HESS J1801-233

    Science.gov (United States)

    Maxted, Nigel I.; de Wilt, Phoebe; Rowell, Gavin P.; Nicholas, Brent P.; Burton, Michael. G.; Walsh, Andrew; Fukui, Yasuo; Kawamura, Akiko

    2016-10-01

    We present 12 mm Mopra observations of the dense (>103 cm-3) molecular gas towards the north-east of the W28 supernova remnant (SNR). This cloud is spatially well matched to the TeV gamma-ray source HESS J1801-233 and is known to be an SNR-molecular cloud interaction region. Shock-disruption is evident from broad NH3 (1,1) spectral linewidths in regions towards the W28 SNR, while strong detections of spatially extended NH3 (3,3), NH3(4,4) and NH3(6,6) inversion emission towards the cloud strengthen the case for the existence of high temperatures within the cloud. Velocity dispersion measurements and NH3(n,n)/(1,1) ratio maps, where n = 2, 3, 4 and 6, indicate that the source of disruption is from the side of the cloud nearest to the W28 SNR, suggesting that it is the source of cloud-disruption. Towards part of the cloud, the ratio of ortho to para-NH3 is observed to exceed 2, suggesting gas-phase NH3 enrichment due to NH3 liberation from dust-grain mantles. The measured NH3 abundance with respect to H2 is ˜(1.2 ± 0.5) × 10-9, which is not high, as might be expected for a hot, dense molecular cloud enriched by sublimated grain-surface molecules. The results are suggestive of NH3 sublimation and destruction in this molecular cloud, which is likely to be interacting with the W28 SNR shock.

  7. Case 233: Blastomycosis.

    Science.gov (United States)

    Mouser, Hans; Miller, Frank H; Berggruen, Senta M

    2016-09-01

    History A 35-year-old man from the upper Midwest region of the United States who had no relevant medical history initially presented to an acute care clinic with multiple small tender skin lesions. His temperature was 38.1°C, and physical examination revealed several small fluctuant masses that were draining purulent material. Skin culture of one of the draining lesions was performed at this time, but there was no subsequent bacterial growth. A diagnosis of furunculosis was made, and Bactrim (sulfamethoxazole-trimethoprim; AR Scientific, Philadelphia, Pa) and a regimen of chlorhexidine washes were prescribed. Two weeks later, the number of skin lesions had increased, and the patient had begun to experience night sweats and fevers. After an episode of hemoptysis and some unusual pain in the patient's right testicle, he presented to the emergency department. At this time, chest radiographs were obtained. The patient was admitted for additional work-up, and computed tomographic (CT) images of the chest were obtained. Physical examination at the time of admission revealed scattered 1-3-cm firm pink hyperpigmented subcutaneous nodules, several of which had overlying pustules. This examination was also notable for a palpable fullness within the right testicle. The patient was afebrile at admission. He denied a history of contact with sick people, illicit drug use, or recent travel. His social history was notable for a 20-pack-year smoking history and a recent relocation to a neighborhood with several new construction sites. Laboratory evaluation revealed leukocytosis (white blood cell count, 15.4 × 10(9)/L; normal range, [3.5-10.5] × 10(9)/L), a chemistry panel revealed a low sodium level (132 mEq/L [132 mmol/L]; normal range, 134-142 mEq/L [134-142 mmol/L]), and serum α-fetoprotein and human chorionic gonadotropin levels were normal. Ultrasonography (US) of the scrotum was performed. Serum analysis was negative for human immunodeficiency virus type 1 and type 2 RNA, and Venereal Disease Research Laboratory and rapid plasma regain test results were negative. Blood cultures were negative for bacterial growth. On the basis of chest CT findings, bronchoscopy with bronchoalveolar lavage was performed. Magnetic resonance (MR) imaging of the abdomen also was performed to further evaluate a focal area of hypoenhancement within the pancreatic tail seen on chest CT images. PMID:27533292

  8. Fiscal Year 2008 Phased Construction Completion Report for EU Z2-33 in Zone 2, East Tennessee Technology Park, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Bechtel Jacobs

    2008-09-11

    The Record of Decision for Soil, Buried Waste, and Subsurface Structure Actions in Zone 2, East Tennessee Technology Park, Oak Ridge, Tennessee (DOE/OR/01-2161&D2) (Zone 2 ROD) acknowledged that most of the 800 acres in Zone 2 were contaminated, but that sufficient data to confirm the levels of contamination were lacking. The Zone 2 ROD further specified that a sampling strategy for filling the data gaps would be developed. The Remedial Design Report/Remedial Action Work Plan for Zone 2 Soils, Slabs, and Subsurface Structures, East Tennessee Technology Park, Oak Ridge, Tennessee (DOE/OR/01-2224&D3) (Zone 2 RDR/RAWP) defined the sampling strategy as the Dynamic Verification Strategy (DVS), generally following the approach used for characterization of the Zone 1 exposure units (EUs). The Zone 2 ROD divided the Zone 2 area into seven geographic areas and 44 EUs. To facilitate the data quality objectives (DQOs) of the DVS process, the Zone 2 RDR/RAWP regrouped the 44 EUs into 12 DQO scoping EU groups. These groups facilitated the DQO process by placing similar facilities and their support facilities together and allowing identification of data gaps. The EU groups were no longer pertinent after DQO planning was completed and characterization was conducted as areas became accessible. As the opportunity to complete characterization became available, the planned DVS program and remedial actions (RAs) were completed for EU Z2-33. Remedial action was also performed at two additional areas in adjacent EU Z2-42 because of their close proximity and similar nature to a small surface soil RA in EU Z2-33. Remedial actions for building slabs performed in EU Z2-33 during fiscal year (FY) 2007 were reported in the Fiscal Year 2007 Phased Construction Completion Report for the Zone 2 Soils, Slabs, and Subsurface Structures at East Tennessee Technology Park, Oak Ridge, Tennessee (DOE/OR/01-2723&D1). Recommended RAs for EU Z2-42 were described in the Fiscal Year 2006 Phased Construction

  9. Measurement of the generation ratio of 233U and the average radiation capture cross section of 232Th with 232ThO2 irradiated by fast neutrons

    International Nuclear Information System (INIS)

    Background: Thorium-Uranium cycle plays an important role in the future's power production technology. Nuclear data involved are urgently needed for engineering design and other purposes since there are obvious differences between the existing evaluated data. Macroscopic neutron integral experiment can be used as a good tool to survey the confusion. Purpose: Macroscopic neutron integral experiment based on radioactive method was carried out to measure the generation ratio of 233U nuclide and the average radiation capture cross section of 232Th while a ThO2 sample was irradiated by fast neutrons leakage from a fast critical facility. We expect that these data can be used as a reference for the research of Th-U cycle. Methods: Radiation capture reactions of 232Th nuclides occur when the nuclides are irradiated by neutrons. 233U nuclides will be generated after two cascade decays by emitting beta rays from the activation products, which are 233Th nuclides. The ThO2 sample was prepared as a slice of 20 mm×10 mm from 0.743 36-g ThO2 powders of 99.9% enriched. The neutron flux was measured by activation method which was 4.07x109 cm-2·s-1 at the sample's irradiation position while the facility worked at the power level of 180 watts. The leakage neutrons' energy distribution was calculated by MC method and it is very close to the fission spectrum with the averaged energy of 1.42 MeV. After irradiation and then a period of cooling time the gamma rays emitted from the sample were measured by an HPGe spectrometer which had been pre-calibrated. From these data the activity of 233Pa was calculated and then the generation ratio of 233U and the average radiation capture cross section of 232Th were calculated. The measured average radiation capture cross section was compared with the cross sections calculated based on the ENDFB-VH.1, CENDL-3.1, JENDL-4.0, BROND2.2 databases. Results: The measured generation ratio of 233U was 4.01×10-12 with an uncertainty of 6

  10. High-pressure phase diagram and equation of state of solid helium from single-crystal X-ray diffraction to 23.3 GPa

    Science.gov (United States)

    Mao, H. K.; Hemley, R. J.; Jephcoat, A. P.; Finger, L. W.; Wu, Y.

    1988-01-01

    Single-crystal X-ray diffraction measurements have been performed on solid He-4 from 15.6 to 23.3 GPa at 300 K with synchrotron radiation. The diffraction patterns demonstrate that the structure of the solid is hexagonal close packed over this pressure-temperature range, contrary to both the interpretation of high-pressure optical studies and to theoretical predictions. The solid is more compressible than is indicated by equations of state calculated with recently determined helium pair potentials. The results suggest that a significant revision of current views of the phase diagram and energetics of dense solid helium is in order.

  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

    Energy Technology Data Exchange (ETDEWEB)

    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. Neutron-induced fission cross sections of 233U and 243Am in the energy range 0.5 Mev En 20 MeV @ n_TOF

    CERN Document Server

    Belloni, F; Milazzo, P M; Calviani, M; Colonna, N; Mastinu, P; Abbondanno, U; Aerts, G; Álvarez, H; Álvarez-Velarde, F; Andriamonje, S; Andrzejewski, J; Assimakopoulos, P; Audouin, L; Badurek, G; Baumann, P; Becvár, F; Berthoumieux, E; Calviño, F; Cano-Ott, D; Capote, R; Carrapiço, C; Cennini, P; Chepel, V; Chiaveri, E; 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; González-Romero, E; Gramegna, F; Guerrero, C; Gunsing, F; Haas, B; Haight, R; Heil, M; Herrera-Martinez, A; Igashira, M; Jericha, E; Käppeler, F; Kadi, Y; Karadimos, D; 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; Martínez, T; Massimi, C; Mengoni, A; 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; Vazl, P; Ventura, A; Villamarin, D; Vincente, M C; Vlachoudis, V; Vlastou, R; Voss, F; Walter, S; Wiescher, M; Wisshak, K

    2011-01-01

    Neutron-induced fission cross-sections of actinides have been recently measured at the neutron time of flight facility n_TOF at CERN in the frame of a research project involving isotopes relevant for nuclear astrophysics and nuclear technologies. Fission fragments are detected by a gas counter with good discrimination between nuclear fission products and background events. Neutron-induced fission cross-sections of 233U and 243Am were determined relative to 235U. The present paper reports the results obtained at neutron energies between 0.5 and 20 MeV.

  13. Study of the excited levels of 233{sup P}a by the 237{sup N}p alpha decay; Estudio de los niveles excitados en el 233{sup P}a por la desintegracion alfa del 237{sup N}p

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, J.; Gaeta, R.; Vano, E.; Los Arcos, J. M.

    1978-07-01

    The excited levels in 233{sup P}a following the 237{sup N}p alpha decay have been studied, by performing different experiences to complete available data and supply new information. Thus, two direct alpha spectrum measurement, one alpha-gamma bidimensional coincidence experiment, three gamma-gamma and gamma-X ray coincidences and some other measurements of the gamma spectrum, direct and coincident with alpha-particles have been made. These last experiences have allowed to obviate usual radiochemical separation methods, the 233{sup P}a radioactive descendent interferences being eliminated by means of the coincidence technic. As a result, a primary decay scheme has been elaborated, including 15 new gamma transitions and two new levels, not observed in the most recent works. (Author) 60 refs.

  14. Third case of 8q23.3-q24.13 deletion in a patient with Langer-Giedion syndrome phenotype without TRPS1 gene deletion.

    Science.gov (United States)

    Pereza, Nina; Severinski, Srećko; Ostojić, Saša; Volk, Marija; Maver, Aleš; Dekanić, Kristina Baraba; Kapović, Miljenko; Peterlin, Borut

    2012-03-01

    Langer-Giedion syndrome (LGS) is a contiguous gene syndrome caused by a hemizygous deletion on chromosome 8q23.3-q24.11 involving TRPS1 and EXT1 genes. We report on a girl with LGS phenotype and a 7.5 Mb interstitial deletion at chromosome 8q23.3-q24.13. Array-comparative genomic hybridization (a-CGH) revealed a deletion encompassing only the EXT1 and not the TRPS1 gene. Even though the deletion of TRPS1 and EXT1 genes is responsible for craniofacial and skeletal features of LGS, there have been previous reports of patients with LGS phenotype and 8q24 deletions leaving the TRPS1 gene intact. To our knowledge, this is the third such case. Our patient differs from previously reported LGS patients without TRPS1 gene deletion in that she has the typical LGS facial dysmorphism and skeletal abnormalities. However, the girl is of normal height and has only a mild developmental delay. Additionally, she has dyslalia and premature adrenarche classified as Tanner stage 3 premature pubarche which have not yet been described as features of LGS. We examine the molecular breakpoints and phenotypes of our patient and previously reported cases.

  15. Third case of 8q23.3-q24.13 deletion in a patient with Langer-Giedion syndrome phenotype without TRPS1 gene deletion.

    Science.gov (United States)

    Pereza, Nina; Severinski, Srećko; Ostojić, Saša; Volk, Marija; Maver, Aleš; Dekanić, Kristina Baraba; Kapović, Miljenko; Peterlin, Borut

    2012-03-01

    Langer-Giedion syndrome (LGS) is a contiguous gene syndrome caused by a hemizygous deletion on chromosome 8q23.3-q24.11 involving TRPS1 and EXT1 genes. We report on a girl with LGS phenotype and a 7.5 Mb interstitial deletion at chromosome 8q23.3-q24.13. Array-comparative genomic hybridization (a-CGH) revealed a deletion encompassing only the EXT1 and not the TRPS1 gene. Even though the deletion of TRPS1 and EXT1 genes is responsible for craniofacial and skeletal features of LGS, there have been previous reports of patients with LGS phenotype and 8q24 deletions leaving the TRPS1 gene intact. To our knowledge, this is the third such case. Our patient differs from previously reported LGS patients without TRPS1 gene deletion in that she has the typical LGS facial dysmorphism and skeletal abnormalities. However, the girl is of normal height and has only a mild developmental delay. Additionally, she has dyslalia and premature adrenarche classified as Tanner stage 3 premature pubarche which have not yet been described as features of LGS. We examine the molecular breakpoints and phenotypes of our patient and previously reported cases. PMID:22315192

  16. R-MATRIX RESONANCE ANALYSIS AND STATISTICAL PROPERTIES OF THE RESONANCE PARAMETERS OF 233U IN THE NEUTRON ENERGY RANGE FROM THERMAL TO 600 eV

    Energy Technology Data Exchange (ETDEWEB)

    Leal, L.C.

    2001-02-27

    The R-matrix resonance analysis of experimental neutron transmission and cross sections of {sup 233}U, with the Reich-Moore Bayesian code SAMMY, was extended up to the neutron energy of 600 eV by taking advantage of new high resolution neutron transmission and fission cross section measurements performed at the Oak Ridge Electron Linear Accelerator (ORELA). The experimental data base is described. In addition to the microscopic data (time-of-flight measurements of transmission and cross sections), some experimental and evaluated integral quantities were included in the data base. Tabulated and graphical comparisons between the experimental data and the SAMMY calculated cross sections are given. The ability of the calculated cross sections to reproduce the effective multiplication factors k{sub eff} for various thermal, intermediate, and fast systems was tested. The statistical properties of the resonance parameters were examined and recommended values of the average s-wave resonance parameters are given.

  17. Two Novel Tyrosinase Inhibitory Sesquiterpenes Induced by CuCl2 from a Marine-Derived Fungus Pestalotiopsis sp. Z233

    Directory of Open Access Journals (Sweden)

    Min Sun

    2013-08-01

    Full Text Available Two new sesquiterpenes, 1β,5α,6α,14-tetraacetoxy-9α-benzoyloxy-7β H-eudesman-2β,11-diol (1 and 4α,5α-diacetoxy-9α-benzoyloxy-7βH-eudesman-1β,2β,11, 14-tetraol (2, were produced as stress metabolites in the cultured mycelia of Pestalotiopsis sp. Z233 isolated from the algae Sargassum horneri in response to abiotic stress elicitation by CuCl2. Their structures were established by spectroscopic means. New compounds 1 and 2 showed tyrosinase inhibitory activities with IC50 value of 14.8 µM and 22.3 µM.

  18. Three core concepts for producing uranium-233 in commercial pressurized light water reactors for possible use in water-cooled breeder reactors

    International Nuclear Information System (INIS)

    Selected prebreeder core concepts are described which could be backfit into a reference light water reactor similar to current commercial reactors, and produce uranium-233 for use in water-cooled breeder reactors. The prebreeder concepts were selected on the basis of minimizing fuel system development and reactor changes required to permit a backfit. The fuel assemblies for the prebreeder core concepts discussed would occupy the same space envelope as those in the reference core but contain a 19 by 19 array of fuel rods instead of the reference 17 by 17 array. An instrument well and 28 guide tubes for control rods have been allocated to each prebreeder fuel assembly in a pattern similar to that for the reference fuel assemblies. Backfit of these prebreeder concepts into the reference reactor would require changes only to the upper core support structure while providing flexibility for alternatives in the type of fuel used

  19. Fission Cross-section Measurements of (233)U, (245)Cm and (241,243)Am at CERN n_TOF Facility

    CERN Document Server

    Calviani, M; Andriamonje, S; Chiaveri, E; Vlachoudis, V; 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; Alvarez-Velarde, F; Cano-Ott, D; Gonzalez-Romero, E; Guerrero, C; Martinez, T; Villamarin, D; Vicente, M C; 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; Kadi, Y; 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; Heil, M; 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; 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

    Neutron-induced fission cross-sections of minor actinides have been measured using the n_TOF white neutron source at CERN, Geneva, as part of a large experimental program aiming at collecting new data relevant for nuclear astrophysics and for the design of advanced reactor systems. The measurements at n_TOF take advantage of the innovative features of the n_TOF facility, namely the wide energy range, high instantaneous neutron flux and good energy resolution. Final results on the fission cross-section of 233U, 245Cm and 243Am from thermal to 20 MeV are here reported, together with preliminary results for 241Am. The measurement have been performed with a dedicated Fast Ionization Chamber (FIC), a fission fragment detector with a very high efficiency, relative to the very well known cross-section of 235U, measured simultaneously with the same detector.

  20. Distinct Patterns of Association of Variants at 11q23.3 Chromosomal Region with Coronary Artery Disease and Dyslipidemia in the Population of Andhra Pradesh, India.

    Science.gov (United States)

    Pranav Chand, Rayabarapu; Kumar, Arramraju Sreenivas; Anuj, Kapadia; Vishnupriya, Satti; Mohan Reddy, Battini

    2016-01-01

    In our attempt to comprehensively understand the nature of association of variants at 11q23.3 apolipoprotein gene cluster region, we genotyped a prioritized set of 96 informative SNPs using Fluidigm customized SNP genotyping platform in a sample of 508 coronary artery disease (CAD) cases and 516 controls. We found 12 SNPs as significantly associated with CAD at P <0.05, albeit only four (rs2849165, rs17440396, rs6589566 and rs633389) of these remained significant after Benjamin Hochberg correction. Of the four, while rs6589566 confers risk to CAD, the other three SNPs reduce risk for the disease. Interaction of variants that belong to regulatory genes BUD13 and ZPR1 with APOA5-APOA4 intergenic variants is also observed to significantly increase the risk towards CAD. Further, ROC analysis of the risk scores of the 12 significant SNPs suggests that our study has substantial power to confer these genetic variants as predictors of risk for CAD, as illustrated by AUC (0.763; 95% CI: 0.729-0.798, p = <0.0001). On the other hand, the protective SNPs of CAD are associated with elevated Low Density Lipoprotein Cholesterol and Total Cholesterol levels, hence with dyslipidemia, in our sample of controls, which may suggest distinct effects of the variants at 11q23.3 chromosomal region towards CAD and dyslipidemia. It may be necessary to replicate these findings in the independent and ethnically heterogeneous Indian samples in order to establish this as an Indian pattern. However, only functional analysis of the significant variants identified in our study can provide more precise understanding of the mechanisms involved in the contrasting nature of their effects in manifesting dyslipidemia and CAD. PMID:27257688

  1. Distinct Patterns of Association of Variants at 11q23.3 Chromosomal Region with Coronary Artery Disease and Dyslipidemia in the Population of Andhra Pradesh, India.

    Directory of Open Access Journals (Sweden)

    Rayabarapu Pranav Chand

    Full Text Available In our attempt to comprehensively understand the nature of association of variants at 11q23.3 apolipoprotein gene cluster region, we genotyped a prioritized set of 96 informative SNPs using Fluidigm customized SNP genotyping platform in a sample of 508 coronary artery disease (CAD cases and 516 controls. We found 12 SNPs as significantly associated with CAD at P <0.05, albeit only four (rs2849165, rs17440396, rs6589566 and rs633389 of these remained significant after Benjamin Hochberg correction. Of the four, while rs6589566 confers risk to CAD, the other three SNPs reduce risk for the disease. Interaction of variants that belong to regulatory genes BUD13 and ZPR1 with APOA5-APOA4 intergenic variants is also observed to significantly increase the risk towards CAD. Further, ROC analysis of the risk scores of the 12 significant SNPs suggests that our study has substantial power to confer these genetic variants as predictors of risk for CAD, as illustrated by AUC (0.763; 95% CI: 0.729-0.798, p = <0.0001. On the other hand, the protective SNPs of CAD are associated with elevated Low Density Lipoprotein Cholesterol and Total Cholesterol levels, hence with dyslipidemia, in our sample of controls, which may suggest distinct effects of the variants at 11q23.3 chromosomal region towards CAD and dyslipidemia. It may be necessary to replicate these findings in the independent and ethnically heterogeneous Indian samples in order to establish this as an Indian pattern. However, only functional analysis of the significant variants identified in our study can provide more precise understanding of the mechanisms involved in the contrasting nature of their effects in manifesting dyslipidemia and CAD.

  2. Distinct Patterns of Association of Variants at 11q23.3 Chromosomal Region with Coronary Artery Disease and Dyslipidemia in the Population of Andhra Pradesh, India

    Science.gov (United States)

    Kumar, Arramraju Sreenivas; Anuj, Kapadia; Vishnupriya, Satti

    2016-01-01

    In our attempt to comprehensively understand the nature of association of variants at 11q23.3 apolipoprotein gene cluster region, we genotyped a prioritized set of 96 informative SNPs using Fluidigm customized SNP genotyping platform in a sample of 508 coronary artery disease (CAD) cases and 516 controls. We found 12 SNPs as significantly associated with CAD at P <0.05, albeit only four (rs2849165, rs17440396, rs6589566 and rs633389) of these remained significant after Benjamin Hochberg correction. Of the four, while rs6589566 confers risk to CAD, the other three SNPs reduce risk for the disease. Interaction of variants that belong to regulatory genes BUD13 and ZPR1 with APOA5-APOA4 intergenic variants is also observed to significantly increase the risk towards CAD. Further, ROC analysis of the risk scores of the 12 significant SNPs suggests that our study has substantial power to confer these genetic variants as predictors of risk for CAD, as illustrated by AUC (0.763; 95% CI: 0.729–0.798, p = <0.0001). On the other hand, the protective SNPs of CAD are associated with elevated Low Density Lipoprotein Cholesterol and Total Cholesterol levels, hence with dyslipidemia, in our sample of controls, which may suggest distinct effects of the variants at 11q23.3 chromosomal region towards CAD and dyslipidemia. It may be necessary to replicate these findings in the independent and ethnically heterogeneous Indian samples in order to establish this as an Indian pattern. However, only functional analysis of the significant variants identified in our study can provide more precise understanding of the mechanisms involved in the contrasting nature of their effects in manifesting dyslipidemia and CAD. PMID:27257688

  3. 听性脑干反应与听觉稳态反应对233例听力复筛未通过婴幼儿早期听力测试结果分析%Analysis of ABR and ASSR test in early hearing diagnostic of 233 infants failed in second hearing screening

    Institute of Scientific and Technical Information of China (English)

    张东红; 王玉璟; 马秀岚

    2012-01-01

    Objective; To discuss the effect of ABR and ASSR test in early hearing diagnostic of infants failed in second hearing screening. Methods: ABR and ASSR were tested in 233 (466 ears) in first and second hearing diagnostic, the results were analyzed. Results;Of 233 infants, 64 infants were normal in first diagnostic tested in 1 to 3 months, 169 infants were with one or two cars hearing loss, among them 88 with milder hearing loss, 60 with moderate hearing loss 12 of the 60 infants with severe hearing loss, 9 with very severe hearing loss. 106 infants accepted second diagnostic test, among them 60 infants with normal hearing, 46 infants with hearing loss 12 of the 46 infants with milder hearing loss, 15 with moderate hearing loss, 10 with severe hearing loss, 9 with very severe hearing loss. Conclusion; Hearing loss infants can de early founded by ABR and ASSR test. ABR and ASSR also provide accurate diagnostic test for early hearing intervention.%目的:探讨听性脑干反应(ABR)与听觉稳态反应(ASSR)在听力复筛未通过婴幼儿早期听力评估中的作用.方法:对233例(466耳)听力复筛未通过的婴幼儿使用ABR、ASSR测试,进行听力学初诊及复诊.分析ABR与ASSR的临床应用情况.结果:233例婴幼儿,在1~3个月时初诊听力正常64例,单耳或双耳听力损失169例,其中轻度88例,中度60例,重度12例,极重度9例.6个月时复诊106例,听力正常60例,听力损失46例,其中轻度12例,中度15例,重度10例,极重度9例.失访63例.结论:ABR与ASSR联合应用可早期发现听力损失,为听力障碍的早期干预提供可靠的依据.

  4. Complete genomic sequences of Campylobacter jejuni strains RM3196 (233.94) and RM3197 (308.95) that were isolated from patients with Guillain-Barré Syndrome

    Science.gov (United States)

    An infection with Campylobacter jejuni subsp. jejuni (Cjj) is a leading cause of foodborne gastroenteritis in humans and also the most prevalent infection preceding Guillain-Barré syndrome (GBS). This study describes the complete genomic sequences of Cjj HS:41 strains RM3196 (233.94) and RM3197 (308...

  5. cis- and trans-2,3,3a,4,5,9b-Hexahydro-1H-benz[e]indoles: synthesis and evaluation of dopamine D2, and D3 receptor binding affinity

    DEFF Research Database (Denmark)

    Song, Xiaodong; Crider, Michael A.; Cruse, Sharon F.;

    1999-01-01

    cis- and trans-2,3,3a,4,5,9b-hexahydro-1H-benz [e]indoles were synthesized as conformationally rigid analogues of 3-phenylpyrrolidine and evaluated for dopamine (DA) D2S and D3 receptor binding affinity. The tricyclic benz[e]indole nucleus was constructed by a previously reported reductive aminat...

  6. Multiwavelength investigation of a near-solar metallicity sub-DLA at z =1.3647 towards PKS 0237-233

    CERN Document Server

    Srianand, R; Petitjean, P; Srianand, Raghunathan; Gupta, Neeraj; Petitjean, Patrick

    2006-01-01

    We searched for 21-cm absorption associated with the z_abs = 1.3647 absorption system toward PKS 0237-233 using the GMRT. A high quality UVES spectrum shows that C I and C I* are detected at this redshift together with C II*, Mg I, Mg II, Si II, Al II, Fe II and Mn II. The complex profiles, spread over ~300 km/s, are fitted with 21 Voigt profile components. None of these components are detected in 21-cm absorption down to a detection limit of \\tau(3\\sigma)\\le 3x10^{-3} (or N(HI)/T_S -0.33. Using photoionization models constrained by the fine-structure excitations of C I and C II, and the 21-cm optical depth, we show that the C I absorption arises predominantly either in WIM or WNM in ionization and thermal equilibrium with the meta-galactic UV background dominated by QSOs and star forming galaxies. The estimated thermal pressure of the gas is of the same order of magnitude over different velocity ranges through the absorption profile (2.6\\le log [P/k cm^{-3} K]\\le 4.0). The gas-phase metallicity corrected for...

  7. Molecular level characterization of diatom-associated biopolymers that bind 234Th, 233Pa, 210Pb, and 7Be in seawater: A case study with Phaeodactylum tricornutum

    Science.gov (United States)

    Chuang, Chia-Ying; Santschi, Peter H.; Xu, Chen; Jiang, Yuelu; Ho, Yi-Fang; Quigg, Antonietta; Guo, Laodong; Hatcher, Patrick G.; Ayranov, Marin; Schumann, Dorothea

    2015-09-01

    In order to investigate the importance of biogenic silica associated biopolymers on the scavenging of radionuclides, the diatom Phaeodactylum tricornutum was incubated together with the radionuclides 234Th, 233Pa, 210Pb, and 7Be during their growth phase. Normalized affinity coefficients were determined for the radionuclides bound with different organic compound classes (i.e., proteins, total carbohydrates, uronic acids) in extracellular (nonattached and attached exopolymeric substances), intracellular (ethylene diamine tetraacetic acid and sodium dodecyl sulfate extractable), and frustule embedded biopolymeric fractions (BF). Results indicated that radionuclides were mostly concentrated in frustule BF. Among three measured organic components, Uronic acids showed the strongest affinities to all tested radionuclides. Confirmed by spectrophotometry and two-dimensional heteronuclear single quantum coherence-nuclear magnetic resonance analyses, the frustule BF were mainly composed of carboxyl-rich, aliphatic-phosphoproteins, which were likely responsible for the strong binding of many of the radionuclides. Results from this study provide evidence for selective absorption of radionuclides with different kinds of diatom-associated biopolymers acting in concert rather than as a single compound. This clearly indicates the importance of these diatom-related biopolymers, especially frustule biopolymers, in the scavenging and fractionation of radionuclides used as particle tracers in the ocean.

  8. Production of actinium-225 for alpha particle mediated radioimmunotherapy.

    Science.gov (United States)

    Boll, Rose A; Malkemus, Dairin; Mirzadeh, Saed

    2005-05-01

    The initial clinical trials for treatment of acute myeloid leukemia have demonstrated the effectiveness of the alpha emitter (213)Bi in killing cancer cells. Bismuth-213 is obtained from a radionuclide generator system from decay of 10-days (225)Ac parent. Recent pre-clinical studies have also shown the potential application of both (213)Bi, and the (225)Ac parent radionuclide in a variety of cancer systems and targeted radiotherapy. This paper describes our five years of experience in production of (225)Ac in partial support of the on-going clinical trials. A four-step chemical process, consisting of both anion and cation exchange chromatography, is utilized for routine separation of carrier-free (225)Ac from a mixture of (228)Th, (229)Th and (232)Th. The separation of Ra and Ac from Th is achieved using the marcoporous anion exchange resin MP1 in 8M HNO(3) media. Two sequential MP1/NO(3) columns provide a separation factor of approximately 10(6) for Ra and Ac from Th. The separation of Ac from Ra is accomplished on a low cross-linking cation exchange resin AG50-X4 using 1.2M HNO(3) as eluant. Two sequential AG50/NO(3) columns provide a separation factor of approximately 10(2) for Ac from Ra. A 60-day processing schedule has been adopted in order to reduce the processing cost and to provide the highest levels of (225)Ac possible. Over an 8-week campaign, a total of approximately 100 mCi of (225)Ac (approximately 80% of the theoretical yield) is shipped in 5-6 batches, with the first batch typically consisting of approximately 50 mCi. After the initial separation and purification of Ac, the Ra pool is re-processed on a bi-weekly schedule or as needed to provide smaller batches of (225)Ac. The averaged radioisotopic purity of the (225)Ac was 99.6 +/- 0.7% with a (225)Ra content of < or =0.6%, and an average (229)Th content of (4(-4)(+5)) x 10(-5)%.

  9. Chemical and spectrochemical production analysis of ThO2 and 233UO2-ThO2 pellets for the light water breeder reactor core for Shippingport (LWBR development program)

    International Nuclear Information System (INIS)

    The Bettis Atomic Power Laboratory has utilized wet chemical, emission spectrochemical, and mass spectrometric analytical techniques for the production analysis of the ThO2 and 233UO2-ThO2 (1 to 6 wt percent 233UO2) pellets for the Light Water Breeder Reactor (LWBR) core for Shippingport. Proof of the fuel breeding concept necessitates measurement of precise and accurate chemical characterization of all fuel pellets before core life. Chemistry's efforts toward this goal are presented in three main sections: (1) general discussions relating the chemical requirements for ThO2 and 233UO2-ThO2 core materials to the analytical capabilities, (2) technical discussions of the chemical and instrumental technology applied for the analysis of aluminum, boron, calcium, carbon, chloride plus bromide, chromium, cobalt, copper, dysprosium, europium, fluoride, gadolinium, iron, magnesium, manganese, mercury, molybdenum, nickel, nitrogen, samarium, silicon, titanium, vanadium, thorium, and uranium (total, trace, and uranium VI), and (3) a formal presentation of the analytical procedures as applied to the LWBR Development Program. (U.S.)

  10. The Energies, Angular Distribution and Yields of the Prompt Neutrons from Individual Fragments in the Thermal-Neutron Fission of U233 and U235

    International Nuclear Information System (INIS)

    An apparatus for simultaneously recording the velocities of both fission fragments and the velocity of a neutron at any one of four angles to the fragment direction has been used to investigate the neutron-emission properties of individual fragments. Early results for U233 exhibit the saw-tooth variation of v, the neutron yield per fragment, observed in the spontaneous fission of Cf252 The yields in the vicinity of mass 130 are consistent with no neutrons being emitted from these fragments. Unlike the neutron yields, the average neutron kinetic energy is symmetric about the symmetric mass point, being high near this point and low at the most probable mass division. The paradox between very small yields and high apparent nuclear temperatures has been qualitatively explained on the basis of a model that takes account of shell structure in the level densities and assumes that at the time of scission the fragments are cold but in some cases highly deformed, in others nearly spherical. The model is supported by the fact that in fissions with more than the average total excitation energy, the fragments near mass 130 and 80 receive much less than half the increase in energy and the other fragment of the pair much more. The experiment is now being conducted with U235 under considerably improved conditions. The background per channel under the neutron spectrum has been reduced by nearly a factor of three, so that 0.39 of all recorded events in the 10° detector are useful neutron events with a corresponding increase in statistical accuracy. Better time resolution in the fragment system (1.5 ns, full width at half maximum) has allowed the. flight paths to be shortened to 125 and 100 cm (formerly 145-145 cm) with a concomitant higher countings rate. (author)

  11. The applicability of MGA method for depleted and natural uranium isotopic analysis in the presence of actinides (232Th, 237Np, 233Pa and 241Am).

