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Sample records for californium 242

  1. Historical review of californium-252 discovery and development

    International Nuclear Information System (INIS)

    Stoddard, D.H.

    1985-01-01

    This paper discusses the discovery and history of californium 252. This isotope may be synthesized by irradiating plutonium 239, plutonium 242, americium 243, or curium 244 with neutrons in a nuclear reactor. Various experiments and inventions involving 252 Cf conducted at the Savannah River Plant are discussed. The evolution of radiotherapy using californium 252 is reviewed

  2. Californium-252

    International Nuclear Information System (INIS)

    1975-01-01

    This meeting constituted the third phase of a project initiated by the Dosimetry Section of the IAEA in 1973. The first step, early in 1973, consisted of the development of a programme for the loan of Cf-252 sources to the Member States in support of education, training and some limited research. To date, 14 institutions in 13 Member States have participated in this loan programme. In August last year, the Agency published an instructional syllabus and laboratory manual authored by Professors Eric J. Hall and Harald H. Rossi of Columbia University (Californium-252 in Teaching and Research, Technical Reports Series No. 159). The appearance of this publication, including guidance on the design and construction of a storage and use facility, was the second phase of this programme aimed at providing some support to potential users in the fields of radiation biology and dosimetry. The objective of the programme's third phase - the convening of an Educational Seminar - was to provide a forum to bring together participants in the Agency's loan programme and experts in various scientific fields. Specifically, the Seminar consisted of a series of expert presentations in spectrometry, activation and prompt gamma analyses, on-stream analysis, dosimetry, health physics, radiology and radiotherapy. (author)

  3. Magnetism in californium

    International Nuclear Information System (INIS)

    Moore, J.R.

    1988-03-01

    A SQUID-based magnetic susceptometer has been constructed for studying small radioactive samples at temperatures below 350 K and in magnetic fields up to 50 kilogauss. The device has been used to study californium (element 98) in a number of solid-state forms: the dhcp metal, several oxides (Cf 2 O 3 in both the bcc and monoclinic structures, Cf 7 O 12 , CfO 2 and BaCfO 3 ), several monopnictides (CfN, CfAs and CfSb) and the trichloride (in both the hexagonal and orthorhombic structures). All of these materials were studied in polycrystalline form, and hexagonal CfCl 3 was studied in single-crystal form as well. The susceptometer has the sensitivity to measure samples containing less than 10 micrograms of californium. The magnetic susceptibilities of all of the californium materials at temperatures above about 100 K are described well by the Curie-Weiss relationship. This behavior is consistent with the assumption that the magnetic 5f electrons are localized and that the paramagnetic behavior can be interpreted in terms of the properties of the free ion. The measured values of the effective paramagnetic moment, μ/sub eff/, for all the californium materials that were studied are reasonably consistent with theoretical values based on intermediate coupling models. All of the californium materials showed some indications of cooperative magnetic effects. The dhcp metal was observed to order ferromagnetically at 52 K, and all of the californium compounds studied showed signs of antiferromagnetic ordering, mostly at temperatures below 25 K. 91 refs., 50 figs., 19 tabs

  4. Medical applications of californium-252

    International Nuclear Information System (INIS)

    Oliver, G.D. Jr.

    1975-01-01

    Primarily, californium-252 sources have been utilized in medicine for the treatment of neoplastic lesions. For five years, a coordinated effort between several cancer research institutions and national laboratories has developed the necessary physics, radiobiology, and engineering skills to establish an evaluation program for californium. Several more years of combined effort are required before it is known whether californium therapy is as good as or better than conventional therapy with sources like radium. Recently, development of diagnostic applications of californium in medicine has received attention. Studies comparing neutron decay activation analysis versus prompt capture gamma ray analysis are in progress. A hopeful application of prompt analysis with reasonable quantities (200 μg) of californium is the elemental analysis of bone in the human body. (U.S.)