    Science.gov (United States)

    Yücel, Haluk

    2007-11-01

    The multi-group analysis (MGA) method for the determination of uranium isotopic abundances in depleted uranium (DU) and natural uranium (NU) samples is applied in this study. A set of non-destructive gamma-ray measurements of DU and NU samples were performed using a planar Ge detector. The relative abundances of 235U and 238U isotopes were compared with the declared values of the standards. The relative abundance for 235U obtained by MGA for a "clean" DU or NU sample with a content of uranium>1wt% is determined with an accuracy of about +/-5%. However, when several actinides such as 232Th, 237Np, 233Pa and 241Am are present along with uranium isotopes simulating "dirty" DU or NU, it has been observed that MGA method gives erroneous results. The 235U abundance results for the samples were 6-25 times higher than the declared values in the presence of above-mentioned actinides, since MGA is utilized the X-ray and gamma-ray peaks in the 80-130 keV energy region, covering XKalpha and XKbeta regions. After the least-squares fitting of the spectra, it is found that the increases in the intensities of the X-ray and gamma-ray peaks of uranium are remarkably larger in the complex 80-130 keV region. On the other hand, it is observed that the interferences of the actinide peaks are relatively less dominant in the higher gamma-ray region of 130-300 keV. The results imply the need for dirty DU and NU samples that the MGA method should utilize the higher energy gamma-rays (up to 1001 keV of (234m)Pa) combined with lower energies of the spectra, which may be collected in a two detector mode (a planar Ge and a high efficient coaxial Ge). PMID:17606378

  12. Fusion hybrids for generation of advanced (231Pa+232U+233U+234U)-fuel in closed (U-Pu-Th)-fuel cycle

    International Nuclear Information System (INIS)

    Technology of controlled thermonuclear fusion (CTF) is traditionally regarded as a practically inexhaustible energy source. However, development, mastering, broad deployment of fast breeder reactors and closure of nuclear fuel cycle (NFC) can also extend fuel base of nuclear power industry (NPI) up to practically unlimited scales. Under these conditions, it seems reasonable to introduce into a circle of the CTF-related studies the works directed towards solving some principal problems which can appear in a large-scale NPI in closed NFC. The first challenge is a large scale of operations in NFC back-end that should be reduced by achieving substantially higher fuel burn-up in power nuclear reactors. The use of 231Pa-232Th-232U-233U fuel in light-water reactor (LWR) opens a possibility of principle to reach very high (about 30% HM) or even ultra-high fuel burn-up. The second challenge is a potential unauthorized proliferation of fissionable materials. As is known, a certain remarkable quantity of 232U being introduced into uranium fraction of nuclear fuel can produce a serious barrier against switching the fuel over to non-energy purposes. Involvement of hybrid thermonuclear reactors (HTR) into NPI structure can substantially facilitate resolving these problems. If HTR will be involved into NPI structure, then main HTR mission consists not in energy generation but in production of nuclear fuel with a certain isotope composition. The present paper analyzes some neutron-physical features in production of advanced nuclear fuels in thorium HTR blankets. The obtained results demonstrated that such a nuclear fuel may be characterized by very stable neutron-multiplying properties during full LWR operation cycle and by enhanced proliferation resistance too. The paper evaluates potential benefits from involvement of HTR with thorium blanket into the international closed NFC. (author)

  13. An Investigation on Government Affairs Micro-Blog and its Improvement Direction---Empirical Evidence from the Investigation on 233 Civil Servants for Chongqing%政务微博的公共治理调查及提升方向*--基于重庆市233个样本数据的分析

    Institute of Scientific and Technical Information of China (English)

    王正攀; 陈文权; 徐信贵

    2015-01-01

    The government affairs micro-blog is not only development of the result from times, but also the concrete embodiment of a-bility of improving government’s public governance. Investigation is adopted on 233 civil servants of ChongQing on knowledge degree, concern degree,satisfaction and social effects on government affairs micro-blog by means of questionnaire. Through these analyses,it is found that:First, there are three features for the survey sample,which are “the higher proportion of owning micro-blog,the higher fre-quency of using micro-blog,a higher degree of interest on the government affairs micro-blog”;Second, the relationship between the sur-vey civil servant’s ages is negatively correlated with its knowledge degree under the age of 46,and the education and awareness are posi-tively related;Third, the survey sample of micro-blog government’ s concern degree is weak. However, the satisfaction is not high;Fourth,the investigation on 233 civil servants’ social effect of government micro-blog hold a positive and positive attitude. Finally,this paper explores some measures to overcome these bottlenecks,such as regular system,professional training ,increasing promotional ef-forts.%“政务微博”不仅是时代发展的结果,也是提升政府公共服务治理能力的具体体现。以问卷调查的方式,调查了重庆市233个公务员样本对政务微博知晓度、关注度、满意度以及社会效果等方面态度。研究发现:调查样本呈现出“有微博账号比例高、使用微博频率高、对政务微博兴趣度较高”的特点;46岁以下调查样本的年龄段与政务微博知晓度呈负相关关系,学历程度与政务微博知晓度呈正相关关系;调查样本对对政务微博的关注度偏弱,满意度不高;调查样本对政务微博的社会效果持肯定、正面态度。最后,从完善制度、专业人才培养、加大推广力度等方面提出了改进建议。

  14. Expeditious method to determine uranium in the process control samples of chemical plant separating (233)U from thoria irradiated in power reactors.

    Science.gov (United States)

    Kedari, C S; Kharwandikar, B K; Banerjee, K

    2016-11-01

    Analysis of U in the samples containing a significant proportion of (232)U and high concentration of Th is of great concern. Transmutation of Th in the nuclear power reactor produces a notable quantity of (232)U (half life 68.9 years) along with fissile isotope (233)U. The decay series of (232)U is initiated with (228)Th (half life 1.9 year) and it is followed by several short lived α emitting progenies, (224)Ra, (220)Rn, (216)Po, (212)Bi and (212)Po. Even at the smallest contamination of (228)Th in the sample, a very high pulse rate of α emission is obtained, which is to be counted for the radiometric determination of [U]. A commercially available anionic type of extractant Alamine®336 is used to obtain the selective extraction of U from other alpha active elements and fission products present in the sample. Experimental conditions of liquid-liquid extraction (LLE) are optimized for obtaining maximum decontamination and recovery of U in the organic phase. The effect of some interfering ionic impurities in the sample on the process of separation is investigated. Depending on the level of the concentration of U in the samples, spectrophotometry or radiometry methods are adopted for its determination after separation by LLE. Under optimized experimental conditions, i.e. 5.5M HCl in the aqueous phase and 0.27M Alamin®336 in the organic phase, the recovery of U is about 100%, the decontamination factor with respect to Th is >2000 and the extraction of fission products like (90)Sr, (144)Ce and (134,137)Cs is negligible. The detection limit for [U] using α radiometry is 10mg/L, even in presence of >100g/L of Th in the sample. Accuracy and precision for the determination of U is also assessed. Reproducibility of results is within 5%. This method shows very good agreement with the results obtained by mass spectrometry.

  15. A replication study of GWAS-derived lipid genes in Asian Indians: the chromosomal region 11q23.3 harbors loci contributing to triglycerides.

    Directory of Open Access Journals (Sweden)

    Timothy R Braun

    Full Text Available Recent genome-wide association scans (GWAS and meta-analysis studies on European populations have identified many genes previously implicated in lipid regulation. Validation of these loci on different global populations is important in determining their clinical relevance, particularly for development of novel drug targets for treating and preventing diabetic dyslipidemia and coronary artery disease (CAD. In an attempt to replicate GWAS findings on a non-European sample, we examined the role of six of these loci (CELSR2-PSRC1-SORT1 rs599839; CDKN2A-2B rs1333049; BUD13-ZNF259 rs964184; ZNF259 rs12286037; CETP rs3764261; APOE-C1-C4-C2 rs4420638 in our Asian Indian cohort from the Sikh Diabetes Study (SDS comprising 3,781 individuals (2,902 from Punjab and 879 from the US. Two of the six SNPs examined showed convincing replication in these populations of Asian Indian origin. Our study confirmed a strong association of CETP rs3764261 with high-density lipoprotein cholesterol (HDL-C (p = 2.03×10(-26. Our results also showed significant associations of two GWAS SNPs (rs964184 and rs12286037 from BUD13-ZNF259 near the APOA5-A4-C3-A1 genes with triglyceride (TG levels in this Asian Indian cohort (rs964184: p = 1.74×10(-17; rs12286037: p = 1.58×10(-2. We further explored 45 SNPs in a ∼195 kb region within the chromosomal region 11q23.3 (encompassing the BUD13-ZNF259, APOA5-A4-C3-A1, and SIK3 genes in 8,530 Asian Indians from the London Life Sciences Population (LOLIPOP (UK and SDS cohorts. Five more SNPs revealed significant associations with TG in both cohorts individually as well as in a joint meta-analysis. However, the strongest signal for TG remained with BUD13-ZNF259 (rs964184: p = 1.06×10(-39. Future targeted deep sequencing and functional studies should enhance our understanding of the clinical relevance of these genes in dyslipidemia and hypertriglyceridemia (HTG and, consequently, diabetes and CAD.

  16. The effect of dissolved hydrogen on the dissolution of {sup 233}U doped UO{sub 2}(s) high burn-up spent fuel and MOX fuel

    Energy Technology Data Exchange (ETDEWEB)

    Carbol, P. [Inst. for Transuranium Elements, Karlsruhe (Germany); Spahiu, K. (ed.) [and others

    2005-03-01

    In this report the results of the experimental work carried out in a large EU-research project (SFS, 2001-2004) on spent fuel stability in the presence of various amounts of near field hydrogen are presented. Studies of the dissolution of {sup 233}U doped UO{sub 2}(s) simulating 'old' spent fuel were carried out as static leaching tests, autoclave tests with various hydrogen concentrations and electrochemical tests. The results of the leaching behaviour of a high burn-up spent fuel pellet in 5 M NaCl solutions in the presence of 3.2 bar H{sub 2} pressure and of MOX fuel in dilute synthetic groundwater under 53 bar H{sub 2} pressure are also presented. In all the experimental studies carried out in this project, a considerable effect of hydrogen in the dissolution rates of radioactive materials was observed. The experimental results obtained in this project with a-doped UO{sub 2}, high burn-up spent fuel and MOX fuel together with literature data give a reliable background to use fractional alteration/dissolution rates for spent fuel of the order of 10{sup -6}/yr - 10{sup -8}/yr with a recommended value of 4x10{sup -7}/yr for dissolved hydrogen concentrations above 10{sup -3} M and Fe(II) concentrations typical for European repository concepts. Finally, based on a review of the experimental data and available literature data, potential mechanisms of the hydrogen effect are also discussed. The work reported in this document was performed as part of the Project SFS of the European Commission 5th Framework Programme under contract no FIKW-CT-2001-20192 SFS. It represents the deliverable D10 of the experimental work package 'Key experiments using a-doped UO{sub 2} and real spent fuel', coordinated by SKB with the participation of ITU, FZK-INE, ENRESA, CIEMAT, ARMINES-SUBATECH and SKB.

  17. Expeditious method to determine uranium in the process control samples of chemical plant separating (233)U from thoria irradiated in power reactors.

    Science.gov (United States)

    Kedari, C S; Kharwandikar, B K; Banerjee, K

    2016-11-01

    Analysis of U in the samples containing a significant proportion of (232)U and high concentration of Th is of great concern. Transmutation of Th in the nuclear power reactor produces a notable quantity of (232)U (half life 68.9 years) along with fissile isotope (233)U. The decay series of (232)U is initiated with (228)Th (half life 1.9 year) and it is followed by several short lived α emitting progenies, (224)Ra, (220)Rn, (216)Po, (212)Bi and (212)Po. Even at the smallest contamination of (228)Th in the sample, a very high pulse rate of α emission is obtained, which is to be counted for the radiometric determination of [U]. A commercially available anionic type of extractant Alamine®336 is used to obtain the selective extraction of U from other alpha active elements and fission products present in the sample. Experimental conditions of liquid-liquid extraction (LLE) are optimized for obtaining maximum decontamination and recovery of U in the organic phase. The effect of some interfering ionic impurities in the sample on the process of separation is investigated. Depending on the level of the concentration of U in the samples, spectrophotometry or radiometry methods are adopted for its determination after separation by LLE. Under optimized experimental conditions, i.e. 5.5M HCl in the aqueous phase and 0.27M Alamin®336 in the organic phase, the recovery of U is about 100%, the decontamination factor with respect to Th is >2000 and the extraction of fission products like (90)Sr, (144)Ce and (134,137)Cs is negligible. The detection limit for [U] using α radiometry is 10mg/L, even in presence of >100g/L of Th in the sample. Accuracy and precision for the determination of U is also assessed. Reproducibility of results is within 5%. This method shows very good agreement with the results obtained by mass spectrometry. PMID:27591623

  18. 232Th、233U、238Pu、240Pu、242Pu、241Am、242Cm、243Cm和244Cm的裂变释放热能研究%Thermal Energy Released in Fission of 232 Th,233 U,238 Pu, 240 Pu,242 Pu,241 Am,242 Cm,243 Cm and 244 Cm

    Institute of Scientific and Technical Information of China (English)

    赵艳飞; 马续波; 陈义学

    2013-01-01

    In the nuclear reactor design ,the precise calculation of thermal fission energy is of great significance .In the pressurized water reactor ,high energy neutron-induced fission rarely occurs ,the isotopes including 233 U ,241 Am and 243 Cm are mostly induced by thermal neutrons ,while the other isotopes such as 232Th ,238Pu ,240Pu ,242Pu ,242Cm and 244 Cm are by fast neutron . In order to carry out this work , the nuclear data extracted from the latest evaluated nuclear data file (ENDF/B-Ⅶ ) were adopted ,and the energy-conservation law for the calculation of total fission energy were used , meanw hile ,with the consideration of capture energy and the correction of βand γ ,the thermal fission energy of nine isotopes was obtained .Compared with the data excerpted from IAEA issued WIMS-D database ,the results are reasonable .The thermal fission energy and its uncertainties of the nine isotopes are :(193.939 ± 0.176) MeV for 232 Th , (200.063 ± 0.084) MeV for 233 U ,(208.786 ± 1.133 ) MeV for 238 Pu ,(211.266 ± 0.220 ) MeV for 240 Pu ,(213.862 ± 0.299 ) MeV for 242 Pu ,(215.077 ± 0.210 ) MeV for 241 Am ,(218.821 ± 0.159) MeV for 242Cm ,(218.525 ± 0.388) MeV for 243Cm ,and (220.067 ± 0.131) MeV for 244 Cm ,respectively .%在核反应堆设计中,对每次裂变释放热能进行精确计算具有重要意义。在压水堆内,高能中子诱发核裂变份额很小,233 U、241 Am、243 Cm主要由热中子诱发裂变,232 T h、238 Pu、240 Pu、242 Pu、242 Cm、244 Cm主要由快中子诱发裂变。本文采用最新的核评价数据库 ENDF/B-Ⅶ,利用质量守恒法计算裂变释放总能,同时研究了中微子带走的能量,中子俘获能及β、γ修正项,最终给出了9种核素裂变释放热能。与IAEA颁布的WIMS-D格式数据库中的裂变释放热能数据的对比表明,本文所用方法计算结果合理。9种核素每次裂变释放热能分别为:232 Th ,(193.939±0.176) MeV ;233 U ,(200.063

  19. Synthesis of methyl [(chloro-2 ethyl)-3 nitroso-3 Ureido]-3 Didesoxy-2,3 α-D-Arabino-hexopyrannoside labelled with carbon-14 or carbon-13 (CY 233 - SR 90008)

    International Nuclear Information System (INIS)

    CY 233 (Ecomustine or SR 90098) is a new antitumour nitrosourea: it is characterized by a 2-chloroethylnitrosourea substituent on a dideoxycarbohydrate. It has been labelled with 14C on a) the carbonyl group of the urea in four stages starting with 14COCl2, b) the second carbon of the chloroethyl group in four stages starting with [14C] ethanolamine, and c) on the methyl group on the anomeric centre of the carbohydrate in three stages starting with 14CH3OH. The final position was also labelled with 13C starting with 13CH3OH. These differently labelled compounds are suitable for mechanistic studies of antitumour activity. (author)

  20. Preliminary results of calculations for heavy-water nuclear-power-plant reactors employing 235U, 233U, and 232Th as a fuel and meeting requirements of a nonproliferation of nuclear weapons

    Science.gov (United States)

    Ioffe, B. L.; Kochurov, B. P.

    2012-02-01

    A physical design is developed for a gas-cooled heavy-water nuclear reactor intended for a project of a nuclear power plant. As a fuel, the reactor would employ thorium with a small admixture of enriched uranium that contains not more than 20% of 235U. It operates in the open-cycle mode involving 233U production from thorium and its subsequent burnup. The reactor meets the conditions of a nonproliferation of nuclear weapons: the content of fissionable isotopes in uranium at all stages of the process, including the final one, is below the threshold for constructing an atomic bomb, the amount of product plutonium being extremely small.

  1. Measurement of neutron-induced fission cross-sections of Th232, U238, U233 and Np237 relative to U235 from 1 MeV to 200 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Shcherbakov, O.A.; Laptev, A.B.; Petrov, G.A. [Petersburg Nuclear Physics Inst., Gatchina, Leningrad district (Russian Federation); Fomichev, A.V.; Donets, A.Y.; Osetrov, O.I.

    1998-11-01

    The measurements of neutron-induced cross-section ratios for Th232, U238, U233 and Np237 relative to U235 have been carried out in the energy range from 1 MeV up to 200 MeV using the neutron time-of-flight spectrometer GNEIS based on 1 GeV proton synchrocyclotron. Below 20 MeV, the results of present measurements are roughly in agreement with evaluated data though there are some discrepances to be resolved. (author)

  2. Comparative effectiveness of incretin-based therapies and the risk of death and cardiovascular events in 38,233 metformin monotherapy users.

    Science.gov (United States)

    Gamble, John-Michael; Thomas, Jamie M; Twells, Laurie K; Midodzi, William K; Majumdar, Sumit R

    2016-06-01

    There is limited comparative effectiveness evidence to guide approaches to managing diabetes in individuals failing metformin monotherapy. Our aim was to compare the incidence of all-cause mortality and major adverse cardiovascular events (MACEs) among new metformin monotherapy users initiating a dipeptidyl-peptidase-4 inhibitor (DPP4i), glucagon-like peptide-1 receptor agonist (GLP-1RA), sulfonylurea (SU), thiazolidinedione, or insulin.We conducted a cohort study using the UK-based Clinical Practice Research Datalink. Participants included a cohort of 38,233 new users of metformin monotherapy who initiated a 2nd antidiabetic agent between January 1, 2007 and December 31, 2012 with follow-up until death, disenrollment, therapy discontinuation, or study end-date. A subcohort of 21,848 patients with linked hospital episode statistics (HES) and Office of National Statistics (ONS) data were studied to include MACE and cardiovascular-related death. The primary exposure contrasts, defined a priori, were initiation of a DPP4i versus an SU and initiation of a GLP-1RA versus an SU following metformin monotherapy. Cox proportional hazards models were used to assess the relative differences in time to mortality and MACE between exposure contrasts, adjusting for important baseline patient factors and comedications used during follow-up.The main study cohort consisted of 6213 (16%) patients who initiated a DPP4i, 25,916 initiated an SU (68%), 4437 (12%) initiated a TZD, 487 (1%) initiated a GLP-1RA, 804 (2%) initiated insulin, and 376 (1%) initiated a miscellaneous agent as their 2nd antidiabetic agent. Mean age was 62 years, 59% were male, and mean glycated hemoglobin was 8.8% (92.6 mmol/mol). Median follow-up was 2.7 years (interquartile range 1.3-4.2). Mortality rates were 8.2 deaths/1000 person-years for DPP4i and 19.1 deaths/1000 person-years for SU initiators. Adjusted hazards ratio (aHR) for mortality in DPP4i versus SU initiators = 0.58, 95% CI 0.46 to 0.73, P

  3. Measurement of the Neutron Capture Cross Sections of $^{233}$U, $^{237}$Np, $^{240,242}$Pu, $^{241,243}$Am and $^{245}$Cm with a Total Absorption Calorimeter at n_TOF

    CERN Multimedia

    Beer, H; Wiescher, M; Cox, J; Rapp, W; Embid, M; Dababneh, S

    2002-01-01

    Accurate and reliable neutron capture cross section data for actinides are necessary for the poper design, safety regulation and precise performance assessment of transmutation devices such as Fast Critical Reactors or Accelerator Driven Systems (ADS). The goal of this proposal is the measurement of the neutron capture cross sections of $^{233}$U, $^{237}$Np, $^{240,242}$Pu, $^{241,243}$Am and $^{245}$Cm at n_TOF with an accuracy of 5~\\%. $^{233}$U plays an essential role in the Th fuel cycle, which has been proposed as a safer and cleaner alternative to the U fuel cycle. The capture cross sections of $^{237}$Np,$^{240,242}$Pu, $^{241,243}$Am and $^{245}$Cm play a key role in the design and optimization of a strategy for the Nuclear Waste Transmutation. A high accuracy can be achieved at n_TOF in such measurements due to a combination of features unique in the world: high instantaneous neutron fluence and excellent energy resolution of the facility, innovative Data Acquisition System based on flash ADCs and t...

  4. Fase aguda da doença de Chagas na Amazônia brasileira: estudo de 233 casos do Pará, Amapá e Maranhão observados entre 1988 e 2005 Acute phase of Chagas disease in the Brazilian Amazon region: study of 233 cases from Pará, Amapá and Maranhão observed between 1988 and 2005

    Directory of Open Access Journals (Sweden)

    Ana Yecê das Neves Pinto

    2008-12-01

    Full Text Available Foram estudados 233 casos de fase aguda da doença de Chagas, oriundos do Pará, Amapá e Maranhão, observados no período de 1988 a 2005, cento e sessenta deles retrospectivamente de 1988 a 2002 e setenta e três prospectivamente de 2003 a 2005. Entre os casos estudados 78,5% (183/233 faziam parte de surtos provavelmente por transmissão oral, acometendo em média 4 pessoas e 21,5% (50/233 eram casos isolados. Foram considerados casos agudos aqueles que apresentaram exames parasitológicos diretos (a fresco, gota espessa ou Quantitative Buffy Coat - QBC e/ou IgM anti-Trypanosoma cruzi positivos. Foram feitos ainda xenodiagnósticos em 224 pacientes e hemoculturas em 213. Todos foram avaliados clinica e epidemiologicamente. As manifestações clínicas mais freqüentes foram febre (100%, cefaléia (92,3%, mialgia (84,1%, palidez (67%, dispnéia (58,4%, edema de membros inferiores (57,9%, edema de face (57,5% dor abdominal (44,2%, miocardite (39,9% e exantema (27%. O eletrocardiograma mostrou alterações de repolarização ventricular em 38,5% dos casos, baixa voltagem de QRS em 15,4% e desvio de SAQRS em 11,5%, extra-sístoles ventriculares em 5,8%, bradicardia em 5,8% e taquicardia em 5,8%, bloqueio de ramo direito em 4,8% e fibrilação atrial em 4,8%. A alteração mais freqüente vista no ecocardiograma foi o derrame pericárdico em 46,2% dos casos. Treze (5,6% pacientes evoluíram para o óbito, 10 (76,9% dos quais por comprometimento cardiovascular, dois por complicações de origem digestiva e um de causa mal definida.Two hundred and thirty-three cases of the acute phase of Chagas disease, from Pará, Amapá and Maranhão, were observed between 1988 and 2005. One hundred and sixty were studied retrospectively from 1988 to 2002 and seventy-three were prospectively followed up from 2003 to 2005. Among the cases studied, 78.5% (183/233 formed part of outbreaks, probably due to oral transmission (affecting a mean of 4 individuals, and 21

  5. Preliminary study of the α ratio measurement, ratio of the neutron capture cross section to the fission one for 233U, on the PEREN platform. Development and study of the experimental setup

    International Nuclear Information System (INIS)

    Producing nuclear energy in order to reduce anthropic CO2 emission and to meet high energy demand, implies three conditions to the nuclear plants of the IV. generation: safety improvements, radioactive waste minimization, and fuel breeding for a sustainable use of the resources. The Thorium fuel cycle used in Molten Salt Reactors seems promising. Many numerical studies based on probabilistic codes are carried out in order to analyse the behaviour of such reactors. Nevertheless, one of the most important parameters is badly known: the alpha ratio of 233U, ratio of the neutron capture cross section to fission one for 233U. This key-parameter is necessary to calculate the breeding ratio and thus, the deployment capacities of those reactors. This Ph-D thesis was intended to prepare a precise measurement of the alpha ratio of 233U between 1 eV and 10 keV. Preliminary measurements have been performed on the experimental platform PEREN. This experimental environment is composed of a lead slowing-down time spectrometer associated with an intense pulsed neutron generator. Capture and fission rates are measured thanks to eight scintillators with their photomultipliers, surrounding a fission chamber. A software analysis sets the coincidence rate between the scintillators. In order to understand perfectly the experimental setup, preliminary tests using a 235U fission chamber have been done. This experiment resulted in a very low signal to background ratio (1 %). The background coming from the scintillators themselves seriously handicapped the measurement. Another series of experiment has been done with scintillators 5 times thinner. Nevertheless, the signal to background ratio should still be increased to measure the capture of 235U. To make sure that the experimental setup has totally been understood, we made many comparisons between experimental results and simulations. Two simulation codes were mainly used: MCNP and GEANT4. We paid special attention to quantify the

  6. Preliminary study of the {alpha} ratio measurement, ratio of the neutron capture cross section to the fission one for {sup 233}U, on the PEREN platform. Development and study of the experimental setup; Etude preliminaire de la mesure du rapport {alpha}, rapport de la section efficace moyenne de capture sur celle de fission de l'{sup 233}U, sur la plateforme PEREN. Developpement et etude du dispositif experimental

    Energy Technology Data Exchange (ETDEWEB)

    Cognet, M.A

    2007-12-15

    Producing nuclear energy in order to reduce anthropic CO{sub 2} emission and to meet high energy demand, implies three conditions to the nuclear plants of the IV. generation: safety improvements, radioactive waste minimization, and fuel breeding for a sustainable use of the resources. The Thorium fuel cycle used in Molten Salt Reactors seems promising. Many numerical studies based on probabilistic codes are carried out in order to analyse the behaviour of such reactors. Nevertheless, one of the most important parameters is badly known: the alpha ratio of {sup 233}U, ratio of the neutron capture cross section to fission one for {sup 233}U. This key-parameter is necessary to calculate the breeding ratio and thus, the deployment capacities of those reactors. This Ph-D thesis was intended to prepare a precise measurement of the alpha ratio of {sup 233}U between 1 eV and 10 keV. Preliminary measurements have been performed on the experimental platform PEREN. This experimental environment is composed of a lead slowing-down time spectrometer associated with an intense pulsed neutron generator. Capture and fission rates are measured thanks to eight scintillators with their photomultipliers, surrounding a fission chamber. A software analysis sets the coincidence rate between the scintillators. In order to understand perfectly the experimental setup, preliminary tests using a {sup 235}U fission chamber have been done. This experiment resulted in a very low signal to background ratio (1 %). The background coming from the scintillators themselves seriously handicapped the measurement. Another series of experiment has been done with scintillators 5 times thinner. Nevertheless, the signal to background ratio should still be increased to measure the capture of {sup 235}U. To make sure that the experimental setup has totally been understood, we made many comparisons between experimental results and simulations. Two simulation codes were mainly used: MCNP and GEANT4. We paid

  7. New measurements of (n,γ) and (n,fission) cross sections and capture-to-fission ratios for ^233,235U and ^239Pu using the DANCE 4π BaF2 array

    Science.gov (United States)

    Bredeweg, T. A.; Jandel, M.; Fowler, M. M.; Bond, E. M.; Haight, R. C.; Keksis, A. L.; O'Donnell, J. M.; Reifarth, R.; Rundberg, R. S.; Ullmann, J. L.; Vieira, D. J.; Wilhelmy, J. B.; Wouters, J. M.; Becker, J. A.; Parker, W. E.; Wu, C. Y.; Baker, J. D.; McGrath, C. A.

    2009-10-01

    Accurate neutron nuclear data are important to many issues in stockpile stewardship, nuclear reactor design and re-certification, nuclear non-proliferation and nuclear forensics. Of particular interest are the production and destruction reactions for all of the major and most of the minor actinides. The competition between capture and fission in many of the actinides presents both an obstacle and an opportunity for large γ detector arrays such as DANCE. Additional instrumentation is required to deconvolve the two contributions to the total observed γ-ray spectrum. However, conducting a simultaneous measurement can simplify background treatment and other sources of systematic uncertainty. An outline of the current experimental program will be presented along with results from neutron capture measurements on ^233,235U and ^239Pu.

  8. Concept of a demonstrational hybrid reactor—a tokamak with molten-salt blanket for {sup 233}U fuel production: 1. Concept of a stationary Tokamak as a neutron source

    Energy Technology Data Exchange (ETDEWEB)

    Azizov, E. A.; Gladush, G. G., E-mail: gladush@triniti.ru; Dokuka, V. N.; Khayrutdinov, R. R. [State Research Center of the Russian Federation, Troitsk Institute for Innovation and Fusion Research (Russian Federation)

    2015-12-15

    On the basis of current understanding of physical processes in tokamaks and taking into account engineering constraints, it is shown that a low-cost facility of a moderate size can be designed within the adopted concept. This facility makes it possible to achieve the power density of neutron flux which is of interest, in particular, for solving the problem of {sup 233}U fuel production from thorium. By using a molten-salt blanket, the important task of ensuring the safe operation of such a reactor in the case of possible coolant loss is accomplished. Moreover, in a hybrid reactor with the blanket based on liquid salts, the problem of periodic refueling that is difficult to perform in solid blankets can be solved.

  9. Divergent, stereoselective access to heterocyclic α,α-quaternary- and β(2,3,3)-amino acid derivatives from a N-Pmp-protected Orn-derived β-lactam.

    Science.gov (United States)

    Núñez-Villanueva, Diego; García-López, M Teresa; Martín-Martínez, Mercedes; González-Muñiz, Rosario

    2015-05-14

    A suitably protected Orn-derived (3S,4S)-β-lactam was used as common intermediate in the synthesis of conformationally constrained (3S,4S)-2-oxoazepane α,α- and (2S,3S)-2-oxopiperidine-β(2,3,3)-amino acid derivatives. Compared to alternative procedures using an N-p-methoxybenzyl group at the 2-azetidinone, the incorporation of a p-methoxyphenyl moiety is crucial for the excellent stereochemical outcomes in the preparation of these heterocyclic amino acids. Chemoselective 7- or 6-exo-trig cyclization was achieved through alternative sequences of Pmp-deprotection/Boc-activation, followed by inter- and intramolecular β-lactam ring opening, respectively.

  10. Concept of a demonstrational hybrid reactor—a tokamak with molten-salt blanket for 233U fuel production: 1. Concept of a stationary Tokamak as a neutron source

    Science.gov (United States)

    Azizov, E. A.; Gladush, G. G.; Dokuka, V. N.; Khayrutdinov, R. R.

    2015-12-01

    On the basis of current understanding of physical processes in tokamaks and taking into account engineering constraints, it is shown that a low-cost facility of a moderate size can be designed within the adopted concept. This facility makes it possible to achieve the power density of neutron flux which is of interest, in particular, for solving the problem of 233U fuel production from thorium. By using a molten-salt blanket, the important task of ensuring the safe operation of such a reactor in the case of possible coolant loss is accomplished. Moreover, in a hybrid reactor with the blanket based on liquid salts, the problem of periodic refueling that is difficult to perform in solid blankets can be solved.

  11. Multilevel analysis of the 233U and 235U capture and fission cross-sections and statistical properties of the Kapur-Peierls-type resonance parameters for the S-wave cross-sections of the fissile isotopes

    International Nuclear Information System (INIS)

    At the 1966 Conference on Nuclear Data for Reactors, simultaneous measurements of the capture and fission cross-sections of 233U and 235U were presented. Those measurements have now been analysed with the multilevel formalism developed by Adler and Adler. To obtain consistent sets of resonance parameters the capture and fission data were least-square fitted simultaneously. This analysis was carried out to 60 eV for 233U and to 100 eV for 235U. The main purpose of this analysis was to provide a simple and precise analytical description of the very complex structure of the fission and capture cross-sections of 233U and 235U at low energy. Such an analytical description should be useful to calculate reaction rates in nuclear reactors and to compare experimental data taken with different energy resolutions or at different sample temperatures. For the low-energy resonances of 233U and 235U, the neutron width is always smaller, by at least two orders of magnitude, than the total width. Thus, the total cross-section, for those isotopes, can be approximated as the sum of the absorption cross-section and the potential scattering cross-section. Hence it is possible to compute the total cross-section from the resonance parameters obtained by fitting the fission and capture cross-sections. The total cross-section of 235U computed by this method is compared to the data from a transmission measurement done at Saclay, with the sample at 77 deg. K. The computed total cross-section of 233U is compared with transmission data obtained at Oak Ridge National Laboratory and at the Material Testing Reactor. Such comparisons between data obtained by different experimental techniques illustrate the internal consistency of the low-energy cross-sections of the two main uranium fissile isotopes. The physical interpretation of the resonance parameters is somewhat ambiguous, because such multilevel fits are by no means unique. This is particularly true for 233U since, for this nucleus, the

  12. Synthesis and Crystal Structure of(3S,4R,Z)-3,6-dimethyl-2-(3-methylbut-2-enylidene)-2,3,3a,4,7,7a-hexahydrobenzofuran-3,4-diol

    Institute of Scientific and Technical Information of China (English)

    CHEN Lei; FANG Hu-Biao; HUANG Nian-Yu; WANG Jun-Zhi; ZOU Kun

    2011-01-01

    The title compound of(3S,4R,Z)-3,6-dimethyl-2-(3-methylbut-2-enylidene)-2,3,3a,4,7,7a-hexahydrobenzofuran-3,4-diol,C15H22O3,as a potential gastric cytoprotective agent has been synthesized by the reduction of bisabolangelone in methanol with sodium borohydride.The title compound was characterized by IR and NMR spectra.Meanwhile,the crystal was obtained and determined by X-ray single-crystal diffraction.Crystal data:monoclinic system,space group P21 with a = 6.0692(12),b = 8.9954(18),c = 13.182(3) ,β = 92.59(3)°,V = 718.9(2) 3,Z = 2,F(000) = 272,Dc = 1.156 g/cm3,μ = 0.633 mm-1,R = 0.0362 and wR = 0.1051 for 9490 independent reflections(Rint = 0.0172) and 2461 observed reflections(I 2σ(I)).Intermolecular O-H…O interactions link the molecules into one-dimensional infinite chains running along the b axis,which contributes to the stability of the crystal structure.

  13. Measurements of Cross Sections and Decay Properties of the Isotopes of Elements 112, 114 and 116 Produced in the Fusion Reactions $^{233,238}$U, $^{242}$Pu, and $^{248}$Cm + $^{48}$Ca

    CERN Document Server

    Oganessian, Yu T; Utyonkov, V K; Lobanov, Yu V; Abdullin, F S; Polyakov, A N; Shirokovsky, I V; Tsyganov, Yu S; Gulbekyan, G G; Bogomolov, S L; Gikal, B N; Mezentsev, A N; Iliev, S; Subbotin, V G; Sukhov, A M; Voinov, A A; Buklanov, G V; Subotic, K M; Zagrebaev, V I; Itkis, M G; Patin, J B; Moody, K J; Wild, J F; Stoyer, M A; Stoyer, N J; Shaughnessy, D A; Kenneally, J M; Wilk, P A; Lougheed, R W; Ilkaev, R I; Vesnovskii, S P

    2004-01-01

    We have studied the dependence of the production cross-sections of the isotopes $^{282,283}$112 and $^{286,287}$114 on the excitation energy of the compound nuclei $^{286}$112 and $^{290}$114. The maximum cross-section values of the \\textit{xn}-evaporation channels for the reaction $^{238}$U($^{48}$Ca, \\textit{xn})$^{286 - x}$112 were measured to be: $\\sigma _{3n}=2.5_{-1.1}^{ + 1.8} $pb and $\\sigma _{4n}=0.6_{ - 0.5}^{ + 1.6} $ pb; for the reaction $^{242}$Pu($^{48}$Ca, \\textit{xn})$^{290 - x}$114: $\\sigma _{2n}\\sim 0.5$ pb, $\\sigma _{3n}=3.6_{- 1.7}^{ + 3.4} $ pb and $\\sigma _{4n}=4.5_{ - 1.9}^{ + 3.6} $ pb. In the reaction $^{233}$U($^{48}$Ca, 2--4$n$)$^{277 - 279}$112 at $E^*=34.9\\pm $2.2 MeV we measured an upper cross-section limit of $\\sigma _{xn} \\leqslant 0.6$ pb. The observed shift of the excitation energy associated with the maximum sum evaporation residue cross section $\\sigma _{\\rm {ER}}(E^*)$ to values significantly higher than that associated with the calculated Coulomb barrier can be caused by ...

  14. Measurement and calculation of absolute single- and double-charge-exchange cross sections for O6 + ions at 1.17 and 2.33 keV/u impacting He and H2

    Science.gov (United States)

    Machacek, J. R.; Mahapatra, D. P.; Schultz, D. R.; Ralchenko, Yu.; Chutjian, A.; Simcic, J.; Mawhorter, R. J.

    2014-11-01

    Absolute single- and double-charge-exchange cross sections for the astrophysically prominent O6 + ion with the atomic and molecular targets He and H2 are reported. These collisions give rise to x-ray emissions in the interplanetary medium, planetary atmospheres, and comets as they approach the sun. Measurements have been carried out using the Caltech Jet Propulsion Laboratory electron cyclotron resonance ion source with O6 + at energies of 1.17 and 2.33 keV/u characteristic of the slow and fast components of the solar wind. Absolute charge-exchange (CE) data are derived from knowledge of the target gas pressure, target path length, incident ion current, and charge-exchanged ion currents. These data are compared with results obtained using the n -electron classical trajectory Monte Carlo method. The radiative and Auger evolution of ion populations following one- and two-electron transfers is calculated with the time-dependent collisional-radiative code nomad using atomic data from the flexible atomic code. Calculated CE emission spectra for 100 Å <λ <1400 Å are reported as well and compared with experimental sublevel spectra and cross sections.

  15. Synthesis and Crystal Structure of Copper (Ⅱ) Compound with 3,3'-Azobispyridine Ligand[Cu(NO3)2(H2O)2(3,3'-azpy)2

    Institute of Scientific and Technical Information of China (English)

    李宝龙; 郎建平; 王寿武; 徐正; 陈久桐

    2003-01-01

    The title complex [Cu(NO3)2(H2O)2(3,3'-azpy)2] (3,3'-azpy = 3,3'-azobispyridine) has been synthesized and characterized, and its crystal belongs to the triclinic system, space group P ī with the following crystallographic parameters: a = 7.4161(2), b = 8.1754(3), c = 10.7545(4) A。,α= 92.958(2),β= 109.978(1),γ = 93.369(2)°, V = 609.96(4) A。3, C20H20N10CuO8, Mr = 592.00, Dc = 1.612 g/cm3, μ(MoKα)= 0.964 mm-1, F(000) = 303, Z = 1, the final R = 0.0494 and wR = 0.1269 for 1945 observed reflections (I > 2((I)). X-ray analysis reveals that the Cu atom adopts a distorted octahedral (4 + 2) coordination. The four closer donor atoms include two N atoms of 3,3'-azpy and two Oatoms of the coordination aqua with the Cu-N and Cu-O distances of 2.014(3) and 1.974(3)A。, respectively. Two longer out-of-plane Cu-O bonds (2.450(3) A。) from nitrate complete the strongly distorted octahedral coordination of the Cu atom. Hydrogen bonds are formed through H atoms of each coordination aqua with the remaining N atoms of 3,3'-azpy and O atoms of nitrate. A two-dimensional network is constructed by hydrogen bonds and π-π interactions.

  16. 233西番莲%Passionflower1

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    @@ 又名 Apricot Vine, Corona De Cristo, Fleischfarbige, Fleur De La Passion, Flor De Passion, Madre Selva, Maypop, Maypop Passion Flower, Passiflora, Passiflorae herba, Passiflore, Passiflorina, Passion Flower, Passion Vine, Passionaria, Passionblume, Passionflower Herb, Passionsblumenkraut,Purple Passion Flower, Water Lemon, Wild Passion Flower.

  17. Energy Magazine. V. 23(3)

    International Nuclear Information System (INIS)

    The permanent secretariat of OLADE, with financial support of the European Commission, will carry out the National Energetic Information System , through which the tools will be developed for the elaboration and administration of the energy statistics in the member states of the organization. It is also included a vision on the action program in energy for the Caribbean to unify efforts and to coordinate actions leading the energy development and the diversification of the energy supply in order to satisfy their requirements. A section of the magazine, it is dedicated to the transformation experienced by the energy sector in Peru

  18. 37 CFR 2.33 - Verified statement.

    Science.gov (United States)

    2010-07-01

    ... behalf of the applicant under § 2.193(e)(1). (b)(1) In an application under section 1(a) of the Act, the... likely, when applied to the goods or services of the other person, to cause confusion or mistake, or to... 44 of the Act, the verified statement must allege: That the applicant has a bona fide intention...

  19. 40 CFR 233.70 - Michigan.

    Science.gov (United States)

    2010-07-01

    ... susceptible for use in their natural condition or by reasonable improvement as a means to transport interstate... December 9, 1983. (2) The Memorandum of Agreement between the U.S. Army Corps of Engineers and the...

  20. 39 CFR 233.12 - Civil penalties.

    Science.gov (United States)

    2010-07-01

    ... Civil penalties. False representation and lottery orders— (a) Issuance. Pursuant to 39 U.S.C. 3005, the... matter which is nonmailable, or engaged in conducting a lottery, gift enterprise, or scheme for the distribution of money or of real or personal property, by lottery, chance, or drawing of any kind....

  1. 34 CFR 668.233 - Student eligibility.

    Science.gov (United States)

    2010-07-01

    ... intellectual disability, as described in paragraph (1) of the definition of a student with an intellectual... as the Social Security Administration or a vocational rehabilitation agency, that identifies...

  2. 45 CFR 233.60 - Institutional status.

    Science.gov (United States)

    2010-10-01

    ... patient in an institution for tuberculosis or mental diseases. (ii) Federal financial participation under... has not attained 65 years of age and who is a patient in an institution for tuberculosis or mental..., or a patient in an institution for tuberculosis or mental diseases; (ii) Whether an institution...

  3. 12 CFR 233.2 - Definitions.

    Science.gov (United States)

    2010-01-01

    ... customer means when a particular fact with respect to that transaction or commercial customer is known by or brought to the attention of: (1) An individual in the organization responsible for the organization's compliance function with respect to that transaction or commercial customer; or (2) An...

  4. 39 CFR 233.3 - Mail covers.

    Science.gov (United States)

    2010-07-01

    ... transcription, photograph, photocopy or any other facsimile of the image of the outside cover, envelope, wrapper... Inspector may also delegate any or all authority to the Manager, Inspector Service Operations Support Group... Support Group, may delegate this authority to no more than two designees at each Operations Support...

  5. Overexpression of the catalytically impaired Taspase1 T234V or Taspase1 D233A variants does not have a dominant negative effect in T(4;11 leukemia cells.

    Directory of Open Access Journals (Sweden)

    Carolin Bier

    Full Text Available BACKGROUND: The chromosomal translocation t(4;11(q21;q23 is associated with high-risk acute lymphoblastic leukemia of infants. The resulting AF4•MLL oncoprotein becomes activated by Taspase1 hydrolysis and is considered to promote oncogenic transcriptional activation. Hence, Taspase1's proteolytic activity is a critical step in AF4•MLL pathophysiology. The Taspase1 proenzyme is autoproteolytically processed in its subunits and is assumed to assemble into an αββα-heterodimer, the active protease. Therefore, we investigated here whether overexpression of catalytically inactive Taspase1 variants are able to interfere with the proteolytic activity of the wild type enzyme in AF4•MLL model systems. METHODOLOGY/FINDINGS: The consequences of overexpressing the catalytically dead Taspase1 mutant, Taspase1(T234V, or the highly attenuated variant, Taspase1(D233A, on Taspase1's processing of AF4•MLL and of other Taspase1 targets was analyzed in living cancer cells employing an optimized cell-based assay. Notably, even a nine-fold overexpression of the respective Taspase1 mutants neither inhibited Taspase1's cis- nor trans-cleavage activity in vivo. Likewise, enforced expression of the α- or β-subunits showed no trans-dominant effect against the ectopically or endogenously expressed enzyme. Notably, co-expression of the individual α- and β-subunits did not result in their assembly into an enzymatically active protease complex. Probing Taspase1 multimerization in living cells by a translocation-based protein interaction assay as well as by biochemical methods indicated that the inactive Taspase1 failed to assemble into stable heterocomplexes with the wild type enzyme. CONCLUSIONS: Collectively, our results demonstrate that inefficient heterodimerization appears to be the mechanism by which inactive Taspase1 variants fail to inhibit wild type Taspase1's activity in trans. Our work favours strategies targeting Taspase1's catalytic activity

  6. The applicability of MGA method for depleted and natural uranium isotopic analysis in the presence of actinides ({sup 232}Th, {sup 237}Np, {sup 233}Pa and {sup 241}Am)

    Energy Technology Data Exchange (ETDEWEB)

    Yuecel, Haluk [TAEK-Saraykoey Nuclear Research and Training Center, Atom Cad. No.27, Saray Mah, 06983 Ankara (Turkey)], E-mail: haluk.yucel@taek.gov.tr

    2007-11-15

    The multi-group analysis (MGA) method for the determination of uranium isotopic abundances in depleted uranium (DU) and natural uranium (NU) samples is applied in this study. A set of non-destructive {gamma}-ray measurements of DU and NU samples were performed using a planar Ge detector. The relative abundances of {sup 235}U and {sup 238}U isotopes were compared with the declared values of the standards. The relative abundance for {sup 235}U obtained by MGA for a 'clean' DU or NU sample with a content of uranium >1 wt% is determined with an accuracy of about {+-}5%. However, when several actinides such as {sup 232}Th, {sup 237}Np, {sup 233}Pa and {sup 241}Am are present along with uranium isotopes simulating 'dirty' DU or NU, it has been observed that MGA method gives erroneous results. The {sup 235}U abundance results for the samples were 6-25 times higher than the declared values in the presence of above-mentioned actinides, since MGA is utilized the X-ray and {gamma}-ray peaks in the 80-130 keV energy region, covering XK{sub {alpha}} and XK{sub {beta}} regions. After the least-squares fitting of the spectra, it is found that the increases in the intensities of the X-ray and {gamma}-ray peaks of uranium are remarkably larger in the complex 80-130 keV region. On the other hand, it is observed that the interferences of the actinide peaks are relatively less dominant in the higher {gamma}-ray region of 130-300 keV. The results imply the need for dirty DU and NU samples that the MGA method should utilize the higher energy {gamma}-rays (up to 1001 keV of {sup 234m}Pa) combined with lower energies of the spectra, which may be collected in a two detector mode (a planar Ge and a high efficient coaxial Ge)

  7. Comparison of the response (in terms of accumulation, cellular and genetic impacts) of the crayfish Procambarus clarkii after exposure to a metallic pollutant (cadmium) and to a radiological pollutant (uranium 238 and 233)

    International Nuclear Information System (INIS)

    The study of the effects of radionuclides and metals on organisms is necessary for the evaluation of their toxicity and their ecological threats. We first aimed to study the impacts of cadmium (Cd) and Uranium (U) on different biological levels of the crayfish Procambarus clarkii after acute and chronic exposures. We evaluated their impacts on mitochondria, oxidative stress responses, on histological structures, and the survival rates. We tried to connect these effects between them and to the bioaccumulation in the gills and the hepato pancreas. We also tried to discriminate the chemo and the radiotoxicity of U by exposing crayfish to either depleted or enriched U (233U: presenting a higher specific activity) using the same criteria of effects. We demonstrated that the gene mt encoding for the metallothionein was always over-expressed in the presence of Cd. Therefore, it seems to be a good bio-marker of Cd toxicity in P. clarkii. The follow up of mitochondrial genes expressions (12s, atp6 and cox1), showed that both metals affect mitochondria and that their mechanisms of action do not seem to be always the same. We also observed that U generates more oxidative stress than Cd when comparing the expression levels of genes encoding for antioxidants (sod (Mn) and mt) and the enzymatic activities of superoxide dismutase, the catalase, the glutathione peroxidase and the glutathione S transferase. However, the symptoms of histo-pathological damages after Cd and U contamination were similar in both conditions. After comparing the survival rates of the crayfish, we concluded that Cd was more toxic than the radioelement. Moreover, we demonstrated that the toxic effect of U on P. clarkii exposed to a low environmental concentration is mainly due to its chemo-toxicity rather than to its radiotoxicity. We established that, the molecular answers vary according to the intensity and the duration of the chemical stress applied to the organisms. We suggested the use of the

  8. Measurements of cross sections and decay properties of the isotopes of elements 112, 114, and 116 produced in the fusion reactions 233,238U, 242Pu, and 248Cm+48Ca

    International Nuclear Information System (INIS)

    We have studied the dependence of the production cross sections of the isotopes 282,283112 and 286,287114 on the excitation energy of the compound nuclei 286112 and 290114. The maximum cross section values of the xn-evaporation channels for the reaction 238U(48Ca,xn)286-x112 were measured to be σ3n=2.5-1.1+1.8 pb and σ4n=0.6-0.5+1.6 pb; for the reaction 242Pu(48Ca,xn)290-x114: σ2n∼0.5 pb, σ3n=3.6-1.7+3.4 pb, and σ4n=4.5-1.9+3.6 pb. In the reaction 233U(48Ca,2-4n)277-279112 at E*=34.9=2.2 MeV we measured an upper cross section limit of σxn≤0.6 pb. The observed shift of the excitation energy associated with the maximum sum evaporation residue cross section σER(E*) to values significantly higher than that associated with the calculated Coulomb barrier can be caused by the orientation of the deformed target nucleus in the entrance channel of the reaction. An increase of σER in the reactions of actinide targets with 48Ca is consistent with the expected increase of the survivability of the excited compound nucleus upon closer approach to the closed neutron shell N=184. In the present work we detected 33 decay chains arising in the decay of the known nuclei 282112, 283112, 286114, 287114, and 288114. In the decay of 287114(α)→283112(α)→279110(SF), in two cases out of 22, we observed decay chains of four and five sequential α transitions that end in spontaneous fission of 271Sg (Tα/SF=2.4-1.0+4.3 min) and 267Rf (TSF∼2.3 h), longer decay chains than reported previously. We observed the new nuclide 292116 (Tα=18-6+16 ms,Eα=10.66±0.07 MeV) in the irradiation of the 248Cm target at a higher energy than in previous experiments. The observed nuclear decay properties of the nuclides with Z=104-118 are compared with theoretical nuclear mass calculations and the systematic trends of spontaneous fission properties. As a whole, they give a consistent pattern of decay of the 18 even-Z neutron-rich nuclides with Z=104-118 and N=163-177. The experiments were

  9. Purification of selenium from thorium, uranium, radium, actinium and potassium impurities for low background measurements

    International Nuclear Information System (INIS)

    A technique of selenium purification from 232Th, 238U, 226,228Ra, 227Ac and 40K was developed. This technique is simple to perform and employs a minimum number of highly pure reagents (bidistilled water, nitric acid). Operations carried out during purification (elution, evaporation) practically exclude losses of the target product (chemical yields of Se > 99%). A test purification of 100 g of selenium was carried out using this technique. The efficiency of this technique was confirmed by low background gamma spectrometry of the purified selenium sample. Distribution coefficients of Th, U, Ra and Ac on DOWEX 50W- x 8 cation-exchange resin at different concentrations of selenium and nitric acid were experimentally determinated. Instrumental neutron activation analysis of bidistilled water, deionized water and nitric acid was performed. (orig.)

  10. Radium-228 analysis of natural waters by Cherenkov counting of Actinium-228

    Energy Technology Data Exchange (ETDEWEB)

    Aleissa, Khalid A.; Almasoud, Fahad I.; Islam, Mohammed S. [Atomic Energy Research Institute, King Abdul Aziz City for Science and Technology, P.O. Box 6086, Riyadh 11442 (Saudi Arabia); L' Annunziata, Michael F. [IAEA Expert, Montague Group, P.O. Box 5033, Oceanside, CA 92052-5033 (United States)], E-mail: mlannunziata@cox.net

    2008-12-15

    The activities of {sup 228}Ra in natural waters were determined by the Cherenkov counting of the daughter nuclide {sup 228}Ac. The radium was pre-concentrated on MnO{sub 2} and the radium purified via ion exchange and, after a 2-day period of incubation to allow for secular equilibrium between the parent-daughter {sup 228}Ra({sup 228}Ac), the daughter nuclide {sup 228}Ac was isolated by ion exchange according to the method of Nour et al. [2004. Radium-228 determination of natural waters via concentration on manganese dioxide and separation using Diphonix ion exchange resin. Appl. Radiat. Isot. 61, 1173-1178]. The Cherenkov photons produced by {sup 228}Ac were counted directly without the addition of any scintillation reagents. The optimum Cherenkov counting window, sample volume, and vial type were determined experimentally to achieve optimum Cherenkov photon detection efficiency and lowest background count rates. An optimum detection efficiency of 10.9{+-}0.1% was measured for {sup 228}Ac by Cherenkov counting with a very low Cherenkov photon background of 0.317{+-}0.013 cpm. The addition of sodium salicylate into the sample counting vial at a concentration of 0.1 g/mL yielded a more than 3-fold increase in the Cherenkov detection efficiency of {sup 228}Ac to 38%. Tests of the Cherenkov counting technique were conducted with several water standards of known activity and the results obtained compared closely with a conventional liquid scintillation counting technique. The advantages and disadvantages of Cherenkov counting compared to liquid scintillation counting methods are discussed. Advantages include much lower Cherenkov background count rates and consequently lower minimal detectable activities for {sup 228}Ra and no need for expensive environmentally unfriendly liquid scintillation cocktails. The disadvantages of the Cherenkov counting method include the need to measure {sup 228}Ac Cherenkov photon detection efficiency and optimum Cherenkov counting volume, which are not at all required when liquid scintillation analysis is used.

  11. Radium-228 analysis of natural waters by Cherenkov counting of Actinium-228.

    Science.gov (United States)

    Aleissa, Khalid A; Almasoud, Fahad I; Islam, Mohammed S; L'Annunziata, Michael F

    2008-12-01

    The activities of (228)Ra in natural waters were determined by the Cherenkov counting of the daughter nuclide (228)Ac. The radium was pre-concentrated on MnO(2) and the radium purified via ion exchange and, after a 2-day period of incubation to allow for secular equilibrium between the parent-daughter (228)Ra((228)Ac), the daughter nuclide (228)Ac was isolated by ion exchange according to the method of Nour et al. [2004. Radium-228 determination of natural waters via concentration on manganese dioxide and separation using Diphonix ion exchange resin. Appl. Radiat. Isot. 61, 1173-1178]. The Cherenkov photons produced by (228)Ac were counted directly without the addition of any scintillation reagents. The optimum Cherenkov counting window, sample volume, and vial type were determined experimentally to achieve optimum Cherenkov photon detection efficiency and lowest background count rates. An optimum detection efficiency of 10.9+/-0.1% was measured for (228)Ac by Cherenkov counting with a very low Cherenkov photon background of 0.317+/-0.013cpm. The addition of sodium salicylate into the sample counting vial at a concentration of 0.1g/mL yielded a more than 3-fold increase in the Cherenkov detection efficiency of (228)Ac to 38%. Tests of the Cherenkov counting technique were conducted with several water standards of known activity and the results obtained compared closely with a conventional liquid scintillation counting technique. The advantages and disadvantages of Cherenkov counting compared to liquid scintillation counting methods are discussed. Advantages include much lower Cherenkov background count rates and consequently lower minimal detectable activities for (228)Ra and no need for expensive environmentally unfriendly liquid scintillation cocktails. The disadvantages of the Cherenkov counting method include the need to measure (228)Ac Cherenkov photon detection efficiency and optimum Cherenkov counting volume, which are not at all required when liquid scintillation analysis is used.

  12. Purification of selenium from thorium, uranium, radium, actinium and potassium impurities for low background measurements

    Energy Technology Data Exchange (ETDEWEB)

    Rakhimov, A.V. [Joint Institute for Nuclear Research (JINR), Dubna (Russian Federation); Uzbek Academy of Sciences, Tashkent (Uzbekistan). Inst. of Nuclear Physics (INP AS RUz); Warot, G. [CEA-CNRS, Modane (France). Laboratoire Souterrain de Modane (LSM); Karaivanov, D.V. [Joint Institute for Nuclear Research (JINR), Dubna (Russian Federation); Institute for Nuclear Research and Nuclear Energy (INRNE), Sofia (Bulgaria); Kochetov, O.I.; Lebedev, N.A.; Filosofov, D.V. [Joint Institute for Nuclear Research (JINR), Dubna (Russian Federation); Mukhamedshina, N.M.; Sadikov, I.I. [Uzbek Academy of Sciences, Tashkent (Uzbekistan). Inst. of Nuclear Physics (INP AS RUz)

    2013-07-01

    A technique of selenium purification from {sup 232}Th, {sup 238}U, {sup 226,228}Ra, {sup 227}Ac and {sup 40}K was developed. This technique is simple to perform and employs a minimum number of highly pure reagents (bidistilled water, nitric acid). Operations carried out during purification (elution, evaporation) practically exclude losses of the target product (chemical yields of Se > 99%). A test purification of 100 g of selenium was carried out using this technique. The efficiency of this technique was confirmed by low background gamma spectrometry of the purified selenium sample. Distribution coefficients of Th, U, Ra and Ac on DOWEX 50W- x 8 cation-exchange resin at different concentrations of selenium and nitric acid were experimentally determinated. Instrumental neutron activation analysis of bidistilled water, deionized water and nitric acid was performed. (orig.)

  13. Linear free energy relationship applied to trivalent cations with lanthanum and actinium oxide and hydroxide structure

    International Nuclear Information System (INIS)

    Linear free energy relationships for trivalent cations with crystalline M2O3 and, M(OH)3 phases of lanthanides and actinides were developed from known thermodynamic properties of the aqueous trivalent cations, modifying the Sverjensky and Molling equation. The linear free energy relationship for trivalent cations is as ΔGf,MvX0=aMvXΔGn,M3+0+bMvX+βMvXrM3+, where the coefficients aMvX, bMvX, and βMvX characterize a particular structural family of MvX, rM3+ is the ionic radius of M3+ cation, ΔGf,MvX0 is the standard Gibbs free energy of formation of MvX and ΔGn,M3+0 is the standard non-solvation free energy of the cation. The coefficients for the oxide family are: aMvX=0.2705, bMvX=-1984.75 (kJ/mol), and βMvX=197.24 (kJ/molnm). The coefficients for the hydroxide family are: aMvX=0.1587, bMvX=-1474.09 (kJ/mol), and βMvX=791.70 (kJ/molnm).

  14. Actinium: A RESTful Runtime Container for Scriptable Internet of Things Applications

    OpenAIRE

    Kovatsch, Matthias; Lanter, Martin; Duquennoy, Simon

    2012-01-01

    Programming Internet of Things (IoT) applications is challenging because developers have to be knowledgeable in various technical domains, from low-power networking, over embedded operating systems, to distributed algorithms. Hence, it will be challenging to find enough experts to provide software for the vast number of expected devices, which must also be scalable and particularly safe due to the connection to the physical world. To remedy this situation, we propose an architecture that pr...

  15. Reflection asymmetry in odd-A and odd-odd actinium nuclei

    International Nuclear Information System (INIS)

    Theoretical calculations and measurements indicate that octupole correlations are at a maximum in the ground states of the odd-proton nuclei Ac and Pa. It has been expected that odd-odd nuclei should have even larger amount of octupole-octupole correlations. We have recently made measurements on the structure of 224Ac. Although spin and parity assignments could not be made, two bands starting at 354.1 and 360.0 keV have properties characteristic of reflection asymmetric shape. These two bands have very similar rotational constants and also similar alpha decay rates, which suggest similarity between the wavefunctions of these bands. These signatures provide evidence for octupole correlations in these nuclides

  16. Bestimmung der Ionisationsenergie von Actinium und Ultraspurenanalyse von Plutonium mit resonanter Ionisationsmassenspektrometrie (RIMS)

    OpenAIRE

    Waldek, Achim Marcus

    2001-01-01

    ZusammenfassungDie Resonanzionisationsmassenspektrometrie (RIMS) verbindet hohe Elementselektivität mit guter Nachweiseffizienz. Aufgrund dieser Eigenschaften ist die Methode für Ultraspurenanalyse und Untersuchungen an seltenen oder schwer handhabbaren Elementen gut geeignet. Für RIMS werden neutrale Atome mit monochromatischem Laserlicht ein- oder mehrfach resonant auf energetisch hoch liegende Niveaus angeregt und anschließend durch einen weiteren Laserstrahl oder durch ein elektrisches Fe...

  17. New method for large scale production of medically applicable Actinium-225 and Radium-223

    International Nuclear Information System (INIS)

    Alpha-emitters (211At, 212Bi, 213Bi, 223Ra, 225Ac) are promising for targeted radiotherapy of cancer. Only two alpha decays near a cell membrane result in 50% death of cancer cell and only a single decay inside the cell is required for this. 225Ac may be used either directly or as a mother radionuclide in 213Bi isotope generator. Production of 225Ac is provided by three main suppliers - Institute for Transuranium Elements in Germany, Oak Ridge National Laboratory in USA and Institute of Physics and Power Engineering in Obninsk, Russia. The current worldwide production of 225Ac is approximately 1.7 Ci per year that corresponds to only 100-200 patients that could be treated annually. The common approach for 225Ac production is separation from mother 229Th or irradiation of 226Ra with protons in a cyclotron. Both the methods have some practical limitations to be applied routinely. 225Ac can be also produced by irradiation of natural thorium with medium energy protons . Cumulative cross sections of 225Ac, 227Ac, 227Th, 228Th formations have been obtained recently. Thorium targets (1-9 g) were irradiated by 114-91 MeV proton beam (1-50 μA) at INR linear accelerator. After dissolution in 8 M HNO3 + 0.004 M HF thorium was removed by double LLX by HDEHP in toluene (1:1). Ac and REE were pre-concentrated and separated from Ra and most fission products by DGA-Resin (Triskem). After washing out by 0.01 M HNO3 Ac was separated from REE by TRU Resin (Triskem) in 3 M HNO3 media. About 6 mCi 225Ac were separated in hot cell with chemical yield 85%. The method may be upscaled for production of Ci amounts of the radionuclide. The main impurity is 227Ac (0.1% at the EOB) but it does not hinder 225Ac from being used for medical 225Ac/213Bi generators. (author)

  18. Two mixed-ligand lanthanide–hydrazone complexes: [Pr(NCS3(pbh2]·H2O and [Nd(NCS(NO3(pbh2(H2O]NO3·2.33H2O [pbh is N′-(pyridin-2-ylmethylidenebenzohydrazide, C13H11N3O

    Directory of Open Access Journals (Sweden)

    Damianos G. Paschalidis

    2016-02-01

    Full Text Available The gel-mediated syntheses and crystal structures of [N′-(pyridin-2-ylmethylidene-κNbenzohydrazide-κ2N′,O]tris(thiocyanato-κNpraseodymium(III monohydrate, [Pr(NCS3(C13H11N3O2]·H2O, (I, and aqua(nitrato-κ2O,O′[N′-(pyridin-2-ylmethylidene-κNbenzohydrazide-κ2N′,O](thiocyanato-κNneodymium(III nitrate 2.33-hydrate, [Nd(NCS(NO3(C13H11N3O2(H2O]NO3·2.33H2O, (II, are reported. The Pr3+ ion in (I is coordinated by two N,N,O-tridentate N′-(pyridin-2-ylmethylidenebenzohydrazide (pbh ligands and three N-bonded thiocyanate ions to generate an irregular PrN7O2 coordination polyhedron. The Nd3+ ion in (II is coordinated by two N,N,O-tridentate pbh ligands, an N-bonded thiocyanate ion, a bidentate nitrate ion and a water molecule to generate a distorted NdN5O5 bicapped square antiprism. The crystal structures of (I and (II feature numerous hydrogen bonds, which lead to the formation of three-dimensional networks in each case.

  19. Purification of radium-226 for the manufacturing of actinium-225 in a cyclotron for alpha-immunotherapy; Radium-Aufreinigung zur Herstellung von Actinium-225 am Zyklotron fuer die Alpha-Immuntherapie

    Energy Technology Data Exchange (ETDEWEB)

    Marx, Sebastian Markus

    2014-09-23

    The thesis describes the development of methods for the purification of Ra-226. The objective was to obtain the radionuclide in the quality that is needed to be used as starting material in the manufacturing process for Ac-225 via proton-irradiated Ra-226. The radionuclide has been gained efficiently out of huge excesses of impurities. The high purity of the obtained radium affords its use as staring material in a pharmaceutical manufacturing process.

  20. Renal uptake of bismuth-213 and its contribution to kidney radiation dose following administration of actinium-225-labeled antibody

    Energy Technology Data Exchange (ETDEWEB)

    Schwartz, J; O' Donoghue, J A; Humm, J L [Department of Medical Physics, Memorial Sloan-Kettering Cancer Center, 1275 York Avenue, New York, NY 10065 (United States); Jaggi, J S [Bristol-Myers Squibb, Plainsboro, NJ (United States); Ruan, S; Larson, S M [Nuclear Medicine Service Department of Radiology, Memorial Sloan-Kettering Cancer Center, 1275 York Avenue, New York, NY 10065 (United States); McDevitt, M; Scheinberg, D A, E-mail: schwarj1@mskcc.org [Molecular Pharmacology and Chemistry, Sloan-Kettering Institute, 1275 York Avenue, New York, NY 10065 (United States)

    2011-02-07

    Clinical therapeutic studies using {sup 225}Ac-labeled antibodies have begun. Of major concern is renal toxicity that may result from the three alpha-emitting progeny generated following the decay of {sup 225}Ac. The purpose of this study was to determine the amount of {sup 225}Ac and non-equilibrium progeny in the mouse kidney after the injection of {sup 225}Ac-huM195 antibody and examine the dosimetric consequences. Groups of mice were sacrificed at 24, 96 and 144 h after injection with {sup 225}Ac-huM195 antibody and kidneys excised. One kidney was used for gamma ray spectroscopic measurements by a high-purity germanium (HPGe) detector. The second kidney was used to generate frozen tissue sections which were examined by digital autoradiography (DAR). Two measurements were performed on each kidney specimen: (1) immediately post-resection and (2) after sufficient time for any non-equilibrium excess {sup 213}Bi to decay completely. Comparison of these measurements enabled estimation of the amount of excess {sup 213}Bi reaching the kidney ({gamma}-ray spectroscopy) and its sub-regional distribution (DAR). The average absorbed dose to whole kidney, determined by spectroscopy, was 0.77 (SD 0.21) Gy kBq{sup -1}, of which 0.46 (SD 0.16) Gy kBq{sup -1} (i.e. 60%) was due to non-equilibrium excess {sup 213}Bi. The relative contributions to renal cortex and medulla were determined by DAR. The estimated dose to the cortex from non-equilibrium excess {sup 213}Bi (0.31 (SD 0.11) Gy kBq{sup -1}) represented {approx}46% of the total. For the medulla the dose contribution from excess {sup 213}Bi (0.81 (SD 0.28) Gy kBq{sup -1}) was {approx}80% of the total. Based on these estimates, for human patients we project a kidney-absorbed dose of 0.28 Gy MBq{sup -1} following administration of {sup 225}Ac-huM195 with non-equilibrium excess {sup 213}Bi responsible for approximately 60% of the total. Methods to reduce renal accumulation of radioactive progeny appear to be necessary for the success of {sup 225}Ac radioimmunotherapy.

  1. Production of actinium, thorium and radium isotopes from natural thorium irradiated with protons up to 141 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Ermolaev, S.V.; Zhuikov, B.L.; Kokhanyuk, V.M.; Matushko, V.L. [Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Research; Kalmykov, S.N. [Lomonosov Moscow State Univ., Moscow (Russian Federation). Chemistry Dept.; Aliev, R.A. [Lomonosov Moscow State Univ., Moscow (Russian Federation). Skobeltsyn Inst. of Nuclear Physics; Tananaev, I.G.; Myasoedov, B.F. [Russian Academy of Sciences, Moscow (Russian Federation). A.N. Frumkin Inst. of Physical Chemistry and Electrochemistry

    2012-07-01

    Cross sections of {sup 225}Ac, {sup 227}Ac, {sup 227}Th and {sup 228}Th in thorium-232 targets irradiated with protons in the energy range 21-141 MeV have been measured. Based on these data, production yields of {sup 225}Ac and {sup 223}Ra in thick thorium targets have been calculated. It is possible to produce in proton energy range 60-140 MeV about 96 GBq (2.6 Ci) {sup 225}Ac per 10-d irradiation with 100 {mu}A proton beam current and 10-d decay, and much higher amount of {sup 223}Ra. The impurities of {sup 227}Ac and {sup 224}Ra are important and need to be assessed for further medical applications. (orig.)

  2. Dicty_cDB: CHG233 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available sequence. 66 2e-18 3 BM056853 |BM056853.1 2154-85 hindgut and Malpighian tubule subtracted cDNA library Ctenocephalides...pighian tubule subtracted cDNA library Ctenocephalides felis cDNA clone 2193-94, ...mRNA sequence. 90 9e-14 1 BM058379 |BM058379.1 2191-29 hindgut and Malpighian tubule subtracted cDNA library Ctenocephalides

  3. 42 CFR 456.233 - Initial continued stay review date.

    Science.gov (United States)

    2010-10-01

    ... assigns the initial continued stay review date within 1 working day after the mental hospital is notified... SERVICES (CONTINUED) MEDICAL ASSISTANCE PROGRAMS UTILIZATION CONTROL Utilization Control: Mental Hospitals... must provide that— (a) When a recipient is admitted to the mental hospital under admission...

  4. Dicty_cDB: AFN233 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available isqem* cryscistih**n*titleiynnll*fkylynr*tkl*snskinv*n*ykrvingfsfti nyyt**ckd*stsnvtisyc*sd*ssl*sl*fsimcre...GLDDTLASR EEINKTLMLKISSIFLNFGLKLEKVEI--- ---*snskinv*n*ykrvingfsftinyyt**ckd*stsnvtisyc*sd*ssl*sl*fsi mcre...igsnitkinhw*ygfr*yfslk rgn**ninvkd**ylfkfws*irks*n--- ---ik*lkn*cikliqesh*wiflynqll...igsnitkinhw*ygfr*yfslkrgn**ninvkd**ylfkfws*irks*nfrnftft insrcitftnfirtct*skcnfsrrf

  5. 45 CFR 233.101 - Dependent children of unemployed parents.

    Science.gov (United States)

    2010-10-01

    ... subdivisions of the State, in which he or she attended, full-time, an elementary school, a secondary school, or... instruction for individuals who have not graduated from a secondary school or obtained an equivalent degree... absence, or incapacity of a parent may receive cash assistance under the AFDC program during the...

  6. 45 CFR 233.90 - Factors specific to AFDC.

    Science.gov (United States)

    2010-10-01

    ... Social Security Act.) (2) An otherwise eligible child who is under the age of 18 years may not be denied... State plan under title IV-A of the Social Security Act shall provide that: (1) The determination whether a child has been deprived of parental support or care by reason of the death, continued absence...

  7. Systems Requirement Document for the MSRE U-233 Conversion System

    Energy Technology Data Exchange (ETDEWEB)

    Aigner, R.D.

    2001-01-11

    The fissile material reclamation activities for the MSRE remediation project include the removal and recovery of uranium from the off-gas system, from the stored fuel salt, and finally, from the uranium-laden charcoal in the Auxiliary Charcoal Bed (ACB). Each of these operations produces an uranium/fluoride compound that is not suitable for long-term storage. The uranium-fluoride compounds can be stored for a limited period of time in pressure vessels. The interim-storage vessels are designed to handle the internal pressure buildup from gases formed by radiolysis of the uranium-fluoride compounds. The conversion process will take the pressurized vessels from interim storage and process the materials in a hot cell located at Building 4501. The gas in the vessels will be vented through chemical traps and then the traps will be processed to convert the various uranium-fluoride compounds to a stable uranium oxide form. This will be done one trap at a time. The chemical form of uranium being extracted from the off-gas system and from fuel salt fluorination process is uranium hexafluoride UF{sub 6}. During the operations at MSRE, the UF{sub 6} is chemisorbed onto sodium fluoride (NaF) traps where it forms the complex, 2NaF{center_dot}UF{sub 6}. The conversion process that will be installed in the Building 4501 Hot Cell D will recover the UF{sub 6} from the NaF traps by decomposition of the binary complex at elevated temperatures (>300 C). After the uranium is extracted from the NaF traps, it is collected in the conversion process reaction vessel. The reaction vessel is then hydrolized and heated through several step operations up to 900 C in order to convert the material to a stable uranium oxide. The ACB at MSRE contains uranium-laden charcoal with unstable C{sub x}F compounds. After extraction at MSRE, this material will be delivered to Building 4501 Hot Cell D for processing to a stable oxide. The charcoal conversion process is still under development, with mockup and full scale testing of the proposed flow sheet funded in FY 99 and FY 00. The uranium-laden charcoal has been pre-treated with ammonia to prevent the deflagration of the C{sub x}F if localized heating (>{approximately}150 C) occurs during the charcoal removal process. Prior to removal, the treatment will be performed a second time to denature the 1 to 5% reformation of C{sub x}F that has occurred due to radiolysis of NH{sub 4}F. The uranium-laden charcoal will be physically extracted and stored in several pressure vessels at MSRE until the conversion process is designed and installed in Hot Cell A in Building 4501.

  8. 39 CFR 233.2 - Circulars and rewards.

    Science.gov (United States)

    2010-07-01

    ... drugs, or proceeds from the sale of illegal drugs. Money Laundering, $50,000. Mailing or causing to be... controlled substances. (iii) Post office burglary. (iv) Stealing or unlawful possession of mail or money or..., counterfeiting, forging, unlawful uttering or passing of postal money orders; or the unlawful use,...

  9. 39 CFR 233.7 - Forfeiture authority and procedures.