  5. Californium loan programme

    International Nuclear Information System (INIS)

    1974-01-01

    The offer of the United States to loan Californium-252 sources to the IAEA was made by Dr. Glenn T. Seaborg, then chairman of the USAEC, in his opening statement at the 15th. General Conference of the IAEA held in Vienna in 1971. The purpose of this loan was to make neutron emitting sources available to universities in the Member States for use in educational programmes. The sources, in the form of small needles designed for medical use in radiation therapy, were judged highly suitable for didactic applications due to their small size, limited activity and well documented radiological parameters. Subsequently, in May 1973, the Director General announced the availability of the Californium sources to the Member States. To date, numerous sources have been loaned to universities in Czechoslovakia, Costa Rica, the Federal Republic of Germany, Ghana, India, Iran, Israel, Japan, South Africa, Switzerland, the United Kingdom and Uruguay; additional applications for loans are being processed. It is anticipated that the loan programme will be terminated in 1975 once all the available sources have been distributed. n order to provide guidance for the Member States on the safe exploitation of these sources, a prototype use and storage facility was designed by IAEA staff of the Dosimetry Section of the Division of Life Sciences, and constructed at the IAEA laboratory in Seibersdorf, Austria. Figures 2-5 illustrate some of the details of this container, which is being given to the Ghana Nuclear Centre in support of a training programme for students at the university in Accra. Further advice to users of these sources will be provided by the publication of an instructional syllabus, a laboratory manual for experiments and the safety precautions inherent in the proper handling of neutron emitting radionuclides, authored by Professors Erich J. Hall and Harald H. Rossi of Columbia University. The syllabus and manual will be published as part of the IAEA Technical Series in September

  6. Californium source transfer

    International Nuclear Information System (INIS)

    Wallace, C.R.

    1995-01-01

    In early 1995, the receipt of four sealed californium-252 sources from Oak Ridge National Lab was successfully accomplished by a team comprised of Radiological Engineering, Radiological Operations and Health Physics Instrumentation personnel. A procedure was developed and walked-down by the participants during a Dry Run Evolution. Several special tools were developed during the pre-planning phases of the project which reduced individual and job dose to minimal levels. These included a mobile lifting device for attachment of a transfer ball valve assembly to the undercarriage of the Cannonball Carrier, a transfer tube elbow to ensure proper angle of the source transfer tube, and several tools used during emergency response for remote retrieval and handling of an unshielded source. Lessons were learned in the areas of contamination control, emergency preparedness, and benefits of thorough pre-planning, effectiveness of locally creating and designing special tools to reduce worker dose, and methods of successfully accomplishing source receipt evolutions during extreme or inclement weather

  7. Californium-252 progress, report No. 7, April 1971

    Energy Technology Data Exchange (ETDEWEB)

    1971-12-31

    This report contains discusses of the following topics on Californium-252: First sales of californium-252; encapsulation services discussed; three new participants in market evaluation program; summer training programs to use californium; Californium-252 shipping casks available; Californium-252 questions and answers, radiotherapy; neutron radiography; natural resources exploration; nuclear safeguards; process control; dosimetry; neutron radiography; neutron shielding; and nuclear safeguards.

  8. Uranium standards for Californium Shuffler

    International Nuclear Information System (INIS)

    Gibbs, A.; Boynton, S.P.

    1978-10-01

    The Laboratories Department analyzed pieces of a U-Al log which were to be canned and used as a set of standards for the nondestructive Californium Shuffler instrument. Evaluation of this instrument is part of an on-going Safeguards Program and is a joint project between LASL and SRP. A U-Al casting of a nominal 30% to 70% composition was made with enriched uranium (56 wt % 235 U). The log was 6 in. in diameter and approximately 2 ft long. A 1/4-in. slice was made before and after each 1-in. slice taken for use as a standard. The 1-in. slices were scanned nondestructively by collimated gamma pulse height analysis. The 1/4-in. slices were divided into quadrants and one quadrant for each slice was destructively analyzed. Results from these tests showed an approximate 1.5% relative variation in uranium concentration from the high to the low point. Successive pieces showed less than 1% relative difference. The 1-in. pieces have been canned and shipped to LASL for testing and will be returned with the Californium Shuffler. The remaining 1/4-in. slices have been sent to NBL and LASL for destructive analysis

  9. Radiography using californium-252 neutron sources

    International Nuclear Information System (INIS)

    Ray, J.W.