    Science.gov (United States)

    2010-07-01

    ..., joint business enterprise, estate, or other legal entity capable of owning property. (xii) The term... remission or mitigation in judicial forfeiture cases are stated in 29 CFR 9.4. (5) Criteria governing... of leasing or renting property for profit, shall be granted remission or mitigation of forfeiture...

  10. 45 CFR 233.20 - Need and amount of assistance.

    Science.gov (United States)

    2010-10-01

    ... supplemental food assistance received under the Child Nutrition Act of 1966 as amended, and the special food... PROGRAMS), ADMINISTRATION FOR CHILDREN AND FAMILIES, DEPARTMENT OF HEALTH AND HUMAN SERVICES COVERAGE AND... Housing Act” means Department of Housing and Urban Development assisted housing which includes Indian...

  11. 45 CFR 233.51 - Eligibility of sponsored aliens.

    Science.gov (United States)

    2010-10-01

    .... Definition: Sponsor is any person who, or any public or private agency or organization that, executed an... by public or private agencies or organizations with respect to periods after October 1, 1984. A State... living in the same household as the sponsor who are or could be claimed by the sponsor as dependents...

  12. Dicty_cDB: VFE233 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available 1 BD183626 |BD183626.1 Material for diagnosing malaria and immune antigen for suppressing growth of plasmodi...um. 76 6e-61 10 BD183625 |BD183625.1 Material for diagnosing malaria and immune antigen for suppressing grow

  13. Treating 233 Cases of Dermatosis with Nettle%荨麻治疗三种皮肤疾患233

    Institute of Scientific and Technical Information of China (English)

    聂鲁

    2003-01-01

    @@ 受玉溪市卫生局和新平县科委的委托,新平县彝族医药翻译整理课题组于1999年9月至2002年10月期间,以新平县人民医院和新平县平甸乡卫生院为载体,对彝族药荨麻设课题进行临床运用研究,旨在通过临床观察,验证荨麻对荨麻疹、痤疮、黄褐斑等皮肤疾患的治疗功效,分析并推断其相应的药理药效.

  14. A study of reaction rates of (n,f), (n,γ) and (n,2n) reactions in natU and 232Th by the neutron fluence produced in the graphite set-up (GAMMA-3) irradiated by 2.33 GeV deuteron beam

    International Nuclear Information System (INIS)

    Spallation neutrons produced in the collision of a 2.33GeV deuteron beam with a large lead target are moderated by a thick graphite block surrounding the target and used to activate the radioactive samples of natU and Th put at three different positions, identified as holes ''a'', ''b'' and ''c'' in the graphite block. Rates of the (n,f), (n,γ) and (n,2n) reactions in the two samples are determined using the gamma spectrometry. The ratios of the experimental reaction rates, R (n,2n)/R (n,f), for 232Th and natU are estimated in order to understand the role of the (n,x n) kind of reactions in Accelerator-Driven Sub-critical Systems. For the Th-sample, the ratio is ∝ 54 (10)% in the case of hole ''a'' and ∝ 95 (57)% in the case of hole ''b'' compared to 1.73(20)% for hole ''a'' and 0.710(9)% for hole ''b'' in the case of the natU sample. Also the ratio of fission rates in uranium to thorium, natU (n,f)/ 232Th (n,f), is ∝ 11.2 (17) in the case of hole ''a'' and 26.8(85) in hole ''b''. Similarly, the ratio 238U (n,2n)/ 232Th (n,2n) is 0.36(4) for hole ''a'' and 0.20(10) for hole ''b'' showing that 232Th is more prone to the (n,x n) reaction than 238U. All the experimental reaction rates are compared with the simulated ones by generating neutron fluxes at the three holes from MCNPX 2.6c and making use of the LA150 library of cross-sections. The experimental and calculated reaction rates of all the three reactions are in reasonably good agreement. The transmutation power, Pnorm as well as Pnorm/Pbeam of the set-up is estimated using the reaction rates of the (n, γ) and (n,2n) reactions for both the samples in the three holes and compared with some of the results of the ''Energy plus Transmutation'' set-up and TARC experiment. (orig.)

  15. TRASH TO TREASURE: CONVERTING COLD WAR LEGACY WASTE INTO WEAPONS AGAINST CANCER

    International Nuclear Information System (INIS)

    As part of its commitment to clean up Cold War legacy sites, the U.S. Department of Energy (DOE) has initiated an exciting and unique project to dispose of its inventory of uranium-233 (233U) stored at Oak Ridge National Laboratory (ORNL), and extract isotopes that show great promise in the treatment of deadly cancers. In addition to increasing the supply of potentially useful medical isotopes, the project will rid DOE of a nuclear concern and cut surveillance and security costs. For more than 30 years, DOE's ORNL has stored over 1,200 containers of fissile 233U, originally produced for several defense-related projects, including a pilot study that looked at using 233U as a commercial reactor fuel. This uranium, designated as special nuclear material, requires expensive security, safety, and environmental controls. It has been stored at an ORNL facility, Building 3019A, that dates back to the Manhattan Project. Down-blending the material to a safer form, rather than continuing to store it, will eliminate a $15 million a year financial liability for the DOE and increase the supply of medical isotopes by 5,700 percent. During the down-blending process, thorium-229 (229Th) will be extracted. The thorium will then be used to extract actinium-225 (225Ac), which will ultimately supply its progeny, bismuth-213 (213Bi), for on-going cancer research. The research includes Phase II clinical trials for the treatment of acute myelogenous leukemia at Sloan-Kettering Memorial Cancer Center in New York, as well as other serious cancers of the lungs, pancreas, and kidneys using a technique known as alpha-particle radioimmunotherapy. Alpha-particle radioimmunotherapy is based on the emission of alpha particles by radionuclides. 213Bi is attached to a monoclonal antibody that targets specific cells. The bismuth then delivers a high-powered but short-range radiation dose, effectively killing the cancerous cells but sparing the surrounding tissue. Production of the actinium and

  16. TRASH TO TREASURE: CONVERTING COLD WAR LEGACY WASTE INTO WEAPONS AGAINST CANCER

    Energy Technology Data Exchange (ETDEWEB)

    Nicholas, R.G.; Lacy, N.H.; Butz, T.R.; Brandon, N.E.

    2004-10-06

    As part of its commitment to clean up Cold War legacy sites, the U.S. Department of Energy (DOE) has initiated an exciting and unique project to dispose of its inventory of uranium-233 (233U) stored at Oak Ridge National Laboratory (ORNL), and extract isotopes that show great promise in the treatment of deadly cancers. In addition to increasing the supply of potentially useful medical isotopes, the project will rid DOE of a nuclear concern and cut surveillance and security costs. For more than 30 years, DOE's ORNL has stored over 1,200 containers of fissile 233U, originally produced for several defense-related projects, including a pilot study that looked at using 233U as a commercial reactor fuel. This uranium, designated as special nuclear material, requires expensive security, safety, and environmental controls. It has been stored at an ORNL facility, Building 3019A, that dates back to the Manhattan Project. Down-blending the material to a safer form, rather than continuing to store it, will eliminate a $15 million a year financial liability for the DOE and increase the supply of medical isotopes by 5,700 percent. During the down-blending process, thorium-229 (229Th) will be extracted. The thorium will then be used to extract actinium-225 (225Ac), which will ultimately supply its progeny, bismuth-213 (213Bi), for on-going cancer research. The research includes Phase II clinical trials for the treatment of acute myelogenous leukemia at Sloan-Kettering Memorial Cancer Center in New York, as well as other serious cancers of the lungs, pancreas, and kidneys using a technique known as alpha-particle radioimmunotherapy. Alpha-particle radioimmunotherapy is based on the emission of alpha particles by radionuclides. 213Bi is attached to a monoclonal antibody that targets specific cells. The bismuth then delivers a high-powered but short-range radiation dose, effectively killing the cancerous cells but sparing the surrounding tissue. Production of the actinium and

  17. 49 CFR 23.3 - What do the terms used in this part mean?

    Science.gov (United States)

    2010-10-01

    ..., Puerto Rican, Cuban, Dominican, Central or South American, or other Spanish or Portuguese culture or..., Eskimos, Aleuts, or Native Hawaiians; (iv) “Asian-Pacific Americans,” which includes persons whose origins..., Kirbati, Juvalu, Nauru, Federated States of Micronesia, or Hong Kong; (v) “Subcontinent Asian...

  18. Yeast Interacting Proteins Database: YOL006C, YMR233W [Yeast Interacting Proteins Database

    Lifescience Database Archive (English)

    Full Text Available YOL006C TOP1 Topoisomerase I, nuclear enzyme that relieves torsional strain in DNA ...YOL006C Bait gene name TOP1 Bait description Topoisomerase I, nuclear enzyme that relieves torsional strain

  19. 45 CFR 233.110 - Foster care maintenance and adoption assistance.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 2 2010-10-01 2010-10-01 false Foster care maintenance and adoption assistance... maintenance and adoption assistance. (a) State plan requirements. A State plan under title IV-A of the Social... Security Act, and operates a foster care maintenance and adoption assistance program in conformity...

  20. Yeast Interacting Proteins Database: YER081W, YPL233W [Yeast Interacting Proteins Database

    Lifescience Database Archive (English)

    Full Text Available oins kinetochore subunits contacting DNA to those contacting microtubules; requir...tacting DNA to those contacting microtubules; required for accurate chromosome segr...t of the MIND kinetochore complex (Mtw1p Including Nnf1p-Nsl1p-Dsn1p) which joins kinetochore subunits con

  1. Measuring the Th-229 nuclear isomer transition with U-233 doped crystals

    CERN Document Server

    Stellmer, Simon; Kazakov, Georgy; Sterba, Johannes; Schumm, Thorsten

    2015-01-01

    We propose a simple approach to measure the energy of the few-eV isomeric state in Th-229. To this end, U-229 nuclei are doped into VUV-transparent crystals, where they undergo alpha decay into Th-229, and, with a probability of 2%, populate the isomeric state. These Th-229m nuclei may decay into the nuclear ground state under emission of the sought-after VUV gamma, whose wavelength can be determined with a spectrometer. Based on measurements of the optical transmission of U:CaF2 crystals in the VUV range, we expect a signal at least 2 orders of magnitude larger compared to current schemes using surface-implantation of recoil nuclei. The signal background is dominated by Cherenkov radiation induced by beta decays of the thorium decay chain. We estimate that, even if the isomer undergoes radiative de-excitation with a probability of only 0.1%, the VUV gamma can be detected within a reasonable measurement time.

  2. 45 CFR 233.10 - General provisions regarding coverage and eligibility.

    Science.gov (United States)

    2010-10-01

    ... to participate because of the failure of a local authority to apply such State plan provisions. (2...) Deprived of parental support or care by reason of the death, continued absence from the home, or...

  3. Editorial Revista Contaduría y Administración 233

    OpenAIRE

    López Herrera Francisco

    2011-01-01

    Existen diversos aspectos que resultan ser de importancia para alcanzar los diversos objetivos que los administradores de organizaciones públicas o privadas, lucrativas o no lucrativas, deben cumplir. Evidentemente la satisfacción del cliente o usuario es uno de los aspectos clave. Una de las ideas que ha alcanzado un alto grado de consenso desde hace ya varios años, a juzgar por lo vasto de la literatura dedicada a ese punto, es que en esa satisfacción juega un papel primordial y crítico el ...

  4. 19 CFR 10.233 - Articles eligible for preferential tariff treatment.

    Science.gov (United States)

    2010-04-01

    ... reference to trade between the United States and Mexico will be deemed to refer to trade between the United... not enter into the commerce of any country that is not a CBTPA beneficiary country while en route to... control of the customs authority of the intermediate country; (ii) Did not enter into the commerce of...

  5. 39 CFR 233.8 - Expedited forfeiture proceedings for property seized for administrative forfeiture involving...

    Science.gov (United States)

    2010-07-01

    ... forfeiture involving controlled substances in personal use quantities. (a) Definitions. As used in this... hallucinogen or cannabis-controlled substance will be considered in excess of personal use quantities if...

  6. Public Law 88-233 : 88th Congress S. 2275 [Hawaiian Islands National Wildlife Refuge

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This document is an act made to revise the procedures of conveying certain lands to the state of Hawaii. It designates certain lands on Sand Island as lands that...

  7. 12 CFR 233.6 - Non-exclusive examples of policies and procedures.

    Science.gov (United States)

    2010-01-01

    ...-party processor, or a card issuer, are deemed to be reasonably designed to identify and block or... designated payment system is permitted to design and implement policies and procedures tailored to its..., those due diligence procedures will be deemed to be reasonably designed to identify and block...

  8. Rapid oxygenation of Earths atmosphere 2.33 billion years ago

    OpenAIRE

    Luo, Genming; Ono, Shuhei; Beukes, Nicolas J.; Wang, David T.; Xie, Shucheng; Summons, Roger E.

    2016-01-01

    Molecular oxygen (O[subscript 2]) is, and has been, a primary driver of biological evolution and shapes the contemporary landscape of Earth’s biogeochemical cycles. Although “whiffs” of oxygen have been documented in the Archean atmosphere, substantial O2 did not accumulate irreversibly until the Early Paleoproterozoic, during what has been termed the Great Oxygenation Event (GOE). The timing of the GOE and the rate at which this oxygenation took place have been poorly constrained until now. ...

  9. 45 CFR 233.53 - Support and maintenance assistance (including home energy assistance) in AFDC.

    Science.gov (United States)

    2010-10-01

    ... which are convertible to cash. Private, nonprofit organization means a religious, charitable...) Provide that in joint AFDC/SSI households, support and maintenance assistance furnished to the household... assistance is in cash or in kind; or (iv) A private nonprofit organization, but only if such assistance is...

  10. PROJECT EXPERIENCE REPORT DEMOLITION OF HANFORDS 233-S PLUTONIUM CONCENTRATION FACILITY

    International Nuclear Information System (INIS)

    This report provides a summary of the preparation, operations, innovative work practices, and lessons learned associated with demolition of the 2334 Plutonium Concentration Facility. This project represented the first open-air demolition of a highly-contaminated plutonium facility at the Hanford Site. This project may also represent the first plutonium facility in the US. Department of Energy (DOE) complex to have been demolished without first decontaminating surfaces to near ''free release'' standards. Demolition of plutonium contaminated structures, if not properly managed, can subject cleanup personnel and the environment to significant risk. However, with proper sequencing and innovative use of commercially available equipment, materials, and services, this project demonstrated that a plutonium processing facility can be demolished while avoiding the need to perform extensive decontamination or to construct large enclosures. This project utilized an excavator with concrete shears, diamond circular saws, water misting and fogging equipment, commercially available fixatives and dust suppressants, conventional mobile crane and rigging services, and near real-time modeling of meteorological and radiological conditions. Following a significant amount of preparation, actual demolition of the 2333 Facility began in October 2003 and was completed in late April 2004. The knowledge and experience gained on this project are important to the Hanford Site as additional plutonium processing facilities are scheduled for demolition in the near future. Other sites throughout the DOE Complex may also be faced with similar challenges. Numerous innovations and effective work practices were implemented on this project. Accordingly, a series of ''Lessons Learned and Innovative Practices Fact Sheets'' were developed and are included as an appendix to this report. This collection of fact sheets is not intended to capture every innovative work practice and lesson learned, but rather to describe those that the project believes to be of most benefit to future DOE projects. These fact sheets cover a number of specific topics within the subject areas noted below: (1) Project Management; (2) Organization Structure and Responsibilities; (3) Demolition Approach and Equipment; (4) Planning and Scheduling; (5) Site Preparation and Infrastructure; (6) Radiological Controls; (7)Industrial Safety and Health; and (8) Waste Management

  11. 16 CFR 233.4 - Bargain offers based upon the purchase of other merchandise.

    Science.gov (United States)

    2010-01-01

    ... given a customer on the condition that he purchase a particular article at the price usually offered by... used, care be taken not to mislead the consumer. (b) Where the seller, in making such an offer, increases his regular price of the article required to be bought, or decreases the quantity and quality...

  12. TINGKAT KANDUNGAN UNSUR RADIOAKTIF AIR SUNGAI AYUNG DI DENPASAR BALI

    Directory of Open Access Journals (Sweden)

    Dewa Nyoman Alit Ardana

    2012-11-01

    Full Text Available Ayung river is one of the longest rivers in Bali. The upstream of the river is in regency of Bangli, Badung, Buleleng, Tabananand downstream is located in Padang Galak beach, East Denpasar Sub-regency. As the sample of the study, the water of the river wastaken from the stream entering the city of Denpasar. The sample was taken in five different points and for each point was taken twice. Thefirst was taken at 5 p.m, and the second was at 6 a.m. This study aims at finding out the rate of radioactive content of Ayung river water inthe city of Denpasar.The water sample was analyzed in Radiometry Analysis Group of Radiation Physics and environmental research centre andNuclear Technique Development, Jalan Taman Sari 71 Bandung – 40132. The process of counting was conducted in this place in order toknow the rate of the element activities and then identification of elements contens in the sample. The result of the counting and identifyingwas compered with standard grade of radioactivity in the area.The element of identification result and the amount of activity rate found showed that the element were natural radioactiveelements, the content: 40K (Kalium-40, 234Th (Thorium-234, 233Th (Thorium-233, 228Ac (Actinium-288, 114mIn (Indium-114m. Thehighest activity of radioactive elements in each sample point: in E2 point content element 40K with the activity 2.08 Bq/lt, in point A1 234Thwith the activity 16.34 Bq/lt, in point E1 containts 233Th with activity 598.29 Bq/lt, in point E1 and E2 contain 228Ac with the activity939.63 Bq/lt. The height of activity value of the counting and identifying elements was still under the rate of the highest level.The result of the study showed that radioactive elements 40K had the tendency of increasing radioactivity. The same thinghappened to 233Th at the peak of energi 185.00 keV. The content of its radioactive tends to exist in each point of sample point and theactivity tends to increase. Though the rate of

  13. Study on laser atomic spectroscopy

    International Nuclear Information System (INIS)

    Laser atomic spectroscopic study on actinium element has been performed in many areas of spectroscopy. The study on characteristic of atomic vapor has been proceeded for copper atom and the spatial density distribution of copper vapor is measured. This experimental data has been compared with the theoretically calculated data. In spectroscopic experiment, the first and second excited states for actinium element are identified and the most efficient ionization scheme for actinium element is identified. In addition, the corrosion problem for filament material due to the heating of the actinium element has been studied. (Author)

  14. SU-E-J-233: Effect of Brachytherapy Seed Artifacts in T2 and Proton Density Maps in MR Images

    Energy Technology Data Exchange (ETDEWEB)

    Mashouf, S [Sunnybrook Odette Cancer Centre, Toronto, Ontario (Canada); University of Toronto, Dept of Radiation Oncology, Toronto, Ontario (Canada); Fatemi-Ardekani, A [Sunnybrook Odette Cancer Centre, Toronto, Ontario (Canada); Sunnybrook Research Institute, Toronto, Ontario (Canada); Song, W [Sunnybrook Odette Cancer Centre, Toronto, Ontario (Canada); University of Toronto, Dept of Radiation Oncology, Toronto, Ontario (Canada); Sunnybrook Research Institute, Toronto, Ontario (Canada)

    2015-06-15

    Purpose: This study aims at investigating the influence of brachytherapy seeds on T2 and proton density (PD) maps generated from MR images. Proton density maps can be used to extract water content. Since dose absorbed in tissue surrounding low energy brachytherapy seeds are highly influenced by tissue composition, knowing the water content is a first step towards implementing a heterogeneity correction algorithm using MR images. Methods: An LDR brachytherapy (IsoAid Advantage Pd-103) seed was placed in the middle of an agar-based gel phantom and imaged using a 3T Philips MR scanner with a 168-channel head coil. A multiple echo sequence with TE=20, 40, 60, 80, 100 (ms) with large repetition time (TR=6259ms) was used to extract T2 and PD maps. Results: Seed artifacts were considerably reduced on T2 maps compared to PD maps. The variation of PD around the mean was obtained as −97% to 125% (±1%) while for T2 it was recorded as −71% to 24% (±1%). Conclusion: PD maps which are required for heterogeneity corrections are susceptible to artifacts from seeds. Seed artifacts on T2 maps, however, are significantly reduced due to not being sensitive to B0 field variation.

  15. Measurement of Effective Cross Section of Th-233(n,γ)Th-234 Reaction Using the KUR

    Science.gov (United States)

    Chatani, Hiroshi

    2005-05-01

    Thorium nitrate was irradiated together with Au and Co neutron fluence monitors in the Kyoto University Reactor (KUR). The thorium was chemically purified using the solvent extraction and ion-exchange methods. The γ-rays in the decay of Th-234 were measured using high-purity Ge detectors (HPGes). Thermal neutron fluxes and epithermal indexes, i.e., the relative strength of the epithermal dE/E component, were determined using the Westcott convention. Five effective cross sections were determined for epithermal indexes from 0.01 to 0.04 using three irradiation facilities. The cross section for 2200 m/s neutrons and the resonance integral were deduced to be (1270±50) b and (1680±930) b, respectively, from the results of the five effective cross sections.

  16. Laparoskopi ved formodet appendicitis acuta. Erfaringer med de 233 første laparoskopier på en universitetsafdeling

    DEFF Research Database (Denmark)

    Pedersen, A G; Petersen, O B; Wara, P;

    1996-01-01

    patients (0.9% and 1.7%), respectively. There was only one complication (0.4%) directly related to the laparoscopic procedure, namely a coecal leak. In conclusion, in a teaching hospital, laparoscopic appendicectomy can be safely offered to patients where surgery is indicated due to suspicion...

  17. Analysis of thorium/U-233 lattices and cores in a breeder/burner heavy water reactor

    International Nuclear Information System (INIS)

    Due to the inevitable dwindling of uranium resources, advanced fuel cycles in the current generation of reactors stand to be of great benefit in the future. Heavy water moderated reactors have much potential to make use of thorium, a currently unexploited resource. Core fuelling configurations of a Heavy Water Reactor based on the self-sufficient thorium fuel cycle were simulated using the DRAGON and DONJON reactor physics codes. Three heterogeneously fuelled reactors and one homogeneously fuelled reactor were studied. (author)

  18. 16 CFR 233.3 - Advertising retail prices which have been established or suggested by manufacturers (or other...

    Science.gov (United States)

    2010-01-01

    ... number of sales of the article in question are made, the advertisement of a reduction may mislead the... them throughout the United States, advertises his pen in a national magazine as having a...

  19. 78 FR 21969 - Gulf of Mexico (GOM), Outer Continental Shelf (OCS), Western Planning Area (WPA) Lease Sale 233...

    Science.gov (United States)

    2013-04-12

    ... MMAA104000 AGENCY: Bureau of Ocean Energy Management (BOEM), Interior. ACTION: Notice of Availability (NOA) of the Final Supplemental Environmental Impact Statement (EIS). Authority: This NOA is...

  20. Aquastress D2.3.3 - Integrated water balance models for water stress adapted to test sites

    OpenAIRE

    S. Schmidt; Rosso, P.; S. Loubier; Preziosi, E.; Tarnacki, K.; Van den Wyngaert, I.

    2008-01-01

    This report is based on the report Milestone 2.3-1 of the Aquastress project (Schmidt et al, 2005), which presented an inventory of examples of water balance models and gave a list of criteria to characterise hydrological models, and on the report Deliverable 2.3-1 of the Aquastress project (Schmidt et al, 2006), which describes the concept of the water balance model and the structure of the water stress assessment in the domestic, industrial, agricultural and (semi)natural ecosystem sectors....

  1. Picosecond time evolution of photoexcitations at 2.33 eV in α-sexithyenil thin films

    Science.gov (United States)

    Lanzani, G.; Danieli, R.; Muccini, M.; Taliani, C.

    1993-11-01

    Picosecond time dynamics of the isotropic as well as the anisotropic transient absorption saturation have been measured in an α-sexithyenil (T6) thin film at room temperature by photoinduced absorption and resonant Kerr-gate experiments. Strongly damped photoacoustical oscillations have been detected superimposed on the photobleaching signal, providing a way to evaluate the sound speed in T6 films along the normal to the substrate; VS~=16 Å/ps. A stretched exponential function has been used to describe the time recovery of the total photoexcited population yielding a time constant τ=3.5 ns with an exponent α=0.5. This is indicative of dispersive diffusion towards recombination centers via intermolecular hopping; the Kerr-gate transmission decay provides an estimate of the photoexcitation diffusion constant, namely, D=6×10-3 cm2/s.

  2. 2.33 长期卧床患者上消化道运动功能分析

    Institute of Scientific and Technical Information of China (English)

    李延青; 韩炜; 卢雪峰; 李君曼; 李学会

    2001-01-01

    目的系统观察我院各科长期卧床患者上消化道运动及分泌功能的变化及转归,以更好的指导临床治疗.方法 1.观察组:长期卧床患者(卧床时间≥30天,且平卧时间≤20小时/日 )19例,均为我院ICU、神经内科、保健科、心内科、骨外科术后病人.其中男性12例、女性 7例,年龄17~67岁,平均年龄44.5岁.入院时均无消化系统症状和手术史,并排除糖尿病和甲亢等内分泌疾患.2.方法:采用Digitrapper MK Ⅲ 24h pH监测仪、BILITEC 2000 24 h胆汁测定仪、Digitrapper 24h胃电图仪(均为瑞典CTD-Synecties公司产品)于入院时分别测定患者上消化道运动和分泌状态.结果入院时:24h胃电图示主频2.99±0.41,其中正常节律占68.49%、胃动过速占10.83%、胃动过缓占20.67%.24h pH监测示24h pH<4的总次数(GERN)42±8. 91、pH<4的时间占监测的时间百分比(GERT%)1.8±0.76%、DeMeester评分9.8±4.23. 24h胆汁返流测定示返流(吸光值≥0.14)次数16.5±10.6、返流>5min次数4.2±3.2、返流总时间%6.9±4.5%.出院时:24h胃电图示主频1.93±0.38,其中正常节律占54.2 3%、胃运过速占4.46%、胃动过缓占41.30%.24h pH监测示GERN 78±13.22、GERT 4.8 1.56、dEmEESTERYGUHWV 18.2±4.22.24h胆汁返流测定示返流次数49.7±35.1、返流>5min次数7.1±4.2、返流总时间%22.9±15.6%.入院时与出院时比较,P<0.05 .结论长期卧床患者是住院病人中的特殊群体.本研究提示长期卧床后患者胃电节律变慢、酸和胆汁的返流量增多,而使病人渐感腹胀、返酸、口苦、纳差.对不能久坐的患者,我们发现半卧位(床头角度≥30度)可很好地防止返流症状的发生.

  3. Genetic mapping of a susceptibility locus for disc herniation and spastic paraplegia on 6q23.3-q24.1

    OpenAIRE

    Zortea, M.; Vettori, A; Trevisan, C; Bellini, S.; Vazza, G.; Armani, M; Simonati, A; Mostacciuolo, M

    2002-01-01

    It has been suggested that a genetic factor(s) or a familial predisposition may contribute to the clinical manifestations of disc herniation; moreover, no genetic linkage between spinal disc herniation and spastic paraplegia has ever been described.

  4. Loss of heterozygosity on 10q23.3 and mutation of tumor suppressor gene PTEN in gastric cancer and precancerous lesions

    Institute of Scientific and Technical Information of China (English)

    Yi-Ling Li; Zhong Tian; Dong-Ying Wu; Bao-Yu Fu; Yan Xin

    2005-01-01

    AIM: To investigate the loss of heterozygosity (LOH) and mutation of tumor suppressor gene PTEN in gastric cancer and precancerous lesions.METHODS: Thirty cases of normal gastric mucosa, advanced and early stage gastric cancer, intestinal metaplasia, atrophic gastritis, and atypical hyperplasia were analyzed for PTEN LOH and mutations within the entire coding region of PTEN gene by PCR-SSCP denaturing PAGE gel electrophoresis,and PTEN mutation was detected by PCR-SSCP sequencing followed by silver staining.RESULTS: LOH rate found in respectively atrophic gastritis was 10% (3/30), intestinal metaplasia 10% (3/30), atypical hyperpiasia 13.3% (4/30), early stage gastric cancer 20%(6/30), and advanced stage gastric cancer 33.3% (9/30),None of the precancerous lesions and early stage gastric cancer showed PTEN mutations, but 10% (3/30) of the advanced stage gastric cancers, which were all positive for LOH, showed PTEN mutation.CONCLUSION: LOH of PTEN gene appears in precancerous lesions, and PTEN mutations are restricted to advanced gastric cancer, LOH and mutation of PTEN gene are closely related to the infiltration and metastasis of gastric cancer.

  5. 8 CFR 233.6 - Aliens entering Guam or the Commonwealth of the Northern Mariana Islands pursuant to Title VII of...

    Science.gov (United States)

    2010-01-01

    ... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Aliens entering Guam or the Commonwealth of the Northern Mariana Islands pursuant to Title VII of Public Law 110-229, âConsolidated Natural... of the Northern Mariana Islands pursuant to Title VII of Public Law 110-229, “Consolidated...

  6. Crystal structure of [1,1':3',1''-ter-phenyl]-2',3,3''-tri-carb-oxy-lic acid.

    Science.gov (United States)

    Decato, Daniel A; Berryman, Orion B

    2015-09-01

    The asymmetric unit of the title compound, C21H14O6, com-prises two symmetrically independent mol-ecules that form a locally centrosymmetric hydrogen-bonded dimer, with the planes of the corresponding carb-oxy-lic acid groups rotated by 15.8 (1) and 17.5 (1)° relative to those of the adjacent benzene rings. The crystal as a whole, however, exhibits a noncentrosymmetric packing, described by the polar space group Pca21. The dimers form layers along the ab plane, being inter-connected by hydrogen bonds involving the remaining carb-oxy-lic acid groups. The plane of the central carb-oxy-lic acid group forms dihedral angles of 62.5 (1) and 63.0 (1)° with those of the adjacent benzene rings and functions as a hydrogen-bond donor and acceptor. As a donor, it inter-connects adjacent layers, while as an acceptor it stabilizes the packing within the layers. The 'distal' carb-oxy-lic acid groups are nearly coplanar with the planes of the adjacent benzene rings, forming dihedral angles of 1.8 (1) and 7.1 (1)°. These groups also form intra- and inter-layer hydrogen bonds, but with 'reversed' functionality, as compared with the central carb-oxy-lic acid groups. PMID:26396894

  7. catena-Poly[[[aqua[3-(3-hydroxyphenylprop-2-enoato]samarium(III]-bis[μ2-3-(3-hydroxyphenylprop-2-enoato

    Directory of Open Access Journals (Sweden)

    Yi-Hang Wen

    2012-05-01

    Full Text Available The title SmIII compound, {[Sm(C9H7O33(H2O]·H2O}n, was obtained under hydrothermal conditions. Its structure is isotypic with the analogous Eu complex. The latter was reported incorrectly in space group P1 by Yan et al. [J. Mol. Struct. (2008, 891, 298–304]. This was corrected by Marsh [Acta Cryst. B65, 782–783] to P-1. The SmIII ion is nine-coordinated by O atoms from one coordinating water molecule and the remaining ones from the 3-(3-hydroxyphenylprop-2-enoatate anions (one bidentate, two bidentate and bridging, two monodentate bridging, leading to a distorted tricapped trigonal–prismatic coordination polyhedron surrounded by solvent water molecules. In the crystal, extensive intermolecular O—H...O hydrogen-bonding interactions and π–π interactions [centroid–centroid separation = 3.9393 (1 Å] lead to the formation of a three-dimensional supramolecular network.

  8. Dynamic analysis of muscular lymphokinetic activities in the treatment of lymphedema of the upper limbs - doi:10.5020/18061230.2007.p233

    Directory of Open Access Journals (Sweden)

    Maria de Fátima Guerreiro Godoy

    2012-01-01

    Full Text Available The aim of the present study was to evaluate the resting and working pressures associated to a restrain mechanism, in patients suffering from lymphedema of the upper limbs, postbreast cancer treatment, whilst performing occupational and day-to-day self-care activities. Six female patients under treatment of lymphedema due to surgical, radiotherapeutic and chemotherapeutic treatment of breast cancer, in the age group between 32 and 76 years (mean 54 years old, ± 31.11 were selected. A compression sleeve of “gorgurão” (cotton-polyester material was applied as a restrain mechanism. The occupational and daily personal care activities evaluated were those common to all participants. These activities included washingup, cooking in a small pan, sweeping the floor using the affected arm, brushing the teeth, brushing the hair, washing small items of clothes, ironing clothes and making the bed. For statistical analysis, mean and standard deviation between resting pressures and minimum and maximum working pressures were determined. The two-tailed student t-test and variance analysis were used for repeated measurements. The Bonferroni limit was used in the analysis of the variables to calculate the alpha error, with a value of 5%, considered statistically significant. All of the analyzed activities associated to the “gorgurão” compression sleeve generated both resting and working pressures (p <0.005. In conclusion, the occupational daily life tasks used in the present study generate resting and working pressures and can be used as a form of treatment of the lymphedema.

  9. The synchronization of palaeoclimatic events in the North Atlantic region during Greenland Stadial 3 (ca 27.5 to 23.3 kyr b2k)

    DEFF Research Database (Denmark)

    Hibbert, F.D.; Peters, C.; Rasmussen, Sune Olander;

    2012-01-01

    Two high resolution marine sediment cores located 83 km apart in the NE Atlantic have been studied: MD95-2006 (Barra Fan; 57°01.82 N, 10°03.48 W; 2120 m water depth) and MD04-2822 (Rockall Trough; 56°50.54 N, 11°22.96 W; 2344 m water depth). The records are anchored to the NGRIP ice core stratigr......Two high resolution marine sediment cores located 83 km apart in the NE Atlantic have been studied: MD95-2006 (Barra Fan; 57°01.82 N, 10°03.48 W; 2120 m water depth) and MD04-2822 (Rockall Trough; 56°50.54 N, 11°22.96 W; 2344 m water depth). The records are anchored to the NGRIP ice core...

  10. Guilhem de Saint Gregori, "Ben grans avolesa intra" (BdT 233.2; Bartolomeo Zorzi, "En tal dezir mos cors intra" (BdT 74.4

    Directory of Open Access Journals (Sweden)

    Alessandro Bampa

    2014-02-01

    Full Text Available This paper provides a commentary and translation of two contrafacta of Arnaut Daniel’s sestina: Guilhem de Saint Gregori’s "Ben gran avolesa intra" and Bartolomeo Zorzi’s "En tal dezir mos cors intra". For the first song, I will highlight the new contexts and meanings given to Arnaut’s images (which are taken from his sestina and other poems within Guilhem’s invective against Aimers II of Poitiers, in order to evaluate its literary qualities and innovations. Through lexical analysis, this paper will reveal the strong connection between Zorzi’s and Guilhem’s songs. In particular, the paper analyses specifically their common theme of Hell, suggesting Bartolomeo’s text is most likely an answer to Arnaut’s sestina, which clearly expresses a desire of sensual pleasure. The study pays particular attention to the relation between sexual love and the matter of eternal damnation: Zorzi attacks Arnaut’s ferm voler, advancing his argument by evoking Chrétien de Troyes’ "Perceval" (references to which are spread throughout the text, and not only in l. 18 and through his constant stress on the duties towards one’s family.

  11. Influence of Sample Preparation on Assay of Functional Phenolic Phytochemicals (American Chemical Society, 233rd National Meeting & Exposition, March 25-29, 2007, Chicago, IL)

    Science.gov (United States)

    Phenolics are one of the most diverse groups of phytochemicals that are ubiquitously distributed throughout the plant kingdom. Phenolic phytochemicals are known to exhibit a wide range of health protective effects. Approximately 8000 different phenolics compounds have been isolated from natural re...

  12. Radiochemical method for the simultaneous determination of 233U, 236U, 237Np, 236Pu, 238Pu, and 239Pu in biological materials

    International Nuclear Information System (INIS)

    A radiochemical method has been developed for the determination of multiple isotopes of uranium, neptunium, and plutonium in biological materials. The elements are separated from the other sample constituents and from each other by anion exchange in halide media. Their recoveries are monitored by isotopic diluents. The amounts of the analyte and diluent isotopes of each element are measured alpha spectrometrically. The interelemental separation factors are generally greater than 102, and the recovery of each element ranges from 60% to 90%. 4 references, 1 table

  13. 45 CFR 233.145 - Expiration of medical assistance programs under titles I, IV-A, X, XIV and XVI of the Social...