    1975-01-01

    The current status in the technology of neutron radiography using californium-252 neutron sources is summarized. Major emphasis is on thermal neutron radiography since it has the widest potential applicability at the present time. Attention is given to four major factors which affect the quality and useability of thermal neutron radiography: source neutron thermalization, neutron beam extraction geometry, neutron collimator dimensions, and neutron imaging methods. Each of these factors has a major effect on the quality of the radiographs which are obtained from a californium source neutron radiography system and the exposure times required to obtain the radiographs; radiograph quality and exposure time in turn affect the practicality of neutron radiography for specific nondestructive inspection applications. A brief discussion of fast neutron radiography using californium-252 neutron sources is also included. (U.S.)

  10. Californium-252 radiotherapy sources for interstitial afterloading

    International Nuclear Information System (INIS)

    Permar, P.H.; Walker, V.W.

    1976-01-01

    Californium-252 neutron sources for interstitial afterloading were developed to investigate the value of this radionuclide in cancer therapy. Californium-252 seed assemblies contain essentially point sources of 252 Cf permanently sealed on 1-cm centers within a flexible plastic tube. The seed assemblies are fabricated with remotely operated, specially designed machines. The fabrication process involves the production of a Pt-10 percent Ir-clad wire with a 252 Cf 2 O 3 -Pd cermet core. The wire is swaged and drawn to size, cut to length, and welded in a Pt-10 percent Ir capsule 0.8 mm in diameter and 6 mm long. Each seed capsule contains approximately 0.5 microgram of 252 Cf. Because the effective half-life of 252 Cf is 2.6 years, the seed assemblies are not disposable and must be reused until their activities have decreased to unsuitable levels. The flexible plastic components must therefore have sufficient resistance to radiation damage to survive the neutron-plus-gamma radiation from 252 Cf. On the basis of accelerated irradiation tests with a large 252 Cf source, a recently developed fluoropolymer, ''Tefzel'' (trademark of E. I. du Pont de Nemours and Company) has adequate radiation resistance for this application. Californium-252 seed assembly systems are loaned by the United States Energy Research and Development Administration for clinical investigations under a protocol of the Radiation Therapy Oncology Group, U.S. National Cancer Institute

  11. Californium-252: a remarkable versatile radioisotope

    International Nuclear Information System (INIS)

    Osborne-Lee, I.W.; Alexander, C.W.

    1995-01-01

    A product of the nuclear age, Californium-252 ( 252 Cf) has found many applications in medicine, scientific research, industry, and nuclear science education. Californium-252 is unique as a neutron source in that it provides a highly concentrated flux and extremely reliable neutron spectrum from a very small assembly. During the past 40 years, 252 Cf has been applied with great success to cancer therapy, neutron radiography of objects ranging from flowers to entire aircraft, startup sources for nuclear reactors, fission activation for quality analysis of all commercial nuclear fuel, and many other beneficial uses, some of which are now ready for further growth. Californium-252 is produced in the High Flux Isotope Reactor (HFIR) and processed in the Radiochemical Engineering Development Center (REDC), both of which are located at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The REDC/HFIR facility is virtually the sole supplier of 252 Cf in the western world and is the major supplier worldwide. Extensive exploitation of this product was made possible through the 252 Cf Market Evaluation Program, sponsored by the United States Department of Energy (DOE) [then the Atomic Energy Commission (AEC) and later the Energy Research and Development Administration (ERDA)]. This program included training series, demonstration centers, seminars, and a liberal loan policy for fabricated sources. The Market Evaluation Program was instituted, in part, to determine if large-quantity production capability was required at the Savannah River Laboratory (SRL). Because of the nature of the product and the means by which it is produced, 252 Cf can be produced only in government-owned facilities. It is evident at this time that the Oak Ridge research facility can meet present and projected near-term requirements. The production, shipment, and sales history of 252 Cf from ORNL is summarized herein

  12. Californium-252: a remarkable versatile radioisotope

    Energy Technology Data Exchange (ETDEWEB)

    Osborne-Lee, I.W.; Alexander, C.W.

    1995-10-10

    A product of the nuclear age, Californium-252 ({sup 252}Cf) has found many applications in medicine, scientific research, industry, and nuclear science education. Californium-252 is unique as a neutron source in that it provides a highly concentrated flux and extremely reliable neutron spectrum from a very small assembly. During the past 40 years, {sup 252}Cf has been applied with great success to cancer therapy, neutron radiography of objects ranging from flowers to entire aircraft, startup sources for nuclear reactors, fission activation for quality analysis of all commercial nuclear fuel, and many other beneficial uses, some of which are now ready for further growth. Californium-252 is produced in the High Flux Isotope Reactor (HFIR) and processed in the Radiochemical Engineering Development Center (REDC), both of which are located at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The REDC/HFIR facility is virtually the sole supplier of {sup 252}Cf in the western world and is the major supplier worldwide. Extensive exploitation of this product was made possible through the {sup 252}Cf Market Evaluation Program, sponsored by the United States Department of Energy (DOE) [then the Atomic Energy Commission (AEC) and later the Energy Research and Development Administration (ERDA)]. This program included training series, demonstration centers, seminars, and a liberal loan policy for fabricated sources. The Market Evaluation Program was instituted, in part, to determine if large-quantity production capability was required at the Savannah River Laboratory (SRL). Because of the nature of the product and the means by which it is produced, {sup 252}Cf can be produced only in government-owned facilities. It is evident at this time that the Oak Ridge research facility can meet present and projected near-term requirements. The production, shipment, and sales history of {sup 252}Cf from ORNL is summarized herein.

  13. Californium-252 sales and loans at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    King, L.J.

    1987-01-01

    The production and distribution in the United States of 252 Cf has recently been consolidated at the Oak Ridge National Laboratory (ORNL). The 252 Cf Industrial Sales/Loan Program and the 252 Cf University Load Program, which were formerly located at the Savannah River Plant (SRP), have been combined with the californium production and distribution activities of the Transuranium Element Production Program at ORNL. Californium-252 is sold to commercial users in the form of bulk californium oxide, palladium-californium alloy pellets, or alloy wires. Neutron source capsules, which are fabricated for loans to DOE or other US government agencies, are still available in all forms previously available. The consolidation of all 252 Cf distribution activities at the production site is expected to result in better service to users. In particular, customers for neutrons sources will be ale to select from a wider range of neutron source forms, including custom designs, through a single contact point

  14. Calibration of a Modified Californium Shuffler

    International Nuclear Information System (INIS)

    Sadowski, E.T.; Armstrong, F.; Oldham, R.; Ceo, R.; Williams, N.

    1995-01-01

    A californium shuffler originally designed to assay hollow cylindrical pieces of UA1 has been modified to assay solid cylinders. Calibration standards were characterized via chemical analysis of the molten UA1 taken during casting of the standards. The melt samples yielded much more reliable characterization data than drill samples taken from standards after the standards had solidified. By normalizing one well-characterized calibration curve to several standards at different enrichments, a relatively small number of standards was required to develop an enrichment-dependent calibration. The precision of this shuffler is 0.65%, and the typical random and systematic uncertainties are 0.53% and 0.73%, respectively, for a six minute assay of an ingot containing approximately 700 grams of 235 U. This paper will discuss (1) the discrepancies encountered when UA1 standards were characterized via melt samples versus drill samples, (2) a calibration methodology employing a small number of standards, and (3) a comparison of results from a previously unused shuffler with an existing shuffler. A small number of UA1 standards have been characterized using samples from the homogeneous molten state and have yielded enrichment-dependent and enrichment-independent calibration curves on two different shufflers

  15. Californium production at the transuranium processing plant

    International Nuclear Information System (INIS)

    King, L.J.