    Science.gov (United States)

    2010-10-01

    ... any period after December 31, 1969. However, these provisions do not affect the availability of... beyond room and board because of the physical or mental condition (or both) of its inpatients; (ii) An... is receiving care or service beyond room and board because of his physical or mental condition...

  14. 10 CFR Appendix E to Part 20 - Nationally Tracked Source Thresholds

    Science.gov (United States)

    2010-01-01

    ... Category 1(TBq) Category 1(Ci) Category 2(TBq) Category 2(Ci) Actinium-227 20 540 0.2 5.4 Americium-241 60... 2 54 Strontium-90 1,000 27,000 10 270 Thorium-228 20 540 0.2 5.4 Thorium-229 20 540 0.2 5.4...

  15. I. The metabolic properties of plutonium and allied materials

    Energy Technology Data Exchange (ETDEWEB)

    Hamilton, J.G.

    1948-05-24

    This report on the metabolic properties of plutonium and related radioactive materials presents experimental information in the following areas: radioautographic studies; tracer studies (with tables of accumulation in tissues) of actinium, radio-zirconium, technetium, radio-rubidium, radio-germanium, beryllium, and cadmium; decontamination and bone metabolism studies; and radio-chemical isolation.

  16. 10 CFR Appendix B to Part 20 - Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for...

    Science.gov (United States)

    2010-01-01

    .... Actinium Ac 89 Aluminum Al 13 Americium Am 95 Antimony Sb 51 Argon Ar 18 Arsenic As 33 Astatine At 85... Curium Cm 96 Dysprosium Dy 66 Einsteinium Es 99 Erbium Er 68 Europium Eu 63 Fermium Fm 100 Fluorine F...

  17. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: fabrication of high-temperature gas-cooled reactor fuel containing uranium-233 and thorium

    International Nuclear Information System (INIS)

    A cost/benefit study was made to determine the cost and effectiveness of various radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from model High-Temperature Gas-Cooled (HTGR) fuel fabrication plants and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist in defining the term ''as low as reasonably achievable'' as it applies to these nuclear facilities. The base cases of the two model plants, a fresh fuel fabrication plant and a refabrication plant, are representative of current proposed commercial designs or are based on technology that is being developed to fabricate uranium, thorium, and graphite into fuel elements. The annual capacities of the fresh fuel plant and the refabrication plant are 450 and 245 metric tons of heavy metal (where heavy metal is uranium plus thorium), as charged to about fifty 1000-MW(e) HTGRs. Additional radwaste treatment systems are added to the base case plants in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The capital and annual costs for the added waste treatment operations and the corresponding reductions in dose commitments are calculated for each case. In the final analysis, the cost/benefit of each case, calculated as additional cost of radwaste system divided by the reduction in dose commitment, is tabulated or the dose commitment is plotted with cost as the variable. The status of each of the radwaste treatment methods is discussed. 48 figures, 74 tables

  18. E. La Stella, Dizionario storico di deonomastica. Vocaboli derivati da nomi propri, con le corrispondenti forme francesi, inglesi, spagnole e tedesche, Firenze, Leo S. Olschki Editore, 1984, pp. 233, s.i.p.

    Directory of Open Access Journals (Sweden)

    Renato Gendre

    2015-10-01

    Full Text Available La pietra miliare nello studio dei vocaboli romanzi di derivazione onomastica - con particolare riguardo all'Italia e alla Francia - resta Dal nome proprio al nome comune di Bruno Migliorini. E' chiaro però, che l'esigenza di un aggiornamento di questo lavoro, pur bello e per tanti aspetti insuperabile, era sentita dagli studiosi dopo oltre mezzo secolo dalla pubblicazione, nonostante il Supplementoaggiunto dall 'Autore stesso nella 'ristampa fotostatica' del volume.

  19. JUAN M. LOPE BLANCH. El habla de Diego de Ordaz. Contribución a la historia del español americano. México, UNAM. 1985. 233 p.

    Directory of Open Access Journals (Sweden)

    J. L. R.

    1988-06-01

    Full Text Available Este libro reúne los trabajos publicados por Lope Blanch en revistas especializadas y homenajes académicos acerca del idiolecto de este importante americano nacido en tierras leonesas hacia 1480, colonizador de las Antillas, expedicionario a Tierra Firme y a Cuba, conquistador de México y explorador del Orinoco. La base documental está constituida por siete cartas autógrafasque L.B. publica al final del libro en una cuidadosa transcripción que corrige defectos de una edición anterior.

  20. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: fabrication of high-temperature gas-cooled reactor fuel containing uranium-233 and thorium

    Energy Technology Data Exchange (ETDEWEB)

    Roddy, J.W.; Blanco, R.E.; Hill, G.S.; Moore, R.E.; Seagren, R.D.; Witherspoon, J.P.

    1976-06-01

    A cost/benefit study was made to determine the cost and effectiveness of various radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from model High-Temperature Gas-Cooled (HTGR) fuel fabrication plants and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist in defining the term ''as low as reasonably achievable'' as it applies to these nuclear facilities. The base cases of the two model plants, a fresh fuel fabrication plant and a refabrication plant, are representative of current proposed commercial designs or are based on technology that is being developed to fabricate uranium, thorium, and graphite into fuel elements. The annual capacities of the fresh fuel plant and the refabrication plant are 450 and 245 metric tons of heavy metal (where heavy metal is uranium plus thorium), as charged to about fifty 1000-MW(e) HTGRs. Additional radwaste treatment systems are added to the base case plants in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The capital and annual costs for the added waste treatment operations and the corresponding reductions in dose commitments are calculated for each case. In the final analysis, the cost/benefit of each case, calculated as additional cost of radwaste system divided by the reduction in dose commitment, is tabulated or the dose commitment is plotted with cost as the variable. The status of each of the radwaste treatment methods is discussed. 48 figures, 74 tables.

  1. Complex three-way translocation involving MLL, ELL, RREB1, and CMAHP genes in an infant with acute myeloid leukemia and t(6;19;11)(p22.2;p13.1;q23.3)

    DEFF Research Database (Denmark)

    Tuborgh, A; Meyer, C; Marschalek, R;

    2013-01-01

    sequencing to characterize the genomic complement in the leukemic cells from aspirated bone marrow cells at AML diagnosis. Karyotyping showed 47,XY,t(6;19;11)(p22;p13;q23),+der(6)t(6;11)(p22;q23)[17]/48,sl,+8[3]/48,sl,+8,der(12)t(1;12)(q11;p13)[3]/ 48,sdl,der(Y)t(Y;1)(q12;q11),+8[7] conferring MLL-ELL fusion...

  2. Health hazard evaluation report No. HHE-80-233-793, Davis Bessie Nuclear Power Station, Toledo Edison Company, United Engineers and Contractors Company (UE and C), Oak Harbor, Ohio

    Energy Technology Data Exchange (ETDEWEB)

    Cone, J.; Hartle, R.

    1981-01-01

    Personal air samples were analyzed and employees were given medical evaluations at Davis Bessie Nuclear Power Station (SIC-4911) in Oak Harbor, Ohio. Requests for evaluation were made by a union representative of the United Engineers and Contractors and a union representative of employees of Toledo Edison Company, working on site at the power station, to evaluate employee skin and scalp problems due to exposure to ceramic wood fibers. Preliminary surveys were conducted on September 24 and 25, 1980 and a follow-up survey was performed on October 16, 1980. Environmental evaluation consisted of gravimetric analyses of personal air samples for airborne ceramic wool fibers. A total of 400 production and maintenance workers and varying numbers of construction workers were exposed to the fibers during installation of insulation which was completed at the time of the survey. The three personal air samples showed no accumulation of particulates and fibers detected were nonrespirable. Medical evaluations were conducted in 52 workers and scalp scrapings were obtained from 43 workers. Thirty seven workers had histories suggestive of irritant dermatitis of the scalp; 24 workers had physical findings consistent with the diagnosis. Of the 43 scalp samples, 18 were contaminated with organisms of the gut, perineum, skin or respiratory tract. Dermatitis was directly related to the history of dust exposure. The authors conclude that a potential health hazard exists for employees from exposure to ceramic wool fiber. Recommendations include provision of handwashing facilities and protective clothing for employees, and installation of an impermeable covering for the ceramic wool fiber.

  3. 47 CFR 15.233 - Operation within the bands 43.71-44.49 MHz, 46.60-46.98 MHz, 48.75-49.51 MHz and 49.66-50.0 MHz.

    Science.gov (United States)

    2010-10-01

    ...) An intentional radiator used as part of a cordless telephone system shall operate centered on one or... to other nearby units or to radio noise resulting in telephone calls being dialed through this...

  4. (3aRS,7aSR-7a-Methoxy-2-oxo-2,3,3a,4,5,6,7,7a-octahydro-1-benzofuran-4,4-dicarbonitrile

    Directory of Open Access Journals (Sweden)

    María González

    2012-12-01

    Full Text Available The racemic title compound, C11H12N2O3, contains a [4.3.0]bicyclic unit in which the shared C—C bond adopts a cis configuration. The five- and six-membered rings are in twisted envelope (with the bridgehead C atom bearing the methoxy substituent as the flap and distorted chair conformations, respectively. In the crystal, the molecules are linked via weak C—H...O iteractions, forming ladder-like chains along [010].

  5. (S-4-[(3aR,4S,7aR-4-Methoxy-6-methyl-3-methylene-2-oxo-2,3,3a,4,7,7a-hexahydrobenzofuran-5-yl]pentyl Acetate

    Directory of Open Access Journals (Sweden)

    Xin Guo

    2016-03-01

    Full Text Available A new etherified 1-O-acetylbritannilactone (ABL analogue 2 was semi-synthesized by a mild etherification reaction. The structure of the newly synthesized analogue was identified by 1H-NMR, 13C-NMR and HR-ESI-MS analysis. 2 exhibited similar cytotoxicity against HCT116, SGC-7901 and HeLa human cancer cell lines with ABL.

  6. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: reprocessing of high-temperature gas-cooled reactor fuel containing U-233 and thorium

    Energy Technology Data Exchange (ETDEWEB)

    Davis, W. Jr.; Blanco, R.E.; Finney, B.C.; Hill, G.S.; Moore, R.E.; Witherspoon, J.P.

    1976-05-01

    A cost/benefit study was made to determine the cost and effectiveness of various radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from a model high-temperature gas-cooled reactor (HTGR) fuel reprocessing plant and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist the U. S. Nuclear Regulatory Commission in defining the term as low as reasonably achievable as it applies to this nuclear facility. The base case is representative of conceptual, developing technology of head-end graphite-burning operations and of extensions of solvent-extraction technology of current designs for light-water-reactor (LWR) fuel reprocessing plants. The model plant has an annual capacity of 450 metric tons of heavy metal (MTHM, where heavy metal is uranium plus thorium), as charged to about fifty 1000-MW(e) HTGRs. Additional radwaste treatment systems are added to the base-case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The capital and annual costs for the added waste treatment operations and the corresponding reductions in dose commitments are calculated for each case. In the final analysis, the cost/benefit of each case, calculated as additional cost of radwaste system divided by the reduction in dose commitment, is tabulated or the dose commitment is plotted with cost as the variable. The status of each of the radwaste treatment methods used in the case studies is discussed.

  7. Investigation for determining the retention properties of rock over the ASSE II mine for dissolved radionuclides

    International Nuclear Information System (INIS)

    For a model consideration of groundwater movement and the associated transport of dissolved substance in deep groundwater, the retention properties of the ASSE II mine for radionuclides dissolved in water were determined. A series of properties of rocks were examined and described for this purpose. Apart from the chemical, mineralogical and petrophysical characteristics of the rocks, the retention was determined by 3 different methods and stated in the form of distribution coefficients for specific elements. A comparison of the results of vibration and diffusion experiments gave good agreement, while the results in through column experiments only reached the same order of magnitude after an expensive determination with the aid of a place concentration distribution. The distribution coefficients for the elements carbon, selenium, strontium, technetium, iodine, caesium, lead, radium, actinium, proto-actinium, uranium, neptunium, plutonium, americium and curium are listed and collected for model rock packages. (orig./HP)

  8. LASL experience in decontamination of the environment

    International Nuclear Information System (INIS)

    This discussion represents one part of a major effort in soil decontamination at the Los Alamos site. A contaminated industrial waste line in the Los Alamos townsite was removed, and a plutonium incineration facility, and a filter building contaminated with actinium-227 were dismantled. The former plutonium handling facility has been decontaminated, and canyons and an old firing site contaminated with strontium-90 have been surveyed

  9. Sorption studies of radioelements on geological materials

    OpenAIRE

    Berry, J. A; 油井 三和; 北村 暁

    2007-01-01

    Batch sorption experiments have been carried out to study the sorption of uranium, technetium, curium, neptunium, actinium, protactinium, polonium, americium and plutonium onto bentonite, granodiorite and tuff. Mathematical modelling using the HARPHRQ program and the HATCHES database was carried out to predict the speciation of uranium and technetium in the equilibrated seawater, and neptunium, americium and plutonium in the rock equilibrated water. Review of the literature for thermodynamic ...

  10. 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

    Energy Technology Data Exchange (ETDEWEB)

    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.)

  11. The discoveries of uranium 237 and symmetric fission — From the archival papers of Nishina and Kimura

    OpenAIRE

    IKEDA, Nagao

    2011-01-01

    Shortly before the Second World War time, Nishina reported on a series of prominent nuclear physical and radiochemical studies in collaboration with Kimura. They artificially produced 231Th, a member of the natural actinium series of nuclides, by bombarding thorium with fast neutrons. This resulted in the discovery of 237U, a new isotope of uranium, by bombarding uranium with fast neutrons, and confirmed that 237U disintegrates into element 93 with a mass number of 237. They also identified t...

  12. System for recovery of daughter isotopes from a source material

    Science.gov (United States)

    Tranter, Troy J [Idaho Falls, ID; Todd, Terry A [Aberdeen, ID; Lewis, Leroy C [Idaho Falls, ID; Henscheid, Joseph P [Idaho Falls, ID

    2009-08-04

    A method of separating isotopes from a mixture containing at least two isotopes in a solution is disclosed. A first isotope is precipitated and is collected from the solution. A daughter isotope is generated and collected from the first isotope. The invention includes a method of producing an actinium-225/bismuth-213 product from a material containing thorium-229 and thorium-232. A solution is formed containing nitric acid and the material containing thorium-229 and thorium-232, and iodate is added to form a thorium iodate precipitate. A supernatant is separated from the thorium iodate precipitate and a second volume of nitric acid is added to the thorium iodate precipitate. The thorium iodate precipitate is stored and a decay product comprising actinium-225 and bismuth-213 is generated in the second volume of nitric acid, which is then separated from the thorium iodate precipitate, filtered, and treated using at least one chromatographic procedure. A system for producing an actinium-225/bismuth-213 product is also disclosed.

  13. GETDB: 113397 [GETDB

    Lifescience Database Archive (English)

    Full Text Available titute of Genetics. FM7c Link to clone table - 1 233 Link to cluster table 233 1 Request - interesting epi s...lusters 1 Stock Request Request - Embryonic Expression interesting epi stripes (S

  14. Gclust Server: 167302 [Gclust Server

    Lifescience Database Archive (English)

    Full Text Available 167302 Bsu_BSU37430=albG Cluster Sequences - 233 antilisterial bacteriocin (subtilo...lbG Link to cluster sequences Cluster Sequences Link to related sequences - Sequence length 233 Representative annotation antilisteri

  15. Canadian Healthcare Practitioners’ Access to Evidence Based Information Is Inequitable. A Review of: Chatterley, T., Storie, D., Chambers, T., Buckingham, J., Shiri, A., & Dorgan, M. (2012. Health information support provided by professional associations in Canada. Health Information & Libraries Journal, 29(3, 233-241.

    Directory of Open Access Journals (Sweden)

    Maria Melssen

    2013-06-01

    Full Text Available Objective – To determine what services and resources are available to health professionals through national Canadian and Alberta based health professional associations and licensing colleges and if those resources and services are being used. Also, to assess the associations’ perceptions of what resources and services Canadian health professionals actually need and if those needs are being met, membership satisfaction with the resources and services provided, and challenges the associations have with providing resources and services.Design – Structured telephone interview.Setting – Health professional associations and licensing colleges in Canada.Subjects – 23 health professional associations: 9 Alberta-based associations and 14 national-level professional associations and licensing colleges.Methods – A librarian, communications officer, or another individual in a comparable position at each association was invited via email to participate in the study. Individuals willing to participate in the interview were emailed the interview questions in advance. Telephone interviews were conducted in July and August of 2009. For those who did not respond to the email request or who did not wish to participate in the interviews, information was collected from the association’s website.Main Results – Of the 23 contacted associations 12 agreed to be interviewed: less than 50% response rate. Data was collected from websites of seven associations that either declined to be interviewed or did not respond to the authors’ email request. Data were unavailable for four associations due to data being in members only sections of the websites. Data were analyzed both qualitatively and quantitatively.Resources and services provided by the associations and licensing colleges range from none to reference services provided by a librarian and access to licensed databases.None of the three licensing colleges or the two provincial associations interviewed maintains usage statistics or surveys their members. Nor do they grant access to licensed databases or offer information services, such as having a librarian or other information professional available to answer reference questions or to perform mediated literature searches. The two provincial associations and the three licensing colleges interviewed do supply information pertinent to health professionals, for example insurance information and funding.Seven national associations were interviewed: two permit access to databases developed by that association and three grant access to licensed databases such as Medline. All seven national associations provide access to journals (four of the seven only provide access to their own association’s journal and five offer information services. Four maintain usage statistics and five survey their members.Of the seven associations not interviewed, none grant access to licensed databases and one permits access to databases developed by that association. Five provide access to their own association’s journal and one provides book loans. Only one offers information services. Cost and the priority to provide resources to staff over members are barriers when trying to provide association members’ services and resources.Conclusion – Health professionals’ access to health information varies depending on the professional’s area of specialization, location in Canada, and particular association memberships. There is no consistency as to what health information is available to all health professionals in Canada, specifically Alberta. The majority of the associations do not provide resources and services, nor do they survey members to assess their usage, desires, needs, or satisfaction with resources and services. Usage rates are low for the associations that do track resource and service usage.A resource list of freely available online health information should be generated to mitigate existing disparities without accruing additional cost factors. Also, a partnership between hospital and academic libraries with various associations is needed to promote the usage of licensed and freely available resources accessible at institutions.This study has several limitations. The low response rate and excluding associations and licensing colleges in other provinces make this an incomplete assessment of all associations which provide resources and services to health professionals in Canada, specifically Alberta. To compensate for this deficit, the authors had collected information from seven associations’ websites; however, because much of the needed information was within members-only pages, some data may be missing. Due to the study’s limitations, further research is needed to better assess health professionals’ information needs and barriers to their use of available resources and services.

  16. Methyl 5-ferrocenyl-5a-hydroxy-1-methyl-10-oxo-2,3,3a,4,5a,10-hexahydro-1H-indeno[1,2:2′,3′]furo[3′,4′-b]pyrrole-3a-carboxylate

    Directory of Open Access Journals (Sweden)

    E. Theboral Sugi Kamala

    2009-06-01

    Full Text Available In the title compound, [Fe(C5H5(C21H20NO5], the pyrrolidine and cyclopentanone rings exhibit a twist conformation. The pyrrolidine ring is almost perpendicular to the cyclopentanone ring, making a dihedral angle of 81.91 (6°. The molecular conformation is stabilized by an intramolecular O—H...N hydrogen bond and C—H...O interactions. The crystal structure is stabilized by intermolecular C—H...O interactions.

  17. International Electronic Journal of Elementary Educ ation, 2013, 5(3), 233-248. ISSN:1307 9298 Copyright © IEJEE www.iejee.com Relationship among Students’ Attitudes, Intentions and Behaviors towards the Inclusion of Peers with Disabilities, in Mainstream Physical Education Classes

    OpenAIRE

    Evangelos BEBETSOS; Derri , Vassiliki; Stratos ZAFEIRIADIS; Pavlos KYRGIRIDIS

    2013-01-01

    Students’ attitudes, intentions and behaviours towards their peers with disabilities are important to their mutual co existence and development. The aim of this study was to investigate a) whetherstudents’ attitudes and intentions towards their schoolmates with disabilities are related to their general and modified behavior in mainstream physical education classes, and b) if the former variables could serve as predictors of the latter. The participants, 172 children without disabilities(Mage=...

  18. meso-4,4′-Dimethoxy-2,2′-{[(3aR,7aS-2,3,3a,4,5,6,7,7a-octahydro-1H-benzimidazole-1,3-diyl]bis(methylene}diphenol

    Directory of Open Access Journals (Sweden)

    Augusto Rivera

    2013-07-01

    Full Text Available The title compound, C23H30N2O4, a di-Mannich base derived from 4-methoxyphenol and cis-1,2-diaminecyclohexane, has a perhydrobenzimidazolidine nucleus, in which the cyclohexane ring adopts a chair conformation and the heterocyclic ring has a half-chair conformation with a C—N—C—C torsion angles of −48.14 (15 and −14.57 (16°. The mean plane of the heterocycle makes dihedral angles of 86.29 (6 and 78.92 (6° with the pendant benzene rings. The molecular structure of the title compound shows the presence of two interactions between the N atoms of the imidazolidine ring and the hydroxyl groups through intramolecular O—H...N hydrogen bonds with graph-set motif S(6. The unobserved lone pairs of the N atoms are presumed to be disposed in a syn conformation, being only the second example of an exception to the typical `rabbit-ears' effect in 1,2-diamines.

  19. 4,4′-Diiodo-2,2′-[(3aR,7aR-2,3,3a,4,5,6,7,7a-octahydro-1H-1,3-benzimidazole-1,3-diylbis(methylene]diphenol

    Directory of Open Access Journals (Sweden)

    Augusto Rivera

    2011-09-01

    Full Text Available In the crystal structure of the title compound, C21H24I2N2O2, the two N atoms of the imidazolidine moiety are linked to the hydroxy groups by intramolecular O—H...N hydrogen-bonding interactions. The cyclohexane ring adopts a chair conformation and the heterocyclic ring to which it is fused has a twisted envelope conformation.

  20. Dimethyl 4,4′-dihydroxy-3,3′-{[(3aRS,7aRS-2,3,3a,4,5,6,7,7a-octahydro-1H-1,3-benzimidazole-1,3-diyl]bis(methylene}dibenzoate

    Directory of Open Access Journals (Sweden)

    Augusto Rivera

    2011-11-01

    Full Text Available The title compound, C25H30N2O6, has the imidazolidine ring in an envelope conformation. There are two intramolecular O—H...N hydrogen-bond interactions with graph-set motif S(6. The cyclohexane ring adopts a slightly distorted chair conformation. One methyl carboxylate substituent forms a dihedral angle of 12.00 (5° with the plane of the benzene ring, while the other methyl carboxylate group is almost coplanar, making a dihedral angle of 2.26 (9°. In the crystal, pairs of intermolecular C—H...O hydrogen bonds form racemic dimers, corresponding to an R22(18 graph-set motif. Further weak C—H...O interactions generate a chain running along the c axis.

  1. Di-n-propyl 4,4′-dihydroxy-3,3′-{[(3aRS,7aRS-2,3,3a,4,5,6,7,7a-octahydro-1H-benzimidazole-1,3-diyl]bis(methylene}dibenzoate

    Directory of Open Access Journals (Sweden)

    Karla Fejfarová

    2011-10-01

    Full Text Available The title compound, C29H38N2O6, was prepared as model for studying intramolecular hydrogen-bonding interactions. Molecules of the title compound are located on a crystallographic twofold rotation axis, which passes through the C atom linked to the two N atoms on the imidazolidine ring. The molecular structure shows the existence of two intramolecular O—H...N hydrogen-bonding interactions between the two N atoms of the imidazolidine moiety and the hydroxy groups in the aromatic rings. The crystal structure shows the strain of ring fusion in the perhydrobenzimidazole moiety according to the endocyclic bond angles and the torsion angles, which evidence a puckering of the cyclohexane ring with respect to normal tetrahedral bond angles in an ideal chair conformation.

  2. 4,4′-Dimethoxy-2,2′-{[(3aRS,7aRS-2,3,3a,4,5,6,7,7a-octahydro-1H-1,3-benzimidazole-1,3-diyl]bis(methylene}diphenol

    Directory of Open Access Journals (Sweden)

    Augusto Rivera

    2011-09-01

    Full Text Available The title compound, C23H30N2O4, is a Mannich base useful for studying the effect of an electron-donating phenol substituent on intramolecular hydrogen bonding. In the molecular structure, the cyclohexane ring adopts a chair conformation and the five-membered ring has a twisted envelope conformation. Each methoxy group is oriented in the same plane of the respective aromatic ring, showing torsion angles below 11.8 (3° and bond angles between the methoxy group and the aromatic ring of 116.6 (2 and 116.6 (1°. The structure shows interactions between two the N atoms of the heterocyclic ring and the hydroxy groups by intramolecular O—H...N hydrogen-bonding interactions. In the crystal, C—H...O interactions are observed. The crystal studied was a racemic mixture of RR and SS enantiomers.

  3. 4,4′-Dichloro-3,3′,5,5′-tetramethyl-2,2′-[(3aR,7aR/3aS,7aS-2,3,3a,4,5,6,7,7a-octahydro-1H-1,3-benzimidazole-1,3-diylbis(methylene]diphenol

    Directory of Open Access Journals (Sweden)

    Augusto Rivera

    2011-08-01

    Full Text Available In the title compound, C25H32Cl2N2O2, there are two intramolecular O—H... N hydrogen-bonding interactions between the hydroxy groups on the aromatic rings and the two N atoms of the heterocyclic group. The cyclohexane ring adopts a chair conformation and the imidazolidine unit to which it is fused has a twisted envelope conformation. The asymmetric unit comprises one half-molecule which is completed by a twofold rotation axis. A C—H...O interaction is observed in the crystal structure.

  4. 4,4′-Dibromo-2,2′-{[(3aS,7aS-2,3,3a,4,5,6,7,7a-octahydro-1H-1,3-benzimidazole-1,3-diyl]bis(methylidene}diphenol

    Directory of Open Access Journals (Sweden)

    Augusto Rivera

    2011-04-01

    Full Text Available The cyclohexane ring in the title compound, C21H24Br2N2O2, adopts a chair conformation and the five-membered ring to which it is fused has a twisted envelope conformation. The asymmetric unit contains one half-molecule, which is related to the other half by a twofold rotation axis. The two N atoms of the five-membered ring are linked to the hydroxy groups by intramolecular O—H...N hydrogen bonds. In the crystal, intermolecular C—H...O and C—H...π interactions occur.

  5. 4,4′-Dichloro-2,2′-[(3aR,7aR/3aS,7aS-2,3,3a,4,5,6,7,7a-octahydro-1H-1,3-benzimidazole-1,3-diylbis(methylene]diphenol

    Directory of Open Access Journals (Sweden)

    Michal Dušek

    2010-10-01

    Full Text Available Molecules of the the title compound, C21H24Cl2N2O2, are located on a twofold rotation axis, which passes through the C atom linking the two N atoms. Two intramolecular O—H...N hydrogen bonds were observed. In the crystal, non-classical intermolecular C—H...O hydrogen bonds link the molecules into chains along the a axis. The crystal studied was a racemic twin.

  6. Diethyl 4,4′-dihydroxy-3,3′-{[(3aRS,7aRS-2,3,3a,4,5,6,7,7a-octahydro-1H-1,3-benzimidazole-1,3-diyl]bis(methylene}dibenzoate

    Directory of Open Access Journals (Sweden)

    Augusto Rivera

    2011-11-01

    Full Text Available The heterocyclic ring in the title compound, C27H34N2O6, has an envelope conformation on one of the bridgehead C atoms [Q(2 = 0.4487 (19 Å and ϕ = 291.3 (2°]. Two strong intramolecular O—H...N hydrogen bonds stabilize the molecular conformation. The benzoate groups differ in the relative orientations of the ethyl groups, as quantified by the values of the C—O—C—C torsion angles of −86.5 (2 and −178.97 (17°. The carbonyl groups are nearly coplanar with the benzene rings, forming C—C—C—O torsion angles of 0.9 (3 and 3.4 (3°. The crystal structure is stabilized by weak intermolecular C—H...O interactions.

  7. meso-4,4′-Difluoro-2,2′-{[(3aR,7aS-2,3,3a,4,5,6,7,7a-octahydro-1H-1,3-benzimidazole-1,3-diyl]bis(methylene}diphenol

    Directory of Open Access Journals (Sweden)

    Augusto Rivera

    2013-02-01

    Full Text Available In the crystal structure of the title compound, C21H24F2N2O2, there are two intramolecular O—H...N hydrogen bonds involving the N atoms of the imidazolidine ring and the hydroxy groups. The crystal studied was a meso compound obtained by the reaction of the aminal (2S,7R,11S,16R-1,8,10,17-tetraazapentacyclo[8.8.1.18,17.02,7.011,16]cosane with 4-fluorophenol. The imidazolidine ring has a twisted conformation with a CH—CH—N—CH2 torsion angle of 44.99 (14° and, surprisingly, the lone pairs of the N atoms are disposed in a syn isomerism, making the title compound an exception to the typical `rabbit-ear effect' in 1,2-diamines. In the crystal, molecules are linked via C—H...F hydrogen bonds, forming chains along the c-axis direction. These chains are linked via another C—H...F hydrogen bond, forming a three-dimensional network.

  8. Di-n-butyl 4,4′-dihydroxy-3,3′-{[(3aRS,7aRS-2,3,3a,4,5,6,7,7a-octahydro-1H-1,3-benzimidazole-1,3-diyl]bis(methylene}dibenzoate

    Directory of Open Access Journals (Sweden)

    Augusto Rivera

    2011-09-01

    Full Text Available The complete molecule of the title compound, C31H42N2O6, is generated by crystallographic twofold symmetry, with one C atom lying on the axis. The dihedral angle between the aromatic rings is 57.03 (6°. The central heterocyclic ring adopts a half-chair conformation. The molecular conformation is stabilized by two intramolecular O—H...N hydrogen bonds with the N atoms of the heterocyclic ring as the acceptors. In the crystal, molecules are linked into chains along the c axis by non-classical C—H...O hydrogen bonds.

  9. 4,4′-Difluoro-2,2′-{[(3aRS,7aRS-2,3,3a,4,5,6,7,7a-octahydro-1H-1,3-benzimidazole-1,3-diyl]bis(methylene]}diphenol

    Directory of Open Access Journals (Sweden)

    Augusto Rivera

    2011-06-01

    Full Text Available In the crystal structure of the title compound, C21H24F2N2O2, the two N atoms of the imidazolidine moiety are linked to the hydroxy groups by intramolecular O—H...N hydrogen-bonding interactions. The crystal studied was a racemic mixture of RR and SS enatiomers. The cyclohexane ring adopts a chair conformation and the imidazolidine group to which it is fused has a twisted envelope conformation.

  10. A visibilidade e representação social das religiões nos selos postais brasileiros (The visibility and social representations of religions in Brazil postage stamps.DOI: 10.5752/P.2175-5841.2012v10n25p233

    Directory of Open Access Journals (Sweden)

    Diego Andres Salcedo

    2012-03-01

    Full Text Available Normal 0 21 false false false PT-BR X-NONE X-NONE MicrosoftInternetExplorer4 Este trabalho analisa a forma com a qual o selo postal brasileiro contribuiu para a construção de representações da religião católica em relação a outras práticas religiosas. Foi considerado, para isso, a concepção deste artefato enquanto media, texto semiótico e sua estreita relação com o discurso religioso. O corpus é composto por selos postais comemorativos brasileiros emitidos durante o século XX. A sua identificação e análise foi feita a partir do catálogo RHM. Entre o ano de 1900 e 2000, os Correios emitiram 2354 selos postais do tipo comemorativo. A partir da observação e identificação de recorrências religiosas foram compilados 222 selos postais comemorativos. O estudo correlacionou a recorrente temática religiosa com o contexto histórico brasileiro, considerando o declínio do catolicismo como maioria religiosa no país e às representações das práticas religiosas nas mídias. A conclusão indica a influência da Conferência Nacional dos Bispos do Brasil, junto ao Ministério das Comunicações e dos Correios do Brasil, consagrando e enaltecendo a visibilidade de personalidades, eventos e a práxis católica, como um discurso único e superior às demais práticas religiosas. Normal 0 21 false false false MicrosoftInternetExplorer4 Abstract This paper analyses the way in which postal Brazilian stamps have contributed to the construction of representations of the catholic religion regarding other religious practices. In this sense, the conception of these stamps was taken into account as media, semioptical texts in close relation with the religious speech. The corpus is composed by postal commemorative Brazilian stamps issued during the twentieth century. The identification and analyzes of the stamps were made through RHM catalogue.  Between the year of 1900 and 2000, the Brazilian post offices issued 2.354 commemorative postage stamps. From the observation and identification of religious recurrences 222 commemorative stamps were compiled. The study correlated the recurring religious theme with the historical Brazilian context, taking into account the decline of the Catholicism as the major religion in Brazil and also the representations of the religious practices in the media. The conclusion of this paper indicates the influence of the National Conference of the Bishops of Brazil regarding the Ministry of the Communications, establishing and enforcing the visibility of Brazilian personalities, events, and also of catholic practices taken as special and superior in comparison with other religious practices.Key-words: Brazil; Religion; Postage Stamps; Social Representation; Visibility.

  11. International Electronic Journal of Elementary Educ ation, 2013, 5(3, 233-248. ISSN:1307 9298 Copyright © IEJEE www.iejee.com Relationship among Students’ Attitudes, Intentions and Behaviors towards the Inclusion of Peers with Disabilities, in Mainstream Physical Education Classes

    Directory of Open Access Journals (Sweden)

    Evangelos BEBETSOS

    2013-07-01

    Full Text Available Students’ attitudes, intentions and behaviours towards their peers with disabilities are important to their mutual co existence and development. The aim of this study was to investigate a whetherstudents’ attitudes and intentions towards their schoolmates with disabilities are related to their general and modified behavior in mainstream physical education classes, and b if the former variables could serve as predictors of the latter. The participants, 172 children without disabilities(Mage=11.15,SD=.70, completed the revised version of the Planned Behavior Theory questionnaire(PBT and the Children’s’ Attitudes towards Inclusion in Physical Education – Revised questionnaire(CAIPE R. Although results revealed several correlations among the variables under study, only general attitudes accounted for both general and modified behavior, and attitudes for modified behavior. These findings could assist in educating students to develop and perform appropriate behaviours towards their peers in order to facilitate their co existence, and their mutual developmentand learning.

  12. DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS

    Energy Technology Data Exchange (ETDEWEB)

    P. Bernot

    2005-07-13

    The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this activity is to predict dissolved concentrations or solubility limits for elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) relevant to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are provided in the form of tabulated functions with pH and log fCO{sub 2} as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. Even though selection of an appropriate set of radionuclides documented in Radionuclide Screening (BSC 2002 [DIRS 160059]) includes actinium, transport of Ac is not modeled in the total system performance assessment for the license application (TSPA-LA) model because of its extremely short half-life. Actinium dose is calculated in the TSPA-LA by assuming secular equilibrium with {sup 231}Pa (Section 6.10); therefore, Ac is not analyzed in this report. The output data from this report are fundamental inputs for TSPA-LA used to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for the actinides discussed in this report. These models cover broad ranges of environmental conditions so they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or

  13. Detection of rare earth elements in Powder River Basin sub-bituminous coal ash using laser-induced breakdown spectroscopy (LIBS)

    Energy Technology Data Exchange (ETDEWEB)

    Tran, Phuoc [National Energy Technology Lab. (NETL), Pittsburgh, PA, (United State; Mcintyre, Dustin [National Energy Technology Lab. (NETL), Pittsburgh, PA, (United State

    2015-10-01

    We reported our preliminary results on the use of laser-induced breakdown spectroscopy to analyze the rare earth elements contained in ash samples from Powder River Basin sub-bituminous coal (PRB-coal). We have identified many elements in the lanthanide series (cerium, europium, holmium, lanthanum, lutetium, praseodymium, promethium, samarium, terbium, ytterbium) and some elements in the actinide series (actinium, thorium, uranium, plutonium, berkelium, californium) in the ash samples. In addition, various metals were also seen to present in the ash samples

  14. Thorium and the Third Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Dukert, Joseph M.

    1970-01-01

    This booklet discusses energy sources for nuclear power plants. Uranium-235 by itself will not be able to handle the energy needs. The two man-made supplements that can be used for nuclear power plants energy sources are plutonium and uranium-233. Uranium-233 is an isotope that appears as a result of radioactive decay after neutrons have been absorbed in thorium-232. This uranium-233 is called the third fuel.

  15. Low background counting of 222Rn, 220Rn and 219Rn with electrostatic counters

    Science.gov (United States)

    Mong, Brian; EXO-200 Collaboration; nEXO Collaboration

    2014-09-01

    The radon counting technique based on electrostatic precipitation of progenies in gas followed by alpha spectroscopy has been applied to support the material selection programs of low background, neutrino and dark matter experiments with emphasis on EXO. An array of 8 counters operated by Laurentian University at SNOLAB and the Waste Isolation Pilot Plant have reached the sensitivity of 10 atoms/day in the uranium, thorium and actinium chains. Hardware improvements are underway to further increase the capacity and sensitivity in support of nEXO. The radon counting technique based on electrostatic precipitation of progenies in gas followed by alpha spectroscopy has been applied to support the material selection programs of low background, neutrino and dark matter experiments with emphasis on EXO. An array of 8 counters operated by Laurentian University at SNOLAB and the Waste Isolation Pilot Plant have reached the sensitivity of 10 atoms/day in the uranium, thorium and actinium chains. Hardware improvements are underway to further increase the capacity and sensitivity in support of nEXO. Supported by NSERC Project Grants ``Search for Double Beta Decay with EXO.''

  16. Purification of cerium, neodymium and gadolinium for low background experiments

    Science.gov (United States)

    Boiko, R. S.; Barabash, A. S.; Belli, P.; Bernabei, R.; Cappella, F.; Cerulli, R.; Danevich, F. A.; Incicchitti, A.; Laubenstein, M.; Mokina, V. M.; Nisi, S.; Poda, D. V.; Polischuk, O. G.; Tretyak, V. I.

    2014-01-01

    Cerium, neodymium and gadolinium contain double beta active isotopes. The most interesting are 150Nd and 160Gd (promising for 0ν2β search), 136Ce (2β+ candidate with one of the highest Q2β). The main problem of compounds containing lanthanide elements is their high radioactive contamination by uranium, radium, actinium and thorium. The new generation 2β experiments require development of methods for a deep purification of lanthanides from the radioactive elements. A combination of physical and chemical methods was applied to purify cerium, neodymium and gadolinium. Liquid-liquid extraction technique was used to remove traces of Th and U from neodymium, gadolinium and for purification of cerium from Th, U, Ra and K. Co-precipitation and recrystallization methods were utilized for further reduction of the impurities. The radioactive contamination of the samples before and after the purification was tested by using ultra-low-background HPGe gamma spectrometry. As a result of the purification procedure the radioactive contamination of gadolinium oxide (a similar purification efficiency was reached also with cerium and neodymium oxides) was decreased from 0.12 Bq/kg to 0.007 Bq/kg in 228Th, from 0.04 Bq/kg to <0.006 Bq/kg in 226Ra, and from 0.9 Bq/kg to 0.04 Bq/kg in 40K. The purification methods are much less efficient for chemically very similar radioactive elements like actinium, lanthanum and lutetium.

  17. Mixed valency of the RE and Ac ions in solid states

    International Nuclear Information System (INIS)

    Full text: This review is devoted to consideration of the methods and results of the theoretical and experimental investigations of the electronic state of the rare earths and actinium ions in the separate compound. The methods of the high resolution X ray spectroscopy were used for our consideration. Energy of the X ray lines of the rare earths and actinium ions in free state and solid states was study carefully. Valency shifts of X Ray lines under change of electronic state of nf - ions in different oxide, fluoride and chloride compounds were determined for K -, L- and M - lines for these ions with accuracy near 10 -100 MeV. We studied the electronic state of nf- ions which is changed from '+2' to '+4' and determined the concentration of ions in different electronic state. Relative error for theoretical energy of the most lines for HFP - approach in comparison with experiment is less than 0.5%, and deviation for concentration is less than 5%

  18. The Technological Enhancement of Normally Occurring Radioactive Materials in Red Mud due to the Production of Alumina

    Directory of Open Access Journals (Sweden)

    Maurice O. Miller

    2016-01-01

    Full Text Available This study investigates the level of technological enhancement of normally occurring radioactive materials (TENORM in the red mud waste due to the production of alumina in Jamaica. Technological enhancements factors (TEF were determined for the uranium, thorium, actinium series, their progenies, and the nonseries potassium-40 using gamma spectrometry. The study concluded that bauxite production technologically enhances the uranium progenies Th-234, Pb-214, Bi-214, and Pa-234 and the thorium-232 progenies Ac-228, Pb-212, and Bi-212 in red mud. The actinium series was technologically enhanced, but K-40 and the thorium daughter, Tl-208, were reduced. The spectrometric comparison of Tl-208 (at 510 keV was unexpected since its other photopeaks at 583 keV, 934 keV, and 968 keV were markedly different. An explanation for this anomaly is discussed. An explanation regarding the process of accumulation and fractionation of organically derived phosphate deposits and potassium-feldspar is offered to explain the spectrometric differences between the alumina product and its waste material, red mud.

  19. A study of uranium and thorium migration at the Koongarra uranium deposit with application to actinide transport from nuclear waste repositories

    International Nuclear Information System (INIS)

    One way to gain confidence in modelling possible radionuclide releases is to study natural systems which are similar to components of the multibarrier waste repository. Several such analogues are currently under study and these provide useful data about radionuclide behaviour in the natural environment. One such system is the Koongarra uranium deposit in the Northern Territory. In this dissertation, the migration of actinides, primarily uranium and thorium, has been studied as an analogue for the behaviour of transuranics in the far-field of a waste repository. The major findings of this study are: 1. the main process retarding uranium migration in the dispersion fan at Koongarra is sorption, which suppresses dissolved uranium concentrations well below solubility limits, with ferrihydrite being a major sorbing phase; 2. thorium is extremely immobile, with very low dissolved concentrations and corresponding high distribution ratios for 230Th. Overall, it is estimated that colloids are relatively unimportant in Koongarra groundwater. Uranium migrates mostly as dissolved species, whereas thorium and actinium are mostly adsorbed to larger, relatively immobile particles and the stationary phase. However, of the small amount of 230Th that passes through a 1μm filter, a significant proportion is associated with colloidal particles. Actinium appears to be slightly more mobile than thorium and is associated with colloids to a greater extent, although generally present in low concentrations. These results support the possibility of colloidal transport of trivalent and tetravalent actinides in the vicinity of a nuclear waste repository. 112 refs., 23 tabs., 32 figs

  20. Purification of cerium, neodymium and gadolinium for low background experiments

    Directory of Open Access Journals (Sweden)

    Boiko R.S.

    2014-01-01

    Full Text Available Cerium, neodymium and gadolinium contain double beta active isotopes. The most interesting are 150Nd and 160Gd (promising for 0ν2β search, 136Ce (2β+ candidate with one of the highest Q2β. The main problem of compounds containing lanthanide elements is their high radioactive contamination by uranium, radium, actinium and thorium. The new generation 2β experiments require development of methods for a deep purification of lanthanides from the radioactive elements. A combination of physical and chemical methods was applied to purify cerium, neodymium and gadolinium. Liquid-liquid extraction technique was used to remove traces of Th and U from neodymium, gadolinium and for purification of cerium from Th, U, Ra and K. Co-precipitation and recrystallization methods were utilized for further reduction of the impurities. The radioactive contamination of the samples before and after the purification was tested by using ultra-low-background HPGe gamma spectrometry. As a result of the purification procedure the radioactive contamination of gadolinium oxide (a similar purification efficiency was reached also with cerium and neodymium oxides was decreased from 0.12 Bq/kg to 0.007 Bq/kg in 228Th, from 0.04 Bq/kg to <0.006 Bq/kg in 226Ra, and from 0.9 Bq/kg to 0.04 Bq/kg in 40K. The purification methods are much less efficient for chemically very similar radioactive elements like actinium, lanthanum and lutetium.

  1. Scoping Review of the Zika Virus Literature.

    Directory of Open Access Journals (Sweden)

    Lisa A Waddell

    Full Text Available The global primary literature on Zika virus (ZIKV (n = 233 studies and reports, up to March 1, 2016 has been compiled using a scoping review methodology to systematically identify and characterise the literature underpinning this broad topic using methods that are documented, updateable and reproducible. Our results indicate that more than half the primary literature on ZIKV has been published since 2011. The articles mainly covered three topic categories: epidemiology of ZIKV (surveillance and outbreak investigations 56.6% (132/233, pathogenesis of ZIKV (case symptoms/ outcomes and diagnosis 38.2% (89/233 and ZIKV studies (molecular characterisation and in vitro evaluation of the virus 18.5% (43/233. There has been little reported in the primary literature on ZIKV vectors (12/233, surveillance for ZIKV (13/233, diagnostic tests (12/233 and transmission (10/233. Three papers reported on ZIKV prevention/control strategies, one investigated knowledge and attitudes of health professionals and two vector mapping studies were reported. The majority of studies used observational study designs, 89.7% (209/233, of which 62/233 were case studies or case series, while fewer (24/233 used experimental study designs. Several knowledge gaps were identified by this review with respect to ZIKV epidemiology, the importance of potential non-human primates and other hosts in the transmission cycle, the burden of disease in humans, and complications related to human infection with ZIKV. Historically there has been little research on ZIKV; however, given its current spread through Australasia and the Americas, research resources are now being allocated to close many of the knowledge gaps identified in this scoping review. Future updates of this project will probably demonstrate enhanced evidence and understanding of ZIKV and its impact on public health.

  2. Scoping Review of the Zika Virus Literature

    Science.gov (United States)

    2016-01-01

    The global primary literature on Zika virus (ZIKV) (n = 233 studies and reports, up to March 1, 2016) has been compiled using a scoping review methodology to systematically identify and characterise the literature underpinning this broad topic using methods that are documented, updateable and reproducible. Our results indicate that more than half the primary literature on ZIKV has been published since 2011. The articles mainly covered three topic categories: epidemiology of ZIKV (surveillance and outbreak investigations) 56.6% (132/233), pathogenesis of ZIKV (case symptoms/ outcomes and diagnosis) 38.2% (89/233) and ZIKV studies (molecular characterisation and in vitro evaluation of the virus) 18.5% (43/233). There has been little reported in the primary literature on ZIKV vectors (12/233), surveillance for ZIKV (13/233), diagnostic tests (12/233) and transmission (10/233). Three papers reported on ZIKV prevention/control strategies, one investigated knowledge and attitudes of health professionals and two vector mapping studies were reported. The majority of studies used observational study designs, 89.7% (209/233), of which 62/233 were case studies or case series, while fewer (24/233) used experimental study designs. Several knowledge gaps were identified by this review with respect to ZIKV epidemiology, the importance of potential non-human primates and other hosts in the transmission cycle, the burden of disease in humans, and complications related to human infection with ZIKV. Historically there has been little research on ZIKV; however, given its current spread through Australasia and the Americas, research resources are now being allocated to close many of the knowledge gaps identified in this scoping review. Future updates of this project will probably demonstrate enhanced evidence and understanding of ZIKV and its impact on public health. PMID:27244249

  3. 77 FR 22234 - Notice of Intent To Request Public Comments

    Science.gov (United States)

    2012-04-13

    ... Against Deceptive Pricing, 16 CFR part 233; Guides Against Bait Advertising, 16 CFR part 238; Guides... Records. 233 Guides Against Deceptive Pricing. 2017. 238 Guides Against Bait Advertising.. 2017. 251 Guide Concerning Use of the Word 2017. AFree@ and Similar Representations. 410 Deceptive Advertising as to...

  4. Program Management Educational Needs of Idaho Business and Marketing Teachers

    Science.gov (United States)

    Kitchel, Allen; Cannon, John; Duncan, Dennis

    2009-01-01

    The purpose of this study was to determine the perceived program management professional development needs of Idaho secondary business/marketing teachers (N = 233) in order to guide pre-service curriculum development and in-service training activities. Sixty-two percent (n = 146) of the 233 teachers completed a modified version of Joerger's (2002)…

  5. NCBI nr-aa BLAST: CBRC-DDIS-01-0174 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-DDIS-01-0174 ref|NP_048305.1| ORF MSV233 hypothetical protein [Melanoplus sanguinipes entomo...poxvirus] gb|AAC97745.1| ORF MSV233 hypothetical protein [Melanoplus sanguinipes entomopoxvirus] NP_048305.1 7e-08 46% ...

  6. NCBI nr-aa BLAST: CBRC-BTAU-01-2984 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-BTAU-01-2984 ref|NP_048305.1| ORF MSV233 hypothetical protein [Melanoplus sanguinipes entomo...poxvirus] gb|AAC97745.1| ORF MSV233 hypothetical protein [Melanoplus sanguinipes entomopoxvirus] NP_048305.1 0.005 34% ...

  7. 75 FR 60745 - Notice of Intent To Prepare a Supplemental Environmental Impact Statement for the Nuclear...

    Science.gov (United States)

    2010-10-01

    ... FR 6967). Over time, due in large part to detailed site geotechnical investigations, some aspects of... of 1954 as plutonium, uranium-233, or uranium enriched in the isotopes uranium-233 or uranium-235... (CMRR RLUOB). Upon completion, the CMRR Facility would replace the CMR Building, operations would...

  8. Summary and conclusions

    Digital Repository Service at National Institute of Oceanography (India)

    Rao, D.G.; Murthy, K.S.R.; Neprochnov, Y.P.; Subrahmanyam, C.

    stream_size 4 stream_content_type text/plain stream_name Mem_Geol_Soc_India_1998_39_233.pdf.txt stream_source_info Mem_Geol_Soc_India_1998_39_233.pdf.txt Content-Encoding ISO-8859-1 Content-Type text/plain; charset=ISO-8859-1 ...

  9. Ecology of marine deposit feeders. Ed. by G. Lopez, C. Taghon and J. Levinton

    Digital Repository Service at National Institute of Oceanography (India)

    Royan, J

    stream_size 2 stream_content_type text/plain stream_name Indian_J_Mar_Sci_19_233.pdf.txt stream_source_info Indian_J_Mar_Sci_19_233.pdf.txt Content-Encoding ISO-8859-1 Content-Type text/plain; charset=ISO-8859-1 ...

  10. Domain Modeling: NP_001009882.1 [SAHG[Archive

    Lifescience Database Archive (English)

    Full Text Available NP_001009882.1 chr1 Crystal structure of human myristoyl-CoA:protein N-myristoyltra...nsferase. d1rxta_ chr1/NP_001009882.1/NP_001009882.1_apo_91-233.pdb c1rxtc_ chr1/NP_001009882.1/NP_001009882.1_holo_91-233.pdb forte 197E CMO 1 ...

  11. GETDB: 113556 [GETDB

    Lifescience Database Archive (English)

    Full Text Available titute of Genetics. FM7c Link to clone table - 1 233 Link to cluster table 233 1 Request - CNS+PNS in stg 15. limit...nic Expression CNS+PNS in stg 15. limited to posterior midline in stg 10 bro. Larval GFP subset of PNS? two

  12. 42 CFR 435.4 - Definitions and use of terms.

    Science.gov (United States)

    2010-10-01

    ... eligible under AFDC or medically needy rules and who are deprived of parental support or care as defined under the AFDC program (see 45 CFR 233.90, 233.100). In addition, this group includes individuals under age 21 who are not deprived of parental support or care but are financially eligible under AFDC...

  13. 42 CFR 436.3 - Definitions and use of terms.

    Science.gov (United States)

    2010-10-01

    ... financially eligible under AFDC or medically needy rules and who are deprived of parental support or care as defined under the AFDC program (see 45 CFR 233.90; 233.100). In addition, this group includes individuals under age 21 who are not deprived of parental support or care but who are financially eligible...

  14. 77 FR 73976 - Nez Perce-Clearwater National Forests; Idaho; Crooked River Valley Rehabilitation Project

    Science.gov (United States)

    2012-12-12

    ... project area. Maintain campsites in the project area. Preserve heritage resource areas as identified by.... The Forest may consider converting the ] existing Road 233 to a trail or completely decommissioning... may consider converting the existing Road 233 to a trail or completely decommissioning the road....

  15. Dicty_cDB: Contig-U14940-1 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available 4e-60 EU079543_1( EU079543 |pid:none) Phytophthora capsici isolate PD_00... 233 4e-60 EU079782_1( EU079782 |...pid:none) Phytophthora vignae isolate PD_001... 233 5e-60 EU079555_1( EU079555 |pid:none) Phytophthora nicot

  16. School functioning in 8- to 18-year-old children born after in vitro fertilization

    NARCIS (Netherlands)

    Wagenaar, Karin; Ceelen, Manon; Weissenbruch, van Mirjam; Knol, Dirk; Delemarre-van de Waal, Henriette; Huisman, Jaap

    2008-01-01

    The aim of this study was to examine the school functioning of 8- to 18-year-old children born after in vitro fertilization (IVF). We compared 233 children born after IVF to 233 matched control children born spontaneously from parents with fertility problems on measures of education level, general c

  17. 77 FR 40380 - Outer Continental Shelf, Gulf of Mexico, Oil and Gas Lease Sales, Western Planning Area Lease...

    Science.gov (United States)

    2012-07-09

    ... Bureau of Ocean Energy Management Outer Continental Shelf, Gulf of Mexico, Oil and Gas Lease Sales, Western Planning Area Lease Sale 233 and Central Planning Area Lease Sale 231 AGENCY: Bureau of Ocean... proposed Western Planning Area (WPA) Lease Sale 233 and Central Planning Area (CPA) Lease Sale 231...

  18. Role of thorium in the industry advantage of atomic energy

    International Nuclear Information System (INIS)

    Based in the utilization of others fossil substances, such as plutonium and uranium 233, produzed through the thorium and natural uranium (238), it is discussed the relative merits of alternative processes: to produce U233 on Pu 239 to substitute the initial load of U235. (M.C.K.)

  19. 76 FR 23872 - Editorial Corrections to the Export Administration Regulations

    Science.gov (United States)

    2011-04-29

    ..., ``Facilities and plants described in 1B233.a are subject to the export licensing authority of the Nuclear... plants described in 1B233.a are subject to the export licensing authority of the Nuclear Regulatory... the Export Administration Regulations AGENCY: Bureau of Industry and Security, Commerce. ACTION:...

  20. 75 FR 22095 - Notice of Funds Availability for the Section 533 Housing Preservation Grants for Fiscal Year 2010

    Science.gov (United States)

    2010-04-27

    ... OMB and published in the Federal Register on June 27, 2003 (68 FR 38402-38405). The Department of..., Kentucky 40503 (859) 224-7325 TDD (859) 224-7422 Beth Moore Louisiana State Office 3727 Government Street... 82602-5006 (307) 233-6716 TDD (307) 233-6733 Alan Brooks FOR FURTHER INFORMATION CONTACT: For...

  1. Operation of CANDU power reactor in thorium self-sufficient fuel cycle

    Indian Academy of Sciences (India)

    B R Bergelson; A S Gerasimov; G V Tikhomirov

    2007-02-01

    This paper presents the results of calculations for CANDU reactor operation in thorium fuel cycle. Calculations are performed to estimate the feasibility of operation of heavy-water thermal neutron power reactor in self-sufficient thorium cycle. Parameters of active core and scheme of fuel reloading were considered to be the same as for standard operation in uranium cycle. Two modes of operations are discussed in the paper: mode of preliminary accumulation of 233U and mode of operation in self-sufficient cycle. For the mode of accumulation of 233U it was assumed for calculations that plutonium can be used as additional fissile material to provide neutrons for 233U production. Plutonium was placed in fuel channels, while 232Th was located in target channels. Maximum content of 233U in target channels was estimated to be ∼ 13 kg/t of ThO2. This was achieved by irradiation for six years. The start of the reactor operation in the self-sufficient mode requires 233U content to be not less than 12 kg/t. For the mode of operation in self-sufficient cycle, it was assumed that all channels were loaded with identical fuel assemblies containing ThO2 and certain amount of 233U. It is shown that nonuniform distribution of 233U in fuel assembly is preferable.

  2. α谱法测定低微量铀、钍含量的研究

    Institute of Scientific and Technical Information of China (English)

    夏明; 周秀云

    1982-01-01

    Alpha-spectrometric technique is described as an independent method of determining micro-content of U233 and Th233. This method is based on the comparison of U234 and Th233 alpha spectral activity in geological samples with U232 and Th233 spectral activity contributed by the spike of known concentration. The experiment procedure consists in dissolving fine powdered sample with acid and adding a given amount of U232-Th223 spike. The uranium and thorium are then separated by ion exchange. After purification each fraction is mounted on a separate stainless steel disk for measurement by alpha spectrometer which consist essentially of a surface barrier deterctor and a low noise amplification system connected to a multichannel analyser. After correcting for background, tail and other factors, the desired U232 and Th232 concentrations can be calculated. The data obtained by the alpha-spectrometric method using U232-Th223 spike are compared with colorimetric determination. Excellent agreement is obtained between the two sets of results. The coefficient of correlation is about 0.98 for U234 and 0.97 for Th232. The accuracy of uranium and thorium analyses by this method depends primarily upon the counting statistics of U233, U232, Th233 and Th223 and, to a lesser extent, upon the calibration of U233-Th238 spike. Errors of uranium and thorium concentration by this method are generally 2 to 5 per cent.

  3. The mode of operation of CANDU power reactor in thorium self-sufficient fuel cycle

    Directory of Open Access Journals (Sweden)

    Bergelson Boris R.

    2008-01-01

    Full Text Available This paper presents the results of calculations for CANDU reactor operation in the thorium fuel cycle. The calculations were performed to estimate feasibility of operation of a heavy-water thermal neutron power reactor in the self-sufficient thorium cycle. The parameters of the active core and the scheme of fuel reloading were considered to be the same as for the standard operation in the uranium cycle. Two modes of operation are discussed in the paper: the mode of preliminary accumulation of 233U and the mode of operation in the self-sufficient cycle. For calculations for the mode of accumulation of 233U, it was assumed that plutonium was used as the additional fissile material to provide neutrons for 233U production. Plutonium was placed in fuel channels, while 232Th was located in target channels. The maximum content of 233U in the target channels was about 13 kg/t of ThO2. This was achieved by six year irradiation. The start of reactor operation in the self-sufficient mode requires content of 233U not less than 12 kg/t. For the mode of operation in the self-sufficient cycle, it was assumed that all the channels were loaded with the identical fuel assemblies containing ThO2 and a certain amount of 233U. It was shown that the non-uniform distribution of 233U in a fuel assembly is preferable.

  4. Radionuclide interactions with marine sediments

    International Nuclear Information System (INIS)

    A critical review of the literature on the subject of the interactions of radionuclides with marine sediments has been carried out. On the basis of the information available, an attempt has been made to give ranges and 'best estimates' for the distribution ratios between seawater and sediments. These estimates have been based on an understanding of the sediment seawater system and the porewater chemistry and mineralogy. Field measurements, laboratory measurements and estimates based on stable-element geochemical data are all taken into account. Laboratory measurements include distribution-ratio and diffusion-coefficient determinations. The elements reviewed are carbon, chlorine, calcium, nickel, selenium, strontium, zirconium, niobium, technetium, tin, iodine, caesium, lead, radium, actinium, thorium, protactinium, uranium, neptunium, plutonium, americium and curium. (author)

  5. Process for radioisotope recovery and system for implementing same

    Science.gov (United States)

    Meikrantz, David H.; Todd, Terry A.; Tranter, Troy J.; Horwitz, E. Philip

    2007-01-02

    A method of recovering daughter isotopes from a radioisotope mixture. The method comprises providing a radioisotope mixture solution comprising at least one parent isotope. The at least one parent isotope is extracted into an organic phase, which comprises an extractant and a solvent. The organic phase is substantially continuously contacted with an aqueous phase to extract at least one daughter isotope into the aqueous phase. The aqueous phase is separated from the organic phase, such as by using an annular centrifugal contactor. The at least one daughter isotope is purified from the aqueous phase, such as by ion exchange chromatography or extraction chromatography. The at least one daughter isotope may include actinium-225, radium-225, bismuth-213, or mixtures thereof. A liquid-liquid extraction system for recovering at least one daughter isotope from a source material is also disclosed.

  6. Proposed training program for construction personnel involved in remedial action work at sites contaminated by naturally occurring radionuclides

    International Nuclear Information System (INIS)

    Many sites used during the early days of the US atomic energy program are contaminated with radionuclides of the primordial decay chains (uranium, thorium, and actinium series). This contamination consists of residues resulting from refining and processing uranium and thorium. Preparation of these sites for release to unrestricted private use will involve the assistance of construction workers, many of whom have limited knowledge of the hazards associated with radioactive materials. Therefore, there is a need to educate these workers in the fundamentals of radioactive material handling to minimize exposures and possible spread of contamination. This training should disseminate relevant information at an appropriate educational level and should instill a cautious, common-sense attitude toward the handling of radioactive materials. The training should emphasize basic information concerning environmental radiation within a context of relative risk. A multi-media format, including colorful visual aids, demonstration, and discussion, should be used to maximize motivation and retention. A detailed, proposed training program design is presented

  7. JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Refinement of thermodynamic data for trivalent actinoids and samarium

    International Nuclear Information System (INIS)

    Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level radioactive and TRU wastes, the refinement of the thermodynamic data for the inorganic compounds and complexes of trivalent actinoids (actinium(III), plutonium(III), americium(III) and curium(III)) and samarium(III) was carried out. Refinement of thermodynamic data for these elements was based on the thermodynamic database for americium published by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). Based on the similarity of chemical properties among trivalent actinoids and samarium, complementary thermodynamic data for their species expected under the geological disposal conditions were selected to complete the thermodynamic data set for the performance assessment of geological disposal of radioactive wastes. (author)

  8. Theoretical Study on Properties of New Isotope 265Bh

    Institute of Scientific and Technical Information of China (English)

    2006-01-01

    The properties of nuclei belonging to the newly observed α-decay chain starting from 265Bh have been studied. The axially deformed relativistic mean-field calculation with the force NL-Z2 has been performed in the blockedBCS approximation. Some ground state properties such as binding energies, deformations, spins, and parities, as well as Q-values of the α-decay for this decay chain have been calculated and compared with known experimental data. Good agreement is found. The single-particle spectrum of the nucleus 265 Bh is studied and some new magic numbers are found,while the magnitudes of the shell gaps in superheavy nuclei are much smaller than those of nuclei before the actinium region, and the Fermi surfaces are close to the continuum. Thus the superheavy nuclei are usually not stable. The The methods which give good agreement with the data are selected.

  9. 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

    Energy Technology Data Exchange (ETDEWEB)

    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.)

  10. 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)

    International Nuclear Information System (INIS)

    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.)

  11. 两种稀土产品中放射性核素分析研究%ANALYSIS OF RADIONUCLIDES IN TWO RARE EARTH PRODUCTS

    Institute of Scientific and Technical Information of China (English)

    周程; 孙恋君

    2009-01-01

    利用高纯锗γ谱仪对两个稀土产品氯化镧和氯化钇的样品进行能谱分析,研究经湿法冶炼工艺后的稀土产品中放射性核素的活度变化.结果表明,样品中存在天然放射性钍系和锕-铀系的核素,以及天然放射性核素~(138)La和~(176)Lu,但两个样品中所含的放射性核素不相同.氯化镧产品中锕-铀系和钍系核素放射性未达平衡,其主要子体~(224)Ra和~(227)Th的含量随时间发生明显变化,约60天达到平衡;而氯化钇产品没有这种现象.%This paper describes a study on raidoactivity change of rare-earth products after hydrometallurgy technology,using HPGe gamma spectrometer to analyze two rare earth products (LaCl_3 and YCl_3).The results show that in the two samples exist natural radionuclides of thorium series and actinium-uranium series as well as other natural radionuclides 138 La and 176 Lu.In the sample of lanthanum chloride the radioactivity of actinium-uranium series and thorium series has not reached balance,the contents of their main progenies ~(226)Ra and ~(227)Th obviously changes with the time,reaching balance 60 days later,while YCl_3 keeps stability.

  12. Sieglind Luise Ellger-Rüttgardt / Grit Wachtel (Hrsg.): Pädagogische Professionalität und Behinderung. Herausforderungen aus historischer, nationaler und internationaler Perspektive, Stuttgart: Kohlhammer 2010 [Rezension

    OpenAIRE

    Weisser, Jan

    2011-01-01

    Rezension von: Sieglind Luise Ellger-Rüttgardt / Grit Wachtel (Hrsg.), Pädagogische Professionalität und Behinderung. Herausforderungen aus historischer, nationaler und internationaler Perspektive, Stuttgart: Kohlhammer 2010, 233 S.

  13. 29 CFR 2.32 - Equal participation of religious organizations.

    Science.gov (United States)

    2010-07-01

    ... governments administering DOL support from accommodating religion in a manner consistent with the..., and expression of its religious beliefs, subject to the provisions of § 2.33 of this subpart....

  14. Kohtuvõimu sõltumatus Euroopa Liiduga ühinemise protsessis. Kohtute sõltumatus Eestis / tõlkinud õigustõlkebüroo Interlex OÜ ... [jt.] ; Avatud Ühiskonna Instituut, Euroopa Liiduga liitumise seireprogramm

    Index Scriptorium Estoniae

    2001-01-01

    Eesti osa autor: Jaan Ginter. - Originaali tiitel: Judicial independence in Estonia : [elektrooniline teavik] // Monitoring the EU accession process: judicial independence. Open Society Institute, 2001 - http://www.eumap.org/reports/content/20/233/html

  15. Concealed Leather and Fur Finds from Kempten/ Allgäu (Germany)

    DEFF Research Database (Denmark)

    Atzbach, Rainer

    2002-01-01

    , in: Guido Helmig, Barbara Scholkmann, Matthias Untermann (Hgg.), Centre-Region-Periphery, Medieval Europe 2002 Preprinted Papers Vol. 3 (Hertingen 2002) 233-238. Online-Version der Posterpräsentation...

  16. 49 CFR 40.235 - What are the requirements for proper use and care of ASDs?

    Science.gov (United States)

    2010-10-01

    ... FOR TRANSPORTATION WORKPLACE DRUG AND ALCOHOL TESTING PROGRAMS Testing Sites, Forms, Equipment and... respect to breath ASDs, you must also follow the device use and care requirements of § 40.233 ....

  17. For Parents & Caregivers

    Science.gov (United States)

    ... All Rights Reserved. Press Privacy Attention Magazine Archives Advertise with CHADD Contact Us Site Map Report a Problem For help call: 800-233-4050 Follow CHADD on Facebook Follow CHADD on Twitter

  18. Complementary and Other Interventions

    Science.gov (United States)

    ... All Rights Reserved. Press Privacy Attention Magazine Archives Advertise with CHADD Contact Us Site Map Report a Problem For help call: 800-233-4050 Follow CHADD on Facebook Follow CHADD on Twitter

  19. Social Skills in Adults with AD/HD

    Science.gov (United States)

    ... All Rights Reserved. Press Privacy Attention Magazine Archives Advertise with CHADD Contact Us Site Map Report a Problem For help call: 800-233-4050 Follow CHADD on Facebook Follow CHADD on Twitter

  20. ADHD and the Military

    Science.gov (United States)

    ... All Rights Reserved. Press Privacy Attention Magazine Archives Advertise with CHADD Contact Us Site Map Report a Problem For help call: 800-233-4050 Follow CHADD on Facebook Follow CHADD on Twitter

  1. Teens with ADHD and Driving

    Science.gov (United States)

    ... All Rights Reserved. Press Privacy Attention Magazine Archives Advertise with CHADD Contact Us Site Map Report a Problem For help call: 800-233-4050 Follow CHADD on Facebook Follow CHADD on Twitter

  2. Women and Girls (With ADHD)

    Science.gov (United States)

    ... All Rights Reserved. Press Privacy Attention Magazine Archives Advertise with CHADD Contact Us Site Map Report a Problem For help call: 800-233-4050 Follow CHADD on Facebook Follow CHADD on Twitter

  3. Tritium Facilities Modernization and Consolidation Project Process Waste Assessment (Project S-7726)

    Energy Technology Data Exchange (ETDEWEB)

    Hsu, R.H. [Westinghouse Savannah River Company, AIKEN, SC (United States); Oji, L.N.

    1997-11-14

    Under the Tritium Facility Modernization {ampersand} Consolidation (TFM{ampersand}C) Project (S-7726) at the Savannah River Site (SS), all tritium processing operations in Building 232-H, with the exception of extraction and obsolete/abandoned systems, will be reestablished in Building 233-H. These operations include hydrogen isotopic separation, loading and unloading of tritium shipping and storage containers, tritium recovery from zeolite beds, and stripping of nitrogen flush gas to remove tritium prior to stack discharge. The scope of the TFM{ampersand}C Project also provides for a new replacement R&D tritium test manifold in 233-H, upgrading of the 233- H Purge Stripper and 233-H/234-H building HVAC, a new 234-H motor control center equipment building and relocating 232-H Materials Test Facility metallurgical laboratories (met labs), flow tester and life storage program environment chambers to 234-H.

  4. Tritium Facilities Modernization and Consolidation Project Process Waste Assessment (Project S-7726)

    International Nuclear Information System (INIS)

    Under the Tritium Facility Modernization ampersand Consolidation (TFM ampersand C) Project (S-7726) at the Savannah River Site (SS), all tritium processing operations in Building 232-H, with the exception of extraction and obsolete/abandoned systems, will be reestablished in Building 233-H. These operations include hydrogen isotopic separation, loading and unloading of tritium shipping and storage containers, tritium recovery from zeolite beds, and stripping of nitrogen flush gas to remove tritium prior to stack discharge. The scope of the TFM ampersand C Project also provides for a new replacement R ampersand D tritium test manifold in 233-H, upgrading of the 233- H Purge Stripper and 233-H/234-H building HVAC, a new 234-H motor control center equipment building and relocating 232-H Materials Test Facility metallurgical laboratories (met labs), flow tester and life storage program environment chambers to 234-H

  5. Data of evolutionary structure change: 1BFOE-1QLRC [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1BFOE-1QLRC 1BFO 1QLR E C DIKMTQSPSFLSASVGDRVTLNCKASQNI-DKYLNWYQQ...KLGESPKLLIYNTNNLQTGIPSRFSGSGSGTDFTLTISSLQPEDVATYFCLQHISRPRTFGTGTKLELKRANAAPTVSIFPPSTEQLATGGASVVCLMNKFYPRDISV...SQSVSSNYLAWYQQKPGQAPRLLIYDASSRATGIPDRFSGSGSGTDFTLTISRLEPEDFAVYYCQQYGSSPLTFGGGTKVEIKRTVAAPSVFIFPPSDEQL...e> 1QLR C 1QL...> ASN CA 259 SER CA 233 1QLR

  6. Bestimmung und Deutung von Angebotskurven Ein Beispiel

    NARCIS (Netherlands)

    J. Tinbergen (Jan)

    1930-01-01

    textabstractIn English: Determination and Interpretation of Supply Curves: an example In: David F. Hendry and Mary S. Morgan (Eds), The Foundations of Econometric Analysis, Cambridge University Press, New York, 1995, pp. 233-245

  7. System Requirements Document for the Molten Salt Reactor Experiment

    Energy Technology Data Exchange (ETDEWEB)

    Aigner, R.D.

    2000-04-01

    The purpose of the conversion process is to convert the {sup 233}U fluoride compounds that are being extracted from the Molten Salt Reactor Experiment (MSRE) equipment to a stable oxide for long-term storage at Bldg. 3019.

  8. Organization and management of the treatment for the wounded in 8.12 Tinjin Port Explosion, China

    Institute of Scientific and Technical Information of China (English)

    Xiao-Xia Guo; Zhi-Jun Li; Hui Li; Zhi-Xiang Zhang; Cong-Zhe Xu; Bin Zhu

    2015-01-01

    Tianjin Medical University General Hospital treated 233 wounded in 8.12 Tinjin Port explosion.Here we would like to analyze the treatment process for the wounded, and share the experiences of organization and management for emergency rescue operation.