    1976-01-01

    The Transuranium Processing Plant (TRU) at ORNL, which is the production, storage, and distribution center for the ERDA heavy element research program, is described. About 0.5 percent of 252 Cf is currently being produced. TRU is a hot-cell, chemical processing facility of advanced design. New concepts have been incorporated into the facility for absolute containment, remote operation, remote equipment installation, and remote maintenance. The facilities include a battery of nine heavily shielded process cells served by master-slave manipulators and eight laboratories, four on each of two floors. Processing includes chemical dissolution of the targets followed by a series of solvent extraction, ion exchange, and precipitation steps to separate and purify the transuranium elements. The transcurium elements Bk, Cf, Es, and Fm are distributed to users. Remote techniques are used to fabricate the Am and Cm into target rods for reirradiation in the HFIR. Californium-252 that is in excess of the needs of the heavy element research program and the Cf sales program is stored at TRU and processed repeatedly to recover the daughter product 248 Cm, which is a highly desirable research material

  16. Fabrication of californium-252 sources in the United Kingdom

    International Nuclear Information System (INIS)

    Ainsworth, A.; Brady, M.W.; Thornett, W.H.

    1975-01-01

    The advent of californium-252 in weighable quantities and at a reasonable price has caused some rethinking among neutron source suppliers. To explore this market the Radiochemical Center Ltd. has purchased 2 mg of californium-252, and subdivided this into a wide range of sources. To take advantage of its high specific neutron emission, a small double welded stainless steel capsule 7.8mm diameter x 10mm high was chosen for stock sources and this entailed the use of a microdispensing technique which had to be specially developed. The apparatus and procedure for subdividing milligram amounts of californium-252 are described. Some details of our experience in processing these one milligram shipments are given. 100 sources with activities from 200 microgram to 0.01 microgram have been produced. Losses have been small. Measurement of neutron spectra gamma spectra and dose rates from encapsulated sources has confirmed published data. Though it is early days, little industrial interest in californium-252 sources has been detected, most of the sources have so far been required for research into activation analysis and two examples of this are given. (U.S.)

  17. Californium Multiplier. Part I. Design for neutron radiography

    International Nuclear Information System (INIS)

    Crosbie, K.L.; Preskitt, C.A.; John, J.; Hastings, J.D.

    1982-01-01

    The Californium Multiplier (CFX) is a subcritical assembly of enriched uranium surrounding a californium-252 neutron source. The function of the CFX is to multiply the neutrons emitted by the source to a number sufficient for neutron radiography. The CFX is designed to provide a collimated beam of thermal neutrons from which the gamma radiation is filtered, and the scattered neutrons are reduced to make it suitable for high resolution radiography. The entire system has inherent safety features, which provide for system and personnel safety, and it operates at moderate cost. In Part I, the CFX and the theory of its operation are described in detail. Part II covers the performance of the Mound Facility CFX

  18. Production, Distribution, and Applications of Californium-252 Neutron Sources

    International Nuclear Information System (INIS)

    Balo, P.A.; Knauer, J.B.; Martin, R.C.

    1999-01-01

    The radioisotope 252 Cf is routinely encapsulated into compact, portable, intense neutron sources with a 2.6-year half-life. A source the size of a person's little finger can emit up to 10 11 neutrons/s. Californium-252 is used commercially as a reliable, cost-effective neutron source for prompt gamma neutron activation analysis (PGNAA) of coal, cement, and minerals, as well as for detection and identification of explosives, laud mines, and unexploded military ordnance. Other uses are neutron radiography, nuclear waste assays, reactor start-up sources, calibration standards, and cancer therapy. The inherent safety of source encapsulations is demonstrated by 30 years of experience and by U.S. Bureau of Mines tests of source survivability during explosions. The production and distribution center for the U. S Department of Energy (DOE) Californium Program is the Radiochemical Engineering Development Center (REDC) at Oak Ridge National Laboratory (ORNL). DOE sells 252 Cf to commercial reencapsulators domestically and internationally. Sealed 252 Cf sources are also available for loan to agencies and subcontractors of the U.S. government and to universities for educational, research, and medical applications. The REDC has established the Californium User Facility (CUF) for Neutron Science to make its large inventory of 252 Cf sources available to researchers for irradiations inside uncontaminated hot cells. Experiments at the CUF include a land mine detection system, neutron damage testing of solid-state detectors, irradiation of human cancer cells for boron neutron capture therapy experiments, and irradiation of rice to induce genetic mutations