  9. Seitse retke isamaale : mälestuslikud esseed / Hellar Grabbi ; [toimetanud Urmas Tõnisson ; kaanekujundus: Mari Ainso ; esikaane foto: Helmuth Neider

    Index Scriptorium Estoniae

    Grabbi, Hellar, 1929-

    2010-01-01

    Mälestusteraamatus meenutatakse ka kohtumisi Toomas Hendrik Ilvesega raadiojaamas "Vaba Euroopa" töötamise ajal (lk. 233, 285-286), 1988. a. Münchenis ilmunud almanahhis Põrp! ilmunud esseed "Niikuinii" (lk. 207)

  10. Men and Sexual Trauma

    Science.gov (United States)

    ... Adult male survivors of childhood sexual abuse. Counseling Psychology Quarterly, 8, 233-241. Garnefski, N., & Diekstra, R. F. W. (1997). Child sexual abuse and emotional and behavioral problems in ...

  11. 10 CFR 71.4 - Definitions.

    Science.gov (United States)

    2010-01-01

    ... unloading is performed by personnel having radiological training and resources appropriate for safe handling... carrier by the consignor. Fissile material means the radionuclides uranium-233, uranium-235, plutonium-239... nuclides themselves, not material containing fissile nuclides. Unirradiated natural uranium and...

  12. 78 FR 33428 - National Heart, Lung, and Blood Institute; Notice of Closed Meetings

    Science.gov (United States)

    2013-06-04

    ...: National Heart, Lung, and Blood Institute Special Emphasis Panel; Cardiovascular Risk Reduction. Date: June.... 93.233, National Center for Sleep Disorders Research; 93.837, Heart and Vascular Diseases...

  13. A Collaborative Virtual Environment for Situated Learning of Car Driving

    NARCIS (Netherlands)

    Miao, Yongwu; Pinkwart, Niels; Hoppe, Ulrich

    2007-01-01

    Miao, Y., Pinkwart, N., and Hoppe, H.U. (2006). "A Collaborative Virtual Environment for Situated Learning of Car Driving". International Journal on Advanced Technology for Learning (ATL), 3(4), 233-240.

  14. Efficacy of sodium bicarbonate as anaesthetic for yellow seahorse, Hippocampus kuda (Bleeker, 1852)

    Digital Repository Service at National Institute of Oceanography (India)

    Pawar, H.B.; Ingole, B.S.; Sreepada, R.A.

    Artemia, mysids or pelleted feeds. Aquaculture 255, 233–241. 27. Zar, J. H., 2005. Biostatistical analysis, Fourth addition, Pearson education (Singapore) Pvt. Ltd., Indian Branch, Delhi: 633 p. Source of support: Nil; Conflict of interest: None...

  15. Lower bounds on the independence number of certain graphs of odd girth at least seven

    DEFF Research Database (Denmark)

    Pedersen, A. S.; Rautenbach, D.; Regen, F.

    2011-01-01

    Heckman and Thomas [C.C. Heckman, R. Thomas, A new proof of the independence ratio of triangle-free cubic graphs, Discrete Math. 233 (2001) 233-237] proved that every connected subcubic triangle-free graph G has an independent set of order at least (4n(G) - m(G) - 1)/7 where n(G) and m(G) denote...

  16. AcEST: DK951968 [AcEST

    Lifescience Database Archive (English)

    Full Text Available ioxygenase OS=Capsicum annuum PE=2 SV=1 236 5e-61 tr|Q0H901|Q0H901_COFCA Carotenoid cleavage dioxygenase 1 OS=Coff....id cleavage dioxygena... 233 5e-60 tr|Q0H8Z7|Q0H8Z7_COFAR Carotenoid cleavage dioxygenase 1 OS=Coff... 233 5

  17. Prevalence and incidence of Parkinson's disease in The Faroe Islands

    DEFF Research Database (Denmark)

    Wermuth, Lene; Bech, Sara Brynhild Winther; Petersen, Maria Skaalum;

    2008-01-01

    A study in The Faroe Islands in 1995 suggested a high prevalence of idiopathic Parkinson's disease (IPD) and total parkinsonism of 187.6 and 233.4 per 100,000 inhabitants respectively.......A study in The Faroe Islands in 1995 suggested a high prevalence of idiopathic Parkinson's disease (IPD) and total parkinsonism of 187.6 and 233.4 per 100,000 inhabitants respectively....

  18. 47 CFR 73.202 - Table of Allotments.

    Science.gov (United States)

    2010-10-01

    ... 297A Lone Wolf 224A Millerton 265C2 Mooreland 254A, 300C2 Muldrow 286A Okeene 268C3 Pawhuska 233A... 280C VERMONT Albany 233A Canaan 231C3 Poultney 223A VIRGINIA Alberta 299A Belle Haven 252A Iron Gate... Waitsburg 272A WEST VIRGINIA Glenville 299A Marlinton 292A St Marys *287A Wardensville 239A White...

  19. Weakly polarization dependent electro-optic effect in poled silica

    DEFF Research Database (Denmark)

    Arentoft, Jesper; Pedersen, K.; Bozhevolnyi, Sergey I.;

    1999-01-01

    A ratio between c(2)33 and c(2)31 less than 3 is observed in measurements of the linear electro-optic effect and second-harmonic generation of poled silica.......A ratio between c(2)33 and c(2)31 less than 3 is observed in measurements of the linear electro-optic effect and second-harmonic generation of poled silica....

  20. The Relationships between Crude Oil Prices, Financial Performances and Share Prices of Oil and Gas Producers

    OpenAIRE

    Liu, Ying Gui

    2014-01-01

    The paper investigates the relationships between crude oil prices, financial performances and share prices of 233 studied oil and gas producers. Hamilton's (2003) study emphasized the significant correlation between increases in crude oil prices and US recessions. Hamilton (2010) also pointed out that almost all major economic downturns have been immediately preceded by a significant rise in oil prices. This study collects and uses all of the 233 worldwide listed oil and gas pr...

  1. Treatment of uranium-thorium fuel at its production stage

    International Nuclear Information System (INIS)

    The possibility of removing 232U at the stage of obtaining 233U for the convenience of processing and reducing radiation dose has been analyzed in the paper. This problem is solved by the technology of obtaining 233U in extracted neutron beams in cold channels of a reactor. This technology will allow the acceleration of the implementation of the uranium-thorium fuel cycle in the current reactor technologies

  2. Caractérisation des sources radioactives du cycle du combustible. Applications au cycle du thorium : synthèse de l'232U en combustibles solides

    OpenAIRE

    Leniau, Baptiste

    2013-01-01

    The thorium cycle is a good candidate for replacing the current U/Pu cycle since the fissile nucleus of the cycle, 233U, has neutronic properties favourable to a much better regeneration of fissile material in thermal reactors. Moreover, the production of minor actinides is significantly reduced. However, the use of Thorium is only viable if the spent fuel is reprocessed to recover the fissile 233U that does not exist in nature. This reprocessing will involve a heavy industrial infrastructure...

  3. The Potential Role of the Thorium Fuel Cycle in Reducing the Radiotoxicity of Long-Lived Waste - 13477

    International Nuclear Information System (INIS)

    The thorium (or more accurately the Th-232/U-233) fuel cycle is attracting growing interest world wide and one reason for this is the reduced radiotoxicity of long-lived waste, with the Th- 232/U-233 fuel cycle often being justified partly on the grounds of low radiotoxicity for long cooling times. This paper considers the evolution of heavy metal radiotoxicity in a Molten Salt Fast Reactor (MSFR) operating a closed Th-232/U-233 cycle during different operational phases. The paper shows that even in the MSFR core, the equilibrium radiotoxicity of the thorium fuel cycle is only reached after almost 100 years of operation. MSFR was chosen because it has many theoretical advantages that favour the Th-232/U-233 fuel cycle. Conventional solid fuel systems would be expected to behave similarly, but with even longer timescales and therefore the MSFR cycle can be used to define the limits of what is practically achievable. The results are used to argue the case that a fair approach to justifying the Th-232/U-233 breeder cycle should not quote the long term equilibrium radiotoxicity, but rather the somewhat less favourable radiotoxicity that could be achieved within the operational lifetime of the first generation of Th-232/U-233 breeder reactors. (authors)

  4. WO3对碳载EMD催化氧还原活性的影响%Effect of WO3 to catalytic activity of carbon supported EMD for oxygen reduction

    Institute of Scientific and Technical Information of China (English)

    黄幼菊; 林育丽; 莫烨强; 李伟善

    2012-01-01

    研究了助催化剂三氧化钨(WO3)对电解二氧化锰(EMD)催化性能的影响.通过球磨制备5种WO3含量的EMD复合催化剂,进行XRD、SEM和电化学性能测试.WO3影响了EMD的孔隙率,添加适量的WO3可改善EMD的催化性能.添加WO3催化剂的氧还原电位较未添加WO3催化剂提前0.02 V.当电压为-0.15 V时,EMD、( MnO2)33( WO3)0.7、(MnO2)33(WO3)1、( MnO2)33 (WO3)1.3及(MnO2 )33( WO3 )1.5的氧还原电流分别为:-0.21 mA、-0.35 mA、-0.85 mA、-0.53 mA和-0.08 mA,表明随着WO3添加量的增加,EMD的催化性能先提高,后下降.EMD、( MnO2)33( WO3 )0.7、( MnO2 )33( WO3)1、(MnO2)33 (WO3)1.3及(MnO2)33 (WO3)1.5制备的电池,放电平台分别为1.05 V、1.08 V、1.21 V、1.14 V和0.98 V;催化活性顺序为:(MnO2)33(WO3)1> (MnO2)33(WO3)1.3>(MnO2)33(WO3)0.7>EMD> (MnO2)33(WO3)1.5.%Effect of tungsten trioxide( WO3) additive to the electrolytic manganese dioxide (EMD) catalyze oxygen reduction activity was studied. EMD composite catalysts with 5 kinds of WO3 content were prepared by ball-milling. XRD, SEM and linear voltage scanning and galvanostatic discharge tests were taken. Adding proper W03 could improve the catalytic activity of EMD, the porosity of EMD was affected by WO3. Compared with the catalyst without adding WO3 ,the oxygen reduction potential of catalyst added WO3 was 0.02 V in advance. When the voltage was - 0.15 V,oxygen reduction current of EMD, (MnO2)33( WO3)0.7, (MnO2)33(WO3)1,(MnO2)33(WO3)1.3 and (MnO2)33(WO3)1.5 was -0.21 mA, -0.35 mA, -0.85 mA, -0.53 mA and - 0.08 mA,respectively,indicated that with the increasing of WO3 adding amount,the oxygen reduction current increased firstly, then decreased. The discharge platform of cell prepared with EMD,(MnO2)33( WO3)o.7,(MnO2)33( WO3)MnO2)33(WO3)1.3 and (MnO2)33(WO3)1.5 was 1.05 V, 1.08 V, 1.21 V, 1.14 V and 0.98 V, respectively.The catalytic activity was in the following order:(MnO2)33(WO3)1 > (MnO2)33(WO3)1.3 > (MnO2)33(WO3)0.7 > EMD > (Mn

  5. Research of natural resources saving by design studies of Pressurized Light Water Reactors and High Conversion PWR cores with mixed oxide fuels composed of thorium/uranium/plutonium

    International Nuclear Information System (INIS)

    Within the framework of innovative neutronic conception of Pressurized Light Water Reactors (PWR) of 3. generation, saving of natural resources is of paramount importance for sustainable nuclear energy production. This study consists in the one hand to design high Conversion Reactors exploiting mixed oxide fuels composed of thorium/uranium/plutonium, and in the other hand, to elaborate multi-recycling strategies of both plutonium and 233U, in order to maximize natural resources economy. This study has two main objectives: first the design of High Conversion PWR (HCPWR) with mixed oxide fuels composed of thorium/uranium/plutonium, and secondly the setting up of multi-recycling strategies of both plutonium and 233U, to better natural resources economy. The approach took place in four stages. Two ways of introducing thorium into PWR have been identified: the first is with low moderator to fuel volume ratios (MR) and ThPuO2 fuel, and the second is with standard or high MR and ThUO2 fuel. The first way led to the design of under-moderated HCPWR following the criteria of high 233U production and low plutonium consumption. This second step came up with two specific concepts, from which multi-recycling strategies have been elaborated. The exclusive production and recycling of 233U inside HCPWR limits the annual economy of natural uranium to approximately 30%. It was brought to light that the strong need in plutonium in the HCPWR dedicated to 233U production is the limiting factor. That is why it was eventually proposed to study how the production of 233U within PWR (with standard MR), from 2020. It was shown that the anticipated production of 233U in dedicated PWR relaxes the constraint on plutonium inventories and favours the transition toward a symbiotic reactor fleet composed of both PWR and HCPWR loaded with thorium fuel. This strategy is more adapted and leads to an annual economy of natural uranium of about 65%. (author)

  6. Minor Actinide Burning in Thermal Reactors. A Report by the Working Party on Scientific Issues of Reactor Systems

    International Nuclear Information System (INIS)

    The actinides (or actinoids) are those elements in the periodic table from actinium upwards. Uranium (U) and plutonium (Pu) are two of the principal elements in nuclear fuel that could be classed as major actinides. The minor actinides are normally taken to be the triad of neptunium (Np), americium (Am) and curium (Cm). The combined masses of the remaining actinides (i.e. actinium, thorium, protactinium, berkelium, californium, einsteinium and fermium) are small enough to be regarded as very minor trace contaminants in nuclear fuel. Those elements above uranium in the periodic table are known collectively as the transuranics (TRUs). The operation of a nuclear reactor produces large quantities of irradiated fuel (sometimes referred to as spent fuel), which is either stored prior to eventual deep geological disposal or reprocessed to enable actinide recycling. A modern light water reactor (LWR) of 1 GWe capacity will typically discharge about 20-25 tonnes of irradiated fuel per year of operation. About 93-94% of the mass of uranium oxide irradiated fuel is comprised of uranium (mostly 238U), with about 4-5% fission products and ∼1% plutonium. About 0.1-0.2% of the mass is comprised of neptunium, americium and curium. These latter elements accumulate in nuclear fuel because of neutron captures, and they contribute significantly to decay heat loading and neutron output, as well as to the overall radio-toxic hazard of spent fuel. Although the total minor actinide mass is relatively small - approximately 20-25 kg per year from a 1 GWe LWR - it has a disproportionate impact on spent fuel disposal, and thus the longstanding interest in transmuting these actinides either by fission (to fission products) or neutron capture in order to reduce their impact on the back end of the fuel cycle. The combined masses of the trace actinides actinium, thorium, protactinium, berkelium and californium in irradiated LWR fuel are only about 2 parts per billion, which is far too low for

  7. Burn-up calculation of different thorium-based fuel matrixes in a thermal research reactor using MCNPX 2.6 code

    Directory of Open Access Journals (Sweden)

    Gholamzadeh Zohreh

    2014-12-01

    Full Text Available Decrease of the economically accessible uranium resources and the inherent proliferation resistance of thorium fuel motivate its application in nuclear power systems. Estimation of the nuclear reactor’s neutronic parameters during different operational situations is of key importance for the safe operation of nuclear reactors. In the present research, thorium oxide fuel burn-up calculations for a demonstrative model of a heavy water- -cooled reactor have been performed using MCNPX 2.6 code. Neutronic parameters for three different thorium fuel matrices loaded separately in the modelled thermal core have been investigated. 233U, 235U and 239Pu isotopes have been used as fissile element in the thorium oxide fuel, separately. Burn-up of three different fuels has been calculated at 1 MW constant power. 135X and 149Sm concentration variations have been studied in the modelled core during 165 days burn-up. Burn-up of thorium oxide enriched with 233U resulted in the least 149Sm and 135Xe productions and net fissile production of 233U after 165 days. The negative fuel, coolant and void reactivity of the used fuel assures safe operation of the modelled thermal core containing (233U-Th O2 matrix. Furthermore, utilisation of thorium breeder fuel demonstrates several advantages, such as good neutronic economy, 233U production and less production of long-lived α emitter high radiotoxic wastes in biological internal exposure point of view

  8. W-007H B Plant Process Condensate Treatment Facility. Revision 3

    International Nuclear Information System (INIS)

    B Plant Process Condensate (BCP) liquid effluent stream is the condensed vapors originating from the operation of the B Plant low-level liquid waste concentration system. In the past, the BCP stream was discharged into the soil column under a compliance plan which expired January 1, 1987. Currently, the BCP stream is inactive, awaiting restart of the E-23-3 Concentrator. B Plant Steam Condensate (BCS) liquid effluent stream is the spent steam condensate used to supply heat to the E-23-3 Concentrator. The tube bundles in the E-23-3 Concentrator discharge to the BCS. In the past, the BCS stream was discharged into the soil column. Currently, the BCS stream is inactive. This project shall provide liquid effluent systems (BCP/BCS/BCE) capable of operating for a minimum of 20 years, which does not include the anticipated decontamination and decommissioning (D and D) period

  9. Optimization of small long-life PWR based on thorium fuel

    Energy Technology Data Exchange (ETDEWEB)

    Subkhi, Moh Nurul, E-mail: nsubkhi@students.itb.ac.id [Nuclear Physics and Biophysics Research Group, Faculty of Mathematics and Natural Science, Bandung Institute of Technology. Jalan Ganesha 10, Bandung (Indonesia); Physics Dept., Faculty of Science and Technology, State Islamic University of Sunan Gunung Djati Bandung Jalan A.H Nasution 105 Bandung (Indonesia); Suud, Zaki, E-mail: szaki@fi.itb.ac.id; Waris, Abdul; Permana, Sidik [Nuclear Physics and Biophysics Research Group, Faculty of Mathematics and Natural Science, Bandung Institute of Technology. Jalan Ganesha 10, Bandung (Indonesia)

    2015-09-30

    A conceptual design of small long-life Pressurized Water Reactor (PWR) using thorium fuel has been investigated in neutronic aspect. The cell-burn up calculations were performed by PIJ SRAC code using nuclear data library based on JENDL 3.2, while the multi-energy-group diffusion calculations were optimized in three-dimension X-Y-Z geometry of core by COREBN. The excess reactivity of thorium nitride with ZIRLO cladding is considered during 5 years of burnup without refueling. Optimization of 350 MWe long life PWR based on 5% {sup 233}U & 2.8% {sup 231}Pa, 6% {sup 233}U & 2.8% {sup 231}Pa and 7% {sup 233}U & 6% {sup 231}Pa give low excess reactivity.

  10. W-007H B Plant Process Condensate Treatment Facility. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Rippy, G.L.

    1995-01-20

    B Plant Process Condensate (BCP) liquid effluent stream is the condensed vapors originating from the operation of the B Plant low-level liquid waste concentration system. In the past, the BCP stream was discharged into the soil column under a compliance plan which expired January 1, 1987. Currently, the BCP stream is inactive, awaiting restart of the E-23-3 Concentrator. B Plant Steam Condensate (BCS) liquid effluent stream is the spent steam condensate used to supply heat to the E-23-3 Concentrator. The tube bundles in the E-23-3 Concentrator discharge to the BCS. In the past, the BCS stream was discharged into the soil column. Currently, the BCS stream is inactive. This project shall provide liquid effluent systems (BCP/BCS/BCE) capable of operating for a minimum of 20 years, which does not include the anticipated decontamination and decommissioning (D and D) period.

  11. Spin coating and plasma process for 2.5D integrated photonics on multilayer polymers

    International Nuclear Information System (INIS)

    Polymer spin coating, surface plasma treatment and selective UV-lithography processes have been developed to realize 2.5D photonic micro-resonators, made of disk- or ring-shaped upper rib waveguides, using common polymers such as SU8 (biphenol A ether glycidyl), PS233 (polymeric silane) and SOG (siloxane Spin on Glass). Both oxygen and argon plasma treatments, applied to PS233 and SOG before spin-coating the SU8, improve substantially the grip of multilayer devices (SU8 / PS233 or SU8 / SOG). Surface energy components derived from contact angle measurements have been used to optimize the processing conditions. In such integrated photonic devices, the both single-electromagnetic-modes called transverse electric (TE00) and transverse magnetic (TM00) have been excited in a SU8 micro-disk, with a single mode propagation strongly localized near the edge of the disk (i.e. the so called whispering gallery modes)

  12. A chromatographic separation of neptunium and protactinium using 1-octanol impregnated onto a solid phase support

    International Nuclear Information System (INIS)

    We have developed a new chromatographic method to efficiently separate and isolate neptunium (Np) and protactinium (Pa), based on the selective extraction of protactinium by primary alcohols. The effectiveness of the new technology is demonstrated by efficient separation of 233Pa from parent radionuclide 237Np, using a hydrochloric acid mobile-phase medium. Our new approach reproducibly isolated 233Pa tracer with a yield of 99 ± 1 % (n = 3; radiochemical purity 100 %) and enabled chemical recovery of 237Np parent material of 92 ± 3 % (radiochemical [99 %) for future 233Pa tracer preparations. Compared to previous methods, the new approach reduces radioactive inorganic and organic waste; simplifies the separation process by eliminating cumbersome liquid-liquid extractions; and allows isolation of radiochemically-pure fractions in less than 1 h. (author)

  13. Antineutrino Monitoring of Thorium Reactors

    CERN Document Server

    Akindele, Oluwatomi A; Norman, Eric B

    2015-01-01

    Various groups have demonstrated that antineutrino monitoring can be successful in assessing the plutonium content in water-cooled nuclear reactors for nonproliferation applications. New reactor designs and concepts incorporate nontraditional fuels types and chemistry. Understanding how these properties affect the antineutrino emission from a reactor can extend the applicability of antineutrino monitoring.Thorium molten salt reactors (MSR) breed U-233, that if diverted constitute an IAEA direct use material. The antineutrino spectrum from the fission of U-233 has been determined, the feasibility of detecting the diversion of a significant quantity, 8 kg of U-233, within the IAEA timeliness goal of 30 days has been evaluated. The antineutrino emission from a thorium reactor operating under normal conditions is compared to a diversion scenario at a 25 meter standoff by evaluating the daily antineutrino count rate and the energy spectrum of the detected antineutrinos. It was found that the diversion of a signifi...

  14. 3种有机硅助剂对2种水性化农药制剂的增效作用%Synergistic Effect of Three Organosilicon Surfactants on Two Waterborne Pesticide Formulations

    Institute of Scientific and Technical Information of China (English)

    许勇华; 胡冬松; 高云英; 袁静; 朱卫刚; 陈杰

    2011-01-01

    To assess the effect of organosilicon surfactant on pesticide formulation, the bioactivity of two waterborne formulations (chlorpyrifos 30% EW and ZJ0712 SC) with three organosilicon surfactants (S233, S240, FGM683) were determined by means of bioassay in laboratory. The results showed that the bioactivity of formulation containing organosilicon surfactants was superior to the formulation without it adding different organosilicon surfactants had different activities. Among three organosilicon surfactants, the synergistic effects of S233 and S240 were obvious, S233 was best.%为评价有机硅助剂对2种水性化农药制剂生物活性的影响,采用室内生物测定,以不含有机硅助剂的制剂为对照,对分别添加有机硅助剂S233、S240、FGM683的30%毒死蜱水乳剂和10%苯醚菌酯悬浮剂室内活性进行了测定.结果表明,3种有机硅助剂对2种水性化制剂的生物活性均具有不同程度的影响,添加有机硅助剂的制剂,其室内活性几乎都高于未添加有机硅助剂的制剂,且添加不同的有机硅助剂,室内活性有较大差异,其中有机硅助剂S233和FGM683的增效作用较为明显,且S233效果最好.

  15. An organization of the thorium fuel cycle start on the basis of fast reactors with spherical fuel elements of the small size

    International Nuclear Information System (INIS)

    The possibility of the organization of thorium fuel cycle start by means of conversion of high background plutonium into isotopically pure Uranium 233 into the highly stressed breeders with the fuel in the form of spherical fuel elements has been studied. A high efficiency of usage of compact plutonium fuel in the form of spherical fuel elements for its transmutation into low background Uranium 233 has been shown as a result of the revealed temporary regularities in the main characteristic behaviour of the reactors of such a type. (authors). 7 refs., 2 figs., 1 tab

  16. The Star Chromatic Numbers of Some Planar Graphs Derived from Wheels

    Institute of Scientific and Technical Information of China (English)

    LI De Ming

    2002-01-01

    The notion of the star chromatic number of a graph is a generalization of the chromaticnumber. In this paper, we calculate the star chromatic numbers of three infinite families of planargraphs. The first two families are derived from a 3-or 5-wheel by subdivisions, their star chromaticnumbers being 2+2/(2n + 1), 2+3/(3n + 1) and 2+3/(3n - 1), respectively. The third family of planargraphs are derived from n odd wheels by Hajos construction with star chromatic numbers 3 + 1/n,which is a generalization of one result of Gao et al.

  17. Radiological impact assessment for near surface disposal of thorium waste

    International Nuclear Information System (INIS)

    Thorium (232Th) itself is not fissile and so is not directly usable in a thermal neutron reactor. However, it is fertile and upon absorbing a neutron will transmute to uranium-233 (233U), which is a fissile fuel material. The thorium fuel fabrication may lead to low level waste comprising of 232Th. This waste may be disposed of in the Near Surface Disposal Facility (NSDF). The very low probability event of leaching of the waste may lead to contamination of the groundwater system. This paper deals with the estimation of the radiological impact of thorium waste disposal in NSDF through groundwater drinking pathway using the Multiple Area Source Model (MASOM). (author)

  18. Preparation of targets for nuclear chemistry experiments at DANCE

    International Nuclear Information System (INIS)

    In this paper, we describe the separation chemistry and electrodepositions conducted for the preparation of 241Am, 243Am and 233U targets used for cross-section measurements at DANCE. Thick, adherent deposits were prepared using molecular plating from isopropyl alcohol solutions. Improved yields and thicknesses were observed for 241Am electrodeposition after the material was purified using TRU resin from Eichrom. Similarly, 233U deposits were improved after purification with an anion exchange column in 9 M HBr followed by purification using UTEVA resin from Eichrom. (author)

  19. PCR identification of bacteria in blood culture does not fit the daily workflow of a routine microbiology laboratory.

    Science.gov (United States)

    Karumaa, Santra; Kärpänoja, Pauliina; Sarkkinen, Hannu

    2012-03-01

    We have evaluated the GenoType blood culture assay (Hain Lifescience, Nehren, Germany) for the identification of bacteria in 233 positive blood cultures and assessed its suitability in the workflow of a routine microbiology laboratory. In 68/233 (29.2%) samples, the culture result could not be confirmed by the GenoType assay due to a lack of primers in the test, multiple organisms in the sample, or inconsistency with respect to the identification by culture. Although the GenoType blood culture assay gives satisfactory results for bacteria for which primers are available, there are difficulties in applying the test in the routine microbiology laboratory.

  20. 钍俘获反应率离线伽马测量方法%Thorium capture ratio determination throughγ-ray off-line method∗

    Institute of Scientific and Technical Information of China (English)

    羊奕伟; 刘荣; 严小松

    2013-01-01

      为了测定聚变-裂变反应堆模型钍包层中的钍俘获率以及钍–铀转化率,探索了一种新的钍活化离线γ测量法.利用测量232Th俘获反应产物233Th衰变链中233Pa衰变放出的311.98 keV特征γ射线,来反推计算并最终确定232Th(n,γ)233Th的反应率,测试实验中不确定度约6%(233Th/232Th量级为10−17情况下).详细介绍了此方法的背景和原理方法,并进行简单的校验实验,证明其能够较好地得到模拟装置中的俘获率.与瞬发γ测量法以及质谱分析法进行对比,本方法更适合用于聚变-裂变反应堆模型钍包层中的钍俘获率以及钍-铀转化率测量,并有望进一步测量其他相关参数.%To determine the thorium capture ratio and thorium-uranium conversion ratio in the thorium cladding of the fusion-fission reactor model, a new approach, activated thorium sample decay γ-ray off-line measurement, is introduced in this paper. This method is based on the measurement of the 311.98 keV characteristic decayγ-ray emitted by 233Pa which is produced through decay of 233Th, the capture product of 232Th. Then some reverse mathematic approach is brought in and finally the 232Th (n,γ) 233Th reaction ratio is determined, with an uncertainty of 6%in the test experiment (233Th/232Th under the order of magnitude 10−17). In the paper, we introduce the detail of the approach including the background, principle and the result of a simple test experiment which shows that this approach can work well in thorium capture ratio determination. Compared with promptγ-ray method and mass spectrometer method, this decayγ-ray off-line method has many advantages in determining the thorium capture ratio and thorium-uranium conversion ratio in the thorium cladding. It is also promising in the measurement of other relevant parameters.

  1. Criticality safety studies of Building 3019 Cell 4 and in-line storage wells

    International Nuclear Information System (INIS)

    New fissile material load limits for storage facilities located in Building 3019 are derived in a manner consistent with currently applicable Martin Marietta Energy Systems requirements. The limits for 233U loading are 2.00, 1.80, 1.45, and 0.19 kg/ft for hydrogen-to-233U atoms ratios of 3, 5, 10, and unrestricted, respectively. Limits were also found for 235U and 239Pu systems. The KENO-Va Monte Carlo Program and Hansen-Roach cross sections were used to derive these limits

  2. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the E. I. Du Pont de Nemours and Co. , Deepwater, New Jersey. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-12-01

    The results of a radiological survey of the E. I. Du Pont Company, Deepwater, New Jersey, are presented in this report. During the 1940's this site was used for development of a process for the conversion of uranium oxide to produce uranium tetrafluoride and small quantities of uranium metal. The survey included measurements of the following: residual alpha and beta--gamma contamination levels, both fixed and transferable, in the one remaining uranium tetrafluoride operations building; external gamma radiation levels at 1 m above the surface inside this building and at outdoor locations where radioactive materials were handled; radon and radon daughter concentrations in the air in the operations building; uranium, radium, actinium, and thorium concentrations in soil and water on and near the site; and the airborne concentrations of uranium, thorium, and radium in the operations building. Elevated concentrations of uranium were found in residues from the operations building and in some surface and subsurface soil samples. Alpha and beta--gamma contamination levels in some areas of the operations building were above the limits of current federal guidelines set for the release of property for unrestricted use. 18 figures, 11 tables.

  3. Ac, La, and Ce radioimpurities in {sup 225}Ac produced in 40-200 MeV proton irradiations of thorium

    Energy Technology Data Exchange (ETDEWEB)

    Engle, Jonathan W.; Ballard, Beau D. [Los Alamos National Laboratory, NM (United States); Weidner, John W. [Air Force Institute of Technology, Wright Patterson Air Force Base, OH (United States); and others

    2014-10-01

    Accelerator production of {sup 225}Ac addresses the global supply deficiency currently inhibiting clinical trials from establishing {sup 225}Ac's therapeutic utility, provided that the accelerator product is of sufficient radionuclidic purity for patient use. Two proton activation experiments utilizing the stacked foil technique between 40 and 200 MeV were employed to study the likely co-formation of radionuclides expected to be especially challenging to separate from {sup 225}Ac. Foils were assayed by nondestructive γ-spectroscopy and by α-spectroscopy of chemically processed target material. Nuclear formation cross sections for the radionuclides {sup 226}Ac and {sup 227}Ac as well as lower lanthanide radioisotopes {sup 139}Ce, {sup 141}Ce, {sup 143}Ce, and {sup 140}La whose elemental ionic radii closely match that of actinium were measured and are reported. The predictions of the latest MCNP6 event generators are compared with measured data, as they permit estimation of the formation rates of other radionuclides whose decay emissions are not clearly discerned in the complex spectra collected from {sup 232}Th(p,x) fission product mixtures. (orig.)

  4. Pulse-shape discrimination and energy quenching of alpha particles in Cs$_2$LiLaBr$_6$:Ce$^{3+}$

    CERN Document Server

    Mesick, Katherine E; Stonehill, Laura C

    2016-01-01

    Cs$_2$LiLaBr$_6$:Ce$^{3+}$ (CLLB) is an elpasolite scintillator that offers excellent linearity and gamma-ray energy resolution and sensitivity to thermal neutrons with the ability to perform pulse-shape discrimination (PSD) to distinguish gammas and neutrons. Our investigation of CLLB has indicated the presence of intrinsic radioactive alpha background that we have determined to be from actinium contamination of the lanthanum component. We measured the pulse shapes for gamma, thermal neutron, and alpha events and determined that PSD can be performed to separate the alpha background with a moderate figure of merit of 0.98. We also measured the electron-equivalent-energy of the alpha particles in CLLB and simulated the intrinsic alpha background from $^{227}$Ac to determine the quenching factor of the alphas. A linear quenching relationship $L_{\\alpha} = E_{\\alpha} \\times q + L_0$ was found at alpha particle energies above 5 MeV, with a quenching factor $q = 0.71$ MeVee/MeV and an offset $L_0 = - 1.19$ MeVee.

  5. An Ion Exchange Study of Possible Hydridized 5f Bonding in theActinides

    Energy Technology Data Exchange (ETDEWEB)

    Diamond, R.M.; Street, Jr., K.; Seaborg, G.T.

    1951-08-28

    A study has been made of the elution behavior of curium(III), americium(III), plutonium(III), actinium(III), plutonium(IV), neptunium(IV), uraniuM(IV), thorium(IV), neptunium(V), plutonium (VI), uranium (VI), lanthanum(III), cerium(III), europium(III), ytterbium(III), ytterium(III), strontium(II), barium(II), radium(II), cesium(I) with 3.2 M, 6.2 M, 9.3 M, and 12.2 M HCl solutions from Dowex-50 cation exchange resin columns. These elutions show that in high concentrations of hydrochloric acid the actinides form complex ions with chloride ion to a much greater extent than the lanthanides. The strengths of the tripositive actinide complex ions apparently go in the order plutonium > americium> curium, although their ionic radii also decrease in this same order. To explain these results, a partial covalent character may be ascribed to the bonding in the transuranium complex ions. It is shown that a reasonable structure for such covalent bonding involves hybridization of the 5f orbitals in the actinide elements.

  6. Extending the north-east limit of the chart of nuclides

    CERN Document Server

    Benlliure, J; Kurtukian-Nieto, T; Schmidt, K -H; Audouin, L; Blank, B; Becker, F; Casarejos, E; Cortina-Gil, D; Enqvist, T; Fernández, B; Fernández-Ordóñez, M; Giovinazzo, J; Henzlova, D; Junghans, A R; Jurado, B; Napolitani, P; Pereira, J; Rejmund, F; Yordanov, O

    2010-01-01

    The existence of nuclei with exotic combinations of protons and neutrons provides fundamental information on the forces acting between nucleons. The maximum number of neutrons a given number of protons can bind, neutron drip line1, is only known for the lightest chemical elements, up to oxygen. For heavier elements, the larger its atomic number, the farther from this limit is the most neutron-rich known isotope. The properties of heavy neutron-rich nuclei also have a direct impact on understanding the observed abundances of chemical elements heavier than iron in our Universe. Above half of the abundances of these elements are thought to be produced in rapid-neutron capture reactions, r-process, taking place in violent stellar scenarios2 where heavy neutron-rich nuclei, far beyond the ones known up today, are produced. Here we present a major step forward in the production of heavy neutron-rich nuclei: the discovery of 73 new neutron-rich isotopes of chemical elements between tantalum (Z=72) and actinium (Z=89...

  7. Liquid Scintillation Counting of Environmental Radioisotopes: A Review of the Impact of Background Reduction

    Energy Technology Data Exchange (ETDEWEB)

    Douglas, Matthew; Bernacki, Bruce E.; Erchinger, Jennifer L.; Finn, Erin C.; Fuller, Erin S.; Hoppe, Eric W.; Keillor, Martin E.; Morley, Shannon M.; Mullen, Crystal A.; Orrell, John L.; Panisko, Mark E.; Warren, Glen A.; Wright, Michael E.

    2016-03-09

    Liquid scintillation counting (LSC) is a versatile and commonplace method for radiometric measurement of charged particle emitting radionuclides. The LSC method provides utility in a range of environmental science applications including hydrological studies of water transport, anthropogenic releases of radionuclides into the environment, and vertical mixing rates within oceans. Instrumental measurement background is one limiting factor of radiometric measurement sensitivity. As part of the development of a custom low background LSC system located in a shallow underground laboratory at Pacific Northwest National Laboratory, a number of measurement applications of LSC have been considered and are summarized here. The focus is on determining which aspects of such measurements would gain the greatest benefit from the reduction of LSC backgrounds by a factor of 10-100 relative to values reported in the literature. Examples of benefits include lowering the minimum detectable activity, reducing the sample size required, and shortening the elapsed timeline of the processing and analysis sequence. In particular tritium, strontium, and actinium isotopes are examined as these isotopes cover a range of requirements related to the LSC measurement method (e.g., 3H: low energy; Sr: spectral deconvolution; Ac: alpha/beta discrimination).

  8. Development of an Ultra-Low Background Liquid Scintillation Counter for Trace Level Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Erchinger, Jennifer L.; Orrell, John L.; Aalseth, Craig E.; Bernacki, Bruce E.; Douglas, Matthew; Finn, Erin C.; Fuller, Erin S.; Keillor, Martin E.; Morley, Shannon M.; Mullen, Crystal A.; Panisko, Mark E.; Shaff, Sarah M.; Warren, Glen A.; Wright, Michael E.

    2015-09-01

    Low-level liquid scintillation counting (LSC) has been established as one of the radiation detection techniques useful in elucidating environmental processes and environmental monitoring around nuclear facilities. The Ultra-Low Background Liquid Scintillation Counter (ULB-LSC) under construction in the Shallow Underground Laboratory at Pacific Northwest National Laboratory aims to further reduce the MDAs and/or required sample processing. Through layers of passive shielding in conjunction with an active veto and 30 meters water equivalent overburden, the background reduction is expected to be 10 to 100 times below typical analytic low-background liquid scintillation systems. Simulations have shown an expected background of around 14 counts per day. A novel approach to the light collection will use a coated hollow light guide cut into the inner copper shielding. Demonstration LSC measurements will show low-energy detection, spectral deconvolution, and alpha/beta discrimination capabilities, from trials with standards of tritium, strontium-90, and actinium-227, respectively. An overview of the system design and expected demonstration measurements will emphasize the potential applications of the ULB-LSC in environmental monitoring for treaty verification, reach-back sample analysis, and facility inspections.

  9. Purification of lanthanides for double beta decay experiments

    Energy Technology Data Exchange (ETDEWEB)

    Polischuk, O. G. [Institute for Nuclear Research, MSP 03680 Kyiv, Ukraine and INFN, Section of Rome, La Sapienza, I-00185 Rome (Italy); Barabash, A. S. [Institute of Theoretical and Experimental Physics, 117259 Moscow (Russian Federation); Belli, P. [INFN, Section of Rome Tor Vergata, I-00133 Rome (Italy); Bernabei, R. [INFN, Section of Rome Tor Vergata, I-00133 Rome, Italy and Department of Physics, University of Rome Tor Vergata, I-00133 Rome (Italy); Boiko, R. S.; Danevich, F. A.; Mokina, V. M.; Poda, D. V.; Tretyak, V. I. [Institute for Nuclear Research, MSP 03680 Kyiv (Ukraine); Cappella, F.; Incicchitti, A. [INFN, Section of Rome La Sapienza, I-00185 Rome, Italy and Department of Physics, University of Rome La Sapienza, I-00185 Rome (Italy); Cerulli, R.; Laubenstein, M.; Nisi, S. [INFN, Gran Sasso National Laboratories, I-67100 Assergi (Aq) (Italy)

    2013-08-08

    There are several potentially double beta active isotopes among the lanthanide elements. However, even high purity grade lanthanide compounds contain {sup 238}U, {sup 226}Ra and {sup 232,228}Th typically on the level of ∼ (0.1 - 1) Bq/kg. The liquid-liquid extraction technique was used to remove traces of U, Ra and Th from CeO{sub 2}, Nd{sub 2}O{sub 3} and Gd{sub 2}O{sub 3}. The radioactive contamination of the samples before and after the purification was tested by using ultra-low-background HPGe γ spectrometry at the underground Gran Sasso National Laboratories of the INFN (Italy). After the purification the radioactive contamination of gadolinium oxide by Ra and Th was decreased at least one order of magnitude. The efficiency of the approach to purify cerium oxide from Ra was on same level, while the radioactive contamination of neodymium sample before and after the purification is below the sensitivity of analytical methods. The purification method is much less efficient for chemically very similar radioactive elements like lanthanum, lutetium and actinium. R and D of the methods to remove the pollutions with improved efficiency is in progress.

  10. Radium-228 determination of natural waters via concentration on manganese dioxide and separation using Diphonix ion exchange resin.

    Science.gov (United States)

    Nour, S; El-Sharkawy, A; Burnett, W C; Horwitz, E P

    2004-12-01

    The objective of this work was to establish a new procedure for 228Ra determination of natural waters via preconcentration of radium on MnO2 and separation of its daughter, 228Ac, using Diphonix ion exchange resin. Following removal of potential interferences via passage through an initial Diphonix Resin column, the first daughter of 228Ra, 228Ac, is isolated by chromatographic separation via a second Diphonix column. A holding time of > 30 h for 228Ac ingrowth in between the two column separations ensures secular equilibrium. Barium-133 is used as a yield tracer. Actinium-228 is eluted from the second Diphonix Resin with 5 ml 1M 1-Hydroxyethane-1,1-diphosphonic acid (HEDPA) and quantified by addition of scintillation cocktail and LSC counting. Radium (and 133Ba) from the load and rinse solutions from the 2nd Diphonix column may be prepared for alpha spectrometry (for determination of 223Ra, 224Ra, and 226Ra) by BaSO4 microprecipitation and filtration. Decontamination tests indicate that U, Th, and Ra series nuclides do not interfere with these measurements, although high contents of 90Sr (90Y) require additional treatment for accurate measurement of 228Ra. Addition of stable Sr as a "hold back" carrier during the initial MnO2 preconcentration step was shown to remove most 90Sr interference.

  11. Soil and river sediments radionuclides monitoring at Aramar Experimental Center: an historical overview

    Energy Technology Data Exchange (ETDEWEB)

    Segre, Nadia; Fagundes, Rosane Correa, E-mail: nadia.segre@ctmsp.mar.mil.br [Centro Tecnologico da Marinha (CTM-SP/CEA/LARE), Ipero, SP (Brazil). Centro Experimental Aramar. Lab. Radioecologico; Moraes, Marco Antonio P.V. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    In order to evaluate possible effects to the environment resulting from the implementation of the Centro Tecnologico da Marinha - Centro Experimental Aramar (CTMSP-CEA) at Ipero in Sao Paulo state, Brazil, which came into operation in 1989, an Environmental Monitoring Program (PMA) was established in October, 1987. One of the aims of this program is to monitor the soil and river sediments radionuclides levels at CEA and beyond its boundary. The utilization of statistical tools to evaluate the results of radiometric environmental monitoring is a procedure required by National Nuclear Energy Commission (CNEN). The box plot is a simple statistical tool for displaying data. The central tendency and dispersion of the results as well as the observation of unusual results (outliers) in the dataset are easily visualized. Control chart is a graph that maps data and provides a picture of how a process is performing over time. A control chart always has a central line for the mean, an upper line for the upper control limit and a lower line for the lower control limit. Box plots and control charts were used to visualize the annual amount of natural uranium, lead-214, actinium-228 and lead-212 in soil and river sediment detected between 1987 and 2011, considering the measurements of all monitored places each year. This historical observation shows that, in average, the results obtained are below than the 1987-1988 levels (CEA's pre-operational) or below than the backgrounds radionuclides values. (author)

  12. Background radiation and individual dosimetry in the costal area of Tamil Nadu, India.

    Science.gov (United States)

    Matsuda, Naoki; Brahmanandhan, G M; Yoshida, Masahiro; Takamura, Noboru; Suyama, Akihiko; Koguchi, Yasuhiro; Juto, Norimichi; Raj, Y Lenin; Winsley, Godwin; Selvasekarapandian, S

    2011-07-01

    South coast of India is known as the high-level background radiation area (HBRA) mainly due to beach sands that contain natural radionuclides as components of the mineral monazite. The rich deposit of monazite is unevenly distributed along the coastal belt of Tamil Nadu and Kerala. An HBRA site that laid in 2×7 m along the sea was found in the beach of Chinnavillai, Tamil Nadu, where the maximum ambient dose equivalent reached as high as 162.7 mSv y(-1). From the sands collected at the HBRA spot, the high-purity germanium semi-conductor detector identified six nuclides of thorium series, four nuclides of uranium series and two nuclides belonging to actinium series. The highest radioactivity observed was 43.7 Bq g(-1) of Th-228. The individual dose of five inhabitants in Chinnavillai, as measured by the radiophotoluminescence glass dosimetry system, demonstrated the average dose of 7.17 mSv y(-1) ranging from 2.79 to 14.17 mSv y(-1).

  13. DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS

    Energy Technology Data Exchange (ETDEWEB)

    NA

    2004-11-22

    The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this modeling activity is to predict dissolved concentrations or solubility limits for 14 elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) important to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are in the form of tabulated functions with pH and log (line integral) CO{sub 2} as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. The output data from this report are fundamental inputs for Total System Performance Assessment for the License Application (TSPA-LA) to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for all of the actinides. These models cover broad ranges of environmental conditions so that they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or otherwise addressed.

  14. A Critical Review of Alpha Radionuclide Therapy-How to Deal with Recoiling Daughters?

    Science.gov (United States)

    de Kruijff, Robin M; Wolterbeek, Hubert T; Denkova, Antonia G

    2015-01-01

    This review presents an overview of the successes and challenges currently faced in alpha radionuclide therapy. Alpha particles have an advantage in killing tumour cells as compared to beta or gamma radiation due to their short penetration depth and high linear energy transfer (LET). Touching briefly on the clinical successes of radionuclides emitting only one alpha particle, the main focus of this article lies on those alpha-emitting radionuclides with multiple alpha-emitting daughters in their decay chain. While having the advantage of longer half-lives, the recoiled daughters of radionuclides like 224Ra (radium), 223Ra, and 225Ac (actinium) can do significant damage to healthy tissue when not retained at the tumour site. Three different approaches to deal with this problem are discussed: encapsulation in a nano-carrier, fast uptake of the alpha emitting radionuclides in tumour cells, and local administration. Each approach has been shown to have its advantages and disadvantages, but when larger activities need to be used clinically, nano-carriers appear to be the most promising solution for reducing toxic effects, provided there is no accumulation in healthy tissue. PMID:26066613

  15. A Critical Review of Alpha Radionuclide Therapy—How to Deal with Recoiling Daughters?

    Science.gov (United States)

    de Kruijff, Robin M.; Wolterbeek, Hubert T.; Denkova, Antonia G.

    2015-01-01

    This review presents an overview of the successes and challenges currently faced in alpha radionuclide therapy. Alpha particles have an advantage in killing tumour cells as compared to beta or gamma radiation due to their short penetration depth and high linear energy transfer (LET). Touching briefly on the clinical successes of radionuclides emitting only one alpha particle, the main focus of this article lies on those alpha-emitting radionuclides with multiple alpha-emitting daughters in their decay chain. While having the advantage of longer half-lives, the recoiled daughters of radionuclides like 224Ra (radium), 223Ra, and 225Ac (actinium) can do significant damage to healthy tissue when not retained at the tumour site. Three different approaches to deal with this problem are discussed: encapsulation in a nano-carrier, fast uptake of the alpha emitting radionuclides in tumour cells, and local administration. Each approach has been shown to have its advantages and disadvantages, but when larger activities need to be used clinically, nano-carriers appear to be the most promising solution for reducing toxic effects, provided there is no accumulation in healthy tissue. PMID:26066613

  16. A Critical Review of Alpha Radionuclide Therapy—How to Deal with Recoiling Daughters?

    Directory of Open Access Journals (Sweden)

    Robin M. de Kruijff

    2015-06-01

    Full Text Available This review presents an overview of the successes and challenges currently faced in alpha radionuclide therapy. Alpha particles have an advantage in killing tumour cells as compared to beta or gamma radiation due to their short penetration depth and high linear energy transfer (LET. Touching briefly on the clinical successes of radionuclides emitting only one alpha particle, the main focus of this article lies on those alpha-emitting radionuclides with multiple alpha-emitting daughters in their decay chain. While having the advantage of longer half-lives, the recoiled daughters of radionuclides like 224Ra (radium, 223Ra, and 225Ac (actinium can do significant damage to healthy tissue when not retained at the tumour site. Three different approaches to deal with this problem are discussed: encapsulation in a nano-carrier, fast uptake of the alpha emitting radionuclides in tumour cells, and local administration. Each approach has been shown to have its advantages and disadvantages, but when larger activities need to be used clinically, nano-carriers appear to be the most promising solution for reducing toxic effects, provided there is no accumulation in healthy tissue.

  17. Tumor Immunotargeting Using Innovative Radionuclides

    Directory of Open Access Journals (Sweden)

    Françoise Kraeber-Bodéré

    2015-02-01

    Full Text Available This paper reviews some aspects and recent developments in the use of antibodies to target radionuclides for tumor imaging and therapy. While radiolabeled antibodies have been considered for many years in this context, only a few have reached the level of routine clinical use. However, alternative radionuclides, with more appropriate physical properties, such as lutetium-177 or copper-67, as well as alpha-emitting radionuclides, including astatine-211, bismuth-213, actinium-225, and others are currently reviving hopes in cancer treatments, both in hematological diseases and solid tumors. At the same time, PET imaging, with short-lived radionuclides, such as gallium-68, fluorine-18 or copper-64, or long half-life ones, particularly iodine-124 and zirconium-89 now offers new perspectives in immuno-specific phenotype tumor imaging. New antibody analogues and pretargeting strategies have also considerably improved the performances of tumor immunotargeting and completely renewed the interest in these approaches for imaging and therapy by providing theranostics, companion diagnostics and news tools to make personalized medicine a reality.

  18. Tumor immunotargeting using innovative radionuclides.

    Science.gov (United States)

    Kraeber-Bodéré, Françoise; Rousseau, Caroline; Bodet-Milin, Caroline; Mathieu, Cédric; Guérard, François; Frampas, Eric; Carlier, Thomas; Chouin, Nicolas; Haddad, Ferid; Chatal, Jean-François; Faivre-Chauvet, Alain; Chérel, Michel; Barbet, Jacques

    2015-01-01

    This paper reviews some aspects and recent developments in the use of antibodies to target radionuclides for tumor imaging and therapy. While radiolabeled antibodies have been considered for many years in this context, only a few have reached the level of routine clinical use. However, alternative radionuclides, with more appropriate physical properties, such as lutetium-177 or copper-67, as well as alpha-emitting radionuclides, including astatine-211, bismuth-213, actinium-225, and others are currently reviving hopes in cancer treatments, both in hematological diseases and solid tumors. At the same time, PET imaging, with short-lived radionuclides, such as gallium-68, fluorine-18 or copper-64, or long half-life ones, particularly iodine-124 and zirconium-89 now offers new perspectives in immuno-specific phenotype tumor imaging. New antibody analogues and pretargeting strategies have also considerably improved the performances of tumor immunotargeting and completely renewed the interest in these approaches for imaging and therapy by providing theranostics, companion diagnostics and news tools to make personalized medicine a reality. PMID:25679452

  19. Rutherford's curriculum vitae, 1894-1907.

    Science.gov (United States)

    Cohen, M

    1995-06-01

    A single page, handwritten document was discovered when the Macdonald Physics building of McGill University in Montreal was gutted in 1978. This proved to be the draft of Ernest Rutherford's curriculum vitae (C.V.) covering the years 1894-1907, probably written in the autumn of 1906 when Rutherford was preparing to leave McGill. The C.V. contains 21 headings in chronological order, referring to research and other activities of Rutherford and his coauthors (especially Soddy and Barnes), plus a further set of headings relating to the associated investigations of Rutherford's team, including Eve and Hahn. A transcript of the document is provided, although in several places, Rutherford's handwriting is difficult to interpret, and the significance of his abbreviations is not always clear. Each of the items in the C.V. is discussed briefly in this review, in the light both of Rutherford's personal career and of the contribution of his team to the development and understanding of radioactivity. This contribution included the cause and nature of radioactivity (with Soddy), energy aspects of radioactive decay (with Barnes), elucidation of the uranium-radium, thorium and actinium series (Godlewski and Hahn), the radioactivity of the earth and atmosphere (Eve), the nature of the gamma rays (Eve) and, perhaps most important of all, the nature and properties of the alpha particle (Rutherford himself). The latter investigations led directly to Rutherford's later work in Manchester, including the nuclear model of the atom and artificial disintegration of the nucleus.

  20. Water masses and property distribution in the EEZ of Mauritius

    Digital Repository Service at National Institute of Oceanography (India)

    DeSousa, S.N.; Singbal, S.Y.S.; George, M.D.

    appears to be centred between 10 degrees and 13 degrees S lat., has low density lying between 22.9 and 23.3, low concentration of nutrients and high dissolved oxygen content (4.5-5.0 ml.l sup(-1)), and (2) a cold (temp. 25 degrees C) and less saline water...

  1. Acculturation, weight status, and eating habits among Chinese-American preschool children and their primary caregivers: A pilot study

    Science.gov (United States)

    This study investigated acculturation, eating habits, and weight status among 53 Chinese-American children and their primary caregivers. Caregivers’ mean acculturation score was 2.1, indicating low acculturation. Caregivers’ mean body mass index (BMI) was 23.3; 21% were overweight (BMI is greater ...

  2. Draft Genome Sequence of “Candidatus Liberibacter asiaticus” from Diaphorina citri in Guangdong, China

    OpenAIRE

    Wu, F.; Z. Zheng; Deng, X.; Cen, Y.; Liang, G; J. Chen

    2015-01-01

    The draft genome sequence of “Candidatus Liberibacter asiaticus” strain YCPsy from an Asian citrus psyllid (Diaphorina citri) in Guangdong, China, is reported here. The YCPsy strain has a genome size of 1,233,647 bp, 36.5% G+C content, 1,171 open reading frames (ORFs), and 53 RNAs.

  3. 77 FR 1941 - National Heart, Lung, and Blood Institute; Notice of Closed Meeting

    Science.gov (United States)

    2012-01-12

    ... Enhancement Grants for Stem Cell Research. Date: February 1, 2012. Time: 1 p.m. to 3 p.m. Agenda: To review... Domestic Assistance Program Nos. 93.233, National Center for Sleep Disorders Research; 93.837, Heart and Vascular Diseases Research; 93.838, Lung Diseases Research; 93.839, Blood Diseases and Resources...

  4. 76 FR 20358 - National Heart, Lung, and Blood Institute; Notice of Closed Meeting

    Science.gov (United States)

    2011-04-12

    ... Award for Stem Cell Research. Date: May 4, 2011. Time: 12:30 p.m. to 3 p.m. Agenda: To review and... Program Nos. 93.233, National Center for Sleep Disorders Research; 93.837, Heart and Vascular Diseases Research; 93.838, Lung Diseases Research; 93.839, Blood Diseases and Resources Research,...

  5. 78 FR 7795 - National Heart, Lung, and Blood Institute; Notice of Closed Meeting

    Science.gov (United States)

    2013-02-04

    ... grant application in rat embryonic stem cell lines. Date: February 21, 2013. Time: 1:00 p.m. to 3:00 p.m... . (Catalogue of Federal Domestic Assistance Program Nos. 93.233, National Center for Sleep Disorders Research; 93.837, Heart and Vascular Diseases Research; 93.838, Lung Diseases Research; 93.839, Blood...

  6. 75 FR 65498 - National Heart, Lung, and Blood Institute; Notice of Closed Meeting

    Science.gov (United States)

    2010-10-25

    ... Awards for Stem Cell Research. Date: November 10, 2010. Time: 12:30 p.m. to 3:30 p.m. Agenda: To review... Program Nos. 93.233, National Center for Sleep Disorders Research; 93.837, Heart and Vascular Diseases Research; 93.838, Lung Diseases Research; 93.839, Blood Diseases and Resources Research,...

  7. 77 FR 30542 - National Heart, Lung, and Blood Institute; Notice of Closed Meetings

    Science.gov (United States)

    2012-05-23

    ... Enhancement Grants for Stem Cell Research Date: June 13, 2012. Time: 1 p.m. to 4 p.m. Agenda: To review and... Federal Domestic Assistance Program Nos. 93.233, National Center for Sleep Disorders Research; 93.837, Heart and Vascular Diseases Research; 93.838, Lung Diseases Research; 93.839, Blood Diseases...

  8. Oxygen sensing and conducted vasomotor responses in mouse cremaster arterioles in situ

    DEFF Research Database (Denmark)

    Ngo, Thuc Anh; Jensen, Lars Jørn; Riemann, Mads Achen;

    2010-01-01

    to low or high oxygen. Induction of localized low (PO(2) = 23.3 +/- 5.7 mmHg) or high (PO(2) = 300.0 +/- 25.7 mm Hg) oxygen tension caused vasodilatation or -constriction locally and at a site 1,000 mum upstream (distantly). Glibenclamide blocker of ATP-sensitive K(+) channels inhibited vasodilatation...

  9. THERMAL MUONIUM IN VACUO FROM SILICA AEROGELS

    NARCIS (Netherlands)

    Schwarz, Willi; Ebert, Volker; Geerds, Hans; Jungmann, Klaus-Peter; Kirches, Stefan; Koppe, Stefan; Maas, Frank Ewald; Mundinger, Hans Juergen; zu Putlitz, Gisbert; Rosenkranz, Juergen; Schaefer, Willi; Schiff, Guenther; Zhang, Zhizhang; Boshier, MG; Hughes, V.W.

    1992-01-01

    Muonium atoms have been observed emerging into vacuum from silica aerogel surfaces with a thermal velocity distribution corresponding to a temperature of 298(10) K after stopping positive muons from a subsurface muon beam. Yields up to 2.3(3)% could be achieved for aerogel samples of 160 mg/cm3 dens

  10. 77 FR 51477 - 2012 Technical Corrections, Clarifying and Other Amendments to the Greenhouse Gas Reporting Rule...

    Science.gov (United States)

    2012-08-24

    ... centrifugal and reciprocating compressors. Amending 40 CFR 98.233(o)(7) to remove the word ``thousand'' in... emissions from centrifugal compressors (Equations W-23 and W-24) and reciprocating compressors (Equations W... is finalizing the amendments to both the centrifugal compressor and reciprocating compressor...

  11. Mars' radio spectrum and the flying dust.

    NARCIS (Netherlands)

    M. Roos-Serote; D.M. Stam; R.P. Fender

    2004-01-01

    Mars' radio spectrum at centimeter wavelengths is produced by thermal radiation from the surface and sub-surface. Observations at 2.8 cm made in the 1975 and 1978 show variations of its radio brightness as a function of longitude on the planet (Doherty et al. , ApJ 233, 1979). In addition, an overal

  12. Encyclopedia of Information Ethics and Security

    OpenAIRE

    Akbulut, Reviewed By Yavuz

    2008-01-01

    233Rapid developments in information andcommunication technologies have created newsecurity threats along with ethical dilemmas. Thesedevelopments have been so fast that appropriatesecurity precautions and ethical codes fail to keeppace with the technological developments. In thisrespect, education of both professionals andordinary citizens regarding information technologyethics carries utmost importance. Encyclopedia ofInformation Ethics and Security serves as anauthentic and comprehensive r...

  13. 76 FR 72189 - Notice of Proposed Information Collection Requests

    Science.gov (United States)

    2011-11-22

    .... Title of Collection: Teacher Education Assistance for College and Higher Education Grant (TEACH... Annual Responses: 233,276. Total Estimated Annual Burden Hours: 32,739. Abstract: The Teacher Education Assistance for College and Higher Education (TEACH) Grant program is a non-need-based grant program...

  14. A Process Analysis of the Transmission of Distress from Interparental Conflict to Parenting: Adult Relationship Security as an Explanatory Mechanism

    Science.gov (United States)

    Davies, Patrick T.; Sturge-Apple, Melissa L.; Woitach, Meredith J.; Cummings, E. Mark

    2009-01-01

    Toward advancing conceptualizations of the spillover hypothesis, this study examined the conditions and mechanisms underlying the transmission of distress from the interparental relationship to parenting difficulties over a 2-year period in a sample of 233 mothers (M = 35.0 years) and fathers (M = 36.8 years) of kindergarten children. Findings…

  15. Application of electrical resistivity prospecting in waste water management: A case study (Kharga Oasis, Egypt

    Directory of Open Access Journals (Sweden)

    M.I.I. Mohamaden

    2016-03-01

    The third layer represents the first Nubian Sandstone aquifer with moderate electrical resistivity values (23.9–233 ohm m detected at the maximum depth of penetration, a great contrast for values according to the lithological content.

  16. Optimisation of initial core of AHWR-LEU using burnable poison

    International Nuclear Information System (INIS)

    This paper focuses on the physics design optimisation of initial core of AHWR-LEU. Advanced Heavy Water Reactor (AHWR) being designed for 920 MWth, is a vertical pressure tube thorium-based reactor cooled by boiling light water and moderated by heavy water designed to maximise power production from thorium. The equilibrium fuel cycle is based on the conversion of naturally available thorium into fissile 233U driven by plutonium as external fissile feed. Plutonium is used as makeup fuel to achieve high discharge burnup and self-sustaining characteristics of Th-233U fuel cycle. The reactor would be operated in closed fuel cycle by recycling 233U back into the reactor. Physics design of AHWR offers considerable flexibility to accommodate different kinds of fuel cycles. Use of Low Enriched Uranium (LEU) fuel with thorium in AHWR has several attractive features like enhanced safe where all the reactivity coefficients are negative by design. The delayed neutron parameter β will be larger than the reference AHWR fuelled with (Th,Pu)MOX and (Th,233U) MOX and hence enhanced controllability. This fuel cycle would be operated in a once-through mode. The initial core will have large excess reactivity and will require large amount of neutron poison (boron) to be dissolved in moderator to quench this initial core excess reactivity. Generally, flux flattening is achieved by using differential enrichment in the central and outer region of the core. (author)

  17. Seed oil and fatty acid composition in Capsicum spp

    Science.gov (United States)

    The oil content and fatty acid composition of seed of 233 genebank accessions (total) of nine Capsicum species, and a single accession of Tubocapsicum anomalum, were determined. The physicochemical characteristics of oil extracted from seed of C. annuum and C. baccatum were also examined. Significan...

  18. Data of evolutionary structure change: 1ALCA-1VEDA [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1ALCA-1VEDA 1ALC 1VED A A KQFTKCELSQNL--YDIDGYGRIALPELICTMFHTSGYD...CA 233 THR CA 295 GLU CA 388 TYR CA 428 1VED... A 1VEDA ASP CA 290 1VED A 1VED... CA 249 GLU CA 193 GLN CA 219 TRP CA 312 1VED

  19. Reference: AUXREPSIAA4 [PLACE

    Lifescience Database Archive (English)

    Full Text Available AUXREPSIAA4 Ballas N, Wong LM, Theologis A Identification of the auxin-responsive e...lement, AuxRE, in the primary indoleacetic acid-inducible gene, PS-IAA4/5, of pea (Pisum sativum). J Mol Biol 233:580-596 (1993) PubMed: 8411166; GenBank: X68216; ...

  20. 75 FR 47059 - Notice To Rescind Notice of Intent To Prepare an Environmental Impact Statement: Warren County, IA

    Science.gov (United States)

    2010-08-04

    ... Statement: Warren County, IA AGENCY: Federal Highway Administration (FHWA), Iowa DOT, Warren County. ACTION... Division Office, 105 Sixth Street, Ames, IA 50010, Phone 515-233-7302; or James P. Rost, Director, Office of Location and Environment, Iowa Department of Transportation, 800 Lincoln Way, Ames, IA...

  1. 78 FR 72789 - Delegation of Authority Pursuant to Section 404(c) of the Child Soldiers Prevention Act of 2008...

    Science.gov (United States)

    2013-12-04

    ... From the Federal Register Online via the Government Publishing Office #0; #0; #0; Presidential Documents #0; #0; #0;#0;Federal Register / Vol. 78, No. 233 / Wednesday, December 4, 2013 /#0;#0; #0; #0;Title 3-- #0;The President ] Memorandum of August 2, 2013 Delegation of Authority Pursuant to Section 404(c) of the Child Soldiers Prevention Act of 2008, as...

  2. 76 FR 44496 - Hazardous Materials Transportation: Revisions of Special Permits Procedures; Response to Appeals...

    Science.gov (United States)

    2011-07-26

    ..., 2011, PHMSA issued a final rule under Docket Number PHMSA-2009-0410 (HM-233B) (76 FR 454) amending the... Transportation (44 FR 11034). Executive Orders 12866 and 13563 require agencies to regulate in the ``most cost... statement on PHMSAs website reads, ``We have been alerted of a potential phishing website not...

  3. Hypercoagulation Assessed by Thromboelastography is Neither Related to Infarct Size nor to Clinical Outcome After Primary Percutaneous Coronary Intervention

    DEFF Research Database (Denmark)

    Dridi, Nadia Paarup; Lønborg, Jacob T; Radu, Maria D;

    2014-01-01

    OBJECTIVES: We investigated the relationship between coagulation assessed by thromboelastography (TEG) and myocardial damage in ST-segment elevation myocardial infarction (STEMI). METHODS: We measured platelet activity with TEG-maximum amplitude (TEG-MA) in 233 patients undergoing urgent percutan...

  4. Can the possibility of some linkage of monsoonal precipitation with solar variability be ignored? Indications from foraminiferal proxy records

    Digital Repository Service at National Institute of Oceanography (India)

    Khare, N.; Nigam, R.

    sample and in cerebrally damaged patterns of thurin gia, G. D. R. (East Germany). J. Phys., Anthrop ., 1975, 42 , 233 ? 235. 5. Census of India, Series 2 ? Andhra Pradesh Part V - A, town dire c- t ion. Director of Census Operations, A n dhra...

  5. 10 CFR 150.17 - Submission to Commission of nuclear material status reports.

    Science.gov (United States)

    2010-01-01

    ..., special nuclear material in a quantity totaling one gram or more of contained uranium-235, uranium-233, or..., disposed of, or lost. This prescribed computer-readable report replaces the DOE/NRC Form 742 which has been... Material Balance Report. This prescribed computer-readable report replaces the DOE/NRC Form 742C which...

  6. 10 CFR 74.13 - Material status reports.

    Science.gov (United States)

    2010-01-01

    ... quantity totaling one gram or more of contained uranium-235, uranium-233, or plutonium shall complete and... computer-readable report replaces the DOE/NRC form 742 which has been previously submitted in paper form... prescribed computer-readable report replaces the DOE/NRC Form 742C which has been previously submitted...

  7. Fission-suppressed hybrid reactor: the fusion breeder

    International Nuclear Information System (INIS)

    Results of a conceptual design study of a 233U-producing fusion breeder are presented. The majority of the study was devoted to conceptual design and evaluation of a fission-suppressed blanket and to fuel cycle issues such as fuel reprocessing, fuel handling, and fuel management. Studies in the areas of fusion engineering, reactor safety, and economics were also performed

  8. Profiles of Motivated Self-Regulation in College Computer Science Courses: Differences in Major versus Required Non-Major Courses

    Science.gov (United States)

    Shell, Duane F.; Soh, Leen-Kiat

    2013-01-01

    The goal of the present study was to utilize a profiling approach to understand differences in motivation and strategic self-regulation among post-secondary STEM students in major versus required non-major computer science courses. Participants were 233 students from required introductory computer science courses (194 men; 35 women; 4 unknown) at…

  9. News

    Institute of Scientific and Technical Information of China (English)

    Celine; Yi

    2008-01-01

    China consumption in July hit 12-year high According to the statistics from National Bureau of Statistics of China, the retail sales of social consumer goods reached RMB 862.9 billion yuan in July,increased by 23.3% year on year and this is the highest record since February of 1996.Statistics

  10. 77 FR 17051 - Environmental Impacts Statements; Notice of Availability

    Science.gov (United States)

    2012-03-23

    ... Purple Line and Metro Red Line Heavy Rail Subway, Los Angeles County Metropolitan Transportation..., Calnev Pipeline Expansion Project, Construction, Operation, and Maintenance of a 233-mile Pipeline from... Project, Propose to Modify and Expand Existing Natural Gas Transmission Pipeline Systems in New...

  11. Respiratory System

    Institute of Scientific and Technical Information of China (English)

    2004-01-01

    7.1 Bronchial asthma2004362 The effects of anti-inflammatory and anti-asthmatic agents on CD34+ hematopoietic cells in bone marrow of asthmatic mice. MAO Hui(毛辉) ,et al. Dept Respir, West China Hosp, Sichuan Univ, Chengdu 610041. Chin J Tuberc Respir Dis 2004; 27 (4):229-233.

  12. Petroleum hydrocarbons in surface sediments in Kandla creek (Gujarat)

    Digital Repository Service at National Institute of Oceanography (India)

    Kadam, A.N.

    Petroleum hydrocarbons in the surface sediments were determined gravimetrically and spectroscopically to evaluate petroleum oil pollution in the Kandla creek. They ranged from 9.6 — 140.5 and 6.5 — 23.3 μg g-1 (wet wt.) respectively. Gas...

  13. Exposure to Community Violence and Protective and Risky Contexts among Low Income Urban African American Adolescents: A Prospective Study

    Science.gov (United States)

    Goldner, Jonathan; Peters, Tracy L.; Richards, Maryse H.; Pearce, Steven

    2011-01-01

    This study examined protective and risky companionship and locations for exposure to community violence among African American young adolescents living in high crime, urban areas. The Experience Sampling Method (ESM), an in vivo data collection method, was employed to gather information from 233 students (62% female) over 3 years, beginning in the…

  14. Becoming a Blood Stem Cell Donor

    Science.gov (United States)

    ... 3:22. CTV News 322 views 3:22 Stem Cell Therapy Injections - Duration: 6:18. Caring Medical Regenerative Medicine Clinics 254,233 views 6:18 Bone Marrow/Stem Cell Transplant - Duration: 7:24. tannermom80 106,911 views ...

  15. 76 FR 9755 - New England Fishery Management Council; Public Meeting

    Science.gov (United States)

    2011-02-22

    ... National Oceanic and Atmospheric Administration RIN: 0648-XA233 New England Fishery Management Council... Administration (NOAA), Commerce. ACTION: Notice; public meeting. SUMMARY: The New England Fishery Management...: (401) 739-3000; fax: (401) 732-9309. Council address: New England Fishery Management Council, 50...

  16. Being a Closely Spaced Second Child Is Not So Bad. Child-Spacing Effects on Intelligence, Personality, and Social Competence.

    Science.gov (United States)

    Nuttall, Ronald L.; Nuttall, Ena Vazquez

    This study focuses on the effects of family size and spacing on intellectual, social, and personality development of children. The sample consisted of 533 suburban, middle class, large family (five or more) and small two child family children. The children, 233 boys and 300 girls, were teenagers attending either junior or senior high school.…

  17. Report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    The information covers the operation of major licensed nuclear fuel manufacturers and research laboratories processing significant quantities of strategic SNM (5 kg 235U, 2 kg Pu or 233U) between Jan. 1, 1968 and Sept. 30, 1976. Fuel manufactured for commercial light water power reactors is not covered. The data presented are inventory differences (MUFs)

  18. Critical-Thinking Types among Nursing and Management Undergraduates.

    Science.gov (United States)

    Thorpe, Karran; Loo, Robert

    2003-01-01

    The short form of the Watson-Glaser Critical Thinking Appraisal was completed by 233 nursing and 131 management students, yielding four clusters of critical thinking types. Discriminant analysis using cluster membership and subtest scores showed 96% were correctly classified. (Contains 40 references) (SK)

  19. A Comparison of the Diagnostic Assessment for the Severely Handicapped-II (DASH-II) and the Aberrant Behavior Checklist (ABC).

    Science.gov (United States)

    Paclawskyj, Theodosia R.; Matson, Johnny L.; Bamburg, Jerald W.; Baglio, Christopher S.

    1997-01-01

    A study of 233 individuals with severe mental retardation examined the validity of the Diagnostic Assessment for the Severely Handicapped-II (DASH-II) through correlation with the Aberrant Behavior Checklist (ABC). DASH-II as a whole was found to have a high degree of convergent validity with the ABC total score. (CR)

  20. Data of evolutionary structure change: 1CTWA-1SX2A [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1CTWA-1SX2A 1CTW 1SX2 A A MNIFEMLRIDEGLRLKIYKDTEGYYTIGIGHLLTKSPSL...entryIDChain>1SX2A LRMLQ-KRWDE ure>HHHH - HHH...G CA 233 TRP CA 289 ASP CA 237 GLU CA 237 1CT...W A 1CTWA LRMLQQ...KRWDE ure>HHHHH HHHure>