  19. Prompt neutron spectrum of the spontaneous fission of californium-252

    International Nuclear Information System (INIS)

    Zamyatnin, Yu.S.; Kroshkin, N.I.; Korostylev, V.A.; Nefedov, V.N.; Ryazanov, D.K.; Starostov, B.I.; Semenov, A.F.

    1976-01-01

    The californium-252 spontaneous fission neutron spectrum was measured in the energy range of 0.01 to 10 MeV by the time-of-flight technique using various neutron detectors. The measurements of 252 Cf neutron spectrum at energies of 0.01 to 5 MeV were performed as a function of fission fragment kinetic energy. The mean neutron spectrum energy in the range of 0.7 to 10 MeV was found from the results of measurements. The irregularity in the 252 Cf neutron spectrum in the neutron energy range of less than 0.7 MeV compared to theoretical values is discussed. The mechanism of 252 Cf neutron emission is also discussed on the basis of neutron yield angle measurements. 12 references

  20. A californium-252 source for radiobiological studies at Hiroshima University

    International Nuclear Information System (INIS)

    Kato, Kazuo; Takeoka, Seiji; Kuroda, Tokue; Tsujimura, Tomotaka; Kawami, Masaharu; Hoshi, Masaharu; Sawada, Shozo

    1987-01-01

    A 1.93 Ci (3.6 mg) californium-252 source was installed in the radiation facility of the Research Institute for Nuclear Medicine and Biology, Hiroshima University. This source produces fission neutrons (8.7 x 10 9 n/s at the time of its installation), which are similar to neutron spectrum of the atomic bombs. It is useful for studying biological effects of fission neutrons and neutron dosimetry. An apparatus was dosigned to accomodate this source and to apply it to such studies. It has resulted in profitable fission neutron exposures, while suppressing scattered neutrons and secondary gamma rays. This apparatus incorporates many safety systems, including one which interlocks with all of doors and an elevator serving the exposure room, so as to prevent accidents involving users. (author)

  1. Application of californium-252 neutron sources for analytical chemistry

    International Nuclear Information System (INIS)

    Ishii, Daido

    1976-01-01

    The researches made for the application of Cf-252 neutron sources to analytical chemistry during the period from 1970 to 1974 including partly 1975 are reviewed. The first part is the introduction to the above. The second part deals with general review of symposia, publications and the like. Attention is directed to ERDA publishing the periodical ''Californium-252 Progress'' and to a study group of Cf-252 utilization held by Japanese Radioisotope Association in 1974. The third part deals with its application for radio activation analysis. The automated absolute activation analysis (AAAA) of Savannha River is briefly explained. The joint experiment of Savannha River operation office with New Brunswick laboratory is mentioned. Cf-252 radiation source was used for the non-destructive analysis of elements in river water. East neutrons of Cf-252 were used for the quantitative analysis of lead in paints. Many applications for industrial control processes have been reported. Attention is drawn to the application of Cf-252 neutron sources for the field search of neutral resources. For example, a logging sonde for searching uranium resources was developed. the fourth part deals with the application of the analysis with gamma ray by capturing neutrons. For example, a bore hole sonde and the process control analysis of sulfur in fuel utilized capture gamma ray. The prompt gamma ray by capturing neutrons may be used for the nondestructive analysis of enrivonment. (Iwakiri, K.)

  2. Teratogenic effect of Californium-252 irradiation in rats

    International Nuclear Information System (INIS)

    Satow, Yukio; Lee, Juing-Yi; Hori, Hiroshi; Okuda, Hiroe; Tsuchimoto, Shigeo; Sawada, Shozo; Yokoro, Kenjiro

    1989-01-01

    The teratogenicity of Californium-252 (Cf-252) irradiation which generates approximately 70% 2.3 MeV fast neutron and 30% gamma rays was evaluated. A single whole body exposure of Cf-252 at various doses was given to pregnant rats on day 8 or 9 of pregnancy, followed by microscopic autopsy of the fetuses at the terminal stage of pregnancy to search for external and internal malformations. For comparison, pregnant rats were irradiated with various doses of Cobalt-60 (Co-60) standard gamma rays at the same dose rate (1 rad/min.). The doses were 20-120 rad of Cf-252 and 80-220 rad of Co-60. Using frequency of radiation induced malformations observed on day 8 of pregnancy as an index, relative biological effectiveness (RBE) of 2.3-2.7 was obtained from the straight line obtained by modifying by the least squares method the frequency curves of malformed fetuses in total implants and in surviving fetuses. The types of malformations induced by Cf-252 and Co-60 irradiation were alike. Using fetal LD 50 as an index, 2.4 was obtained as RBE when irradiated on day 8 of pregnancy and 3.1 as that when irradiated on day 9. The results showed that Cf-252 had stronger a teratogenic effect than Co-60 gamma rays. (author)

  3. Experimental studies on californium bioavailability to marine benthic invertebrates

    International Nuclear Information System (INIS)

    Fowler, S.W.; Carvalho, F.P.; Aston, S.R.

    1986-01-01

    252 Cf is readily taken up by benthic invertebrates from sea water, reaching whole-body concentration factors of 763 in the polychaete Hermione hystrix, 220 in the shrimp Lysmata seticaudata, 665 in the crab Pilumnus hirtellus and 78 in the bivalve mollusc Venerupis decussata after 3 weeks exposure. Surface sorption plays a predominant role in the uptake process. Depuration in clean sea water was a relatively slow process. The shrimp Lysmata eliminated 252 Cf very rapidly due to moulting. Absorption coefficients for ingested 252 Cf were high, approx. 23% in crabs and approx. 97% in brittlestars. The absorbed fraction was excreted twice as fast from crabs as brittlestars. Exposure of organisms to labelled sediment resulted in low transfer factors that were species dependent. There is some evidence to suggest that uptake from sediments is primarily due to 252 Cf transfer from the pore water. Comparison of these results with published experimental data on other transuranic nuclides in the same or similar species suggests that californium bioavailability is roughly equivalent to that of plutonium and americium. (author)

  4. Biomedical neutron research at the Californium User Facility for Neutron Science

    International Nuclear Information System (INIS)

    Martin, R.C.; Byrne, T.E.; Miller, L.F.

    1998-01-01

    The Californium User Facility for Neutron Science has been established at Oak Ridge National Laboratory (ORNL). The Californium User Facility (CUF) is a part of the larger Californium Facility, which fabricates and stores compact 252 Cf neutron sources for worldwide distribution. The CUF can provide a cost-effective option for research with 252 Cf sources. Three projects at the CUF that demonstrate the versatility of 252 Cf for biological and biomedical neutron-based research are described: future establishment of a 252 Cf-based neutron activation analysis system, ongoing work to produce miniature high-intensity, remotely afterloaded 252 Cf sources for tumor therapy, and a recent experiment that irradiated living human lung cancer cells impregnated with experimental boron compounds to test their effectiveness for boron neutron capture therapy. (author)

  5. Proposed Californium-252 User Facility for Neutron Science at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Martin, R.C.; Laxson, R.R.; Knauer, J.B.

    1996-01-01

    The Radiochemical Engineering Development Center (REDC) at ORNL has petitioned to establish a Californium-252 User Facility for Neutron Science for academic, industrial, and governmental researchers. The REDC Californium Facility (CF) stores the national inventory of sealed 252 Cf neutron source for university and research loans. Within the CF, the 252 Cf storage pool and two uncontaminated hot cells currently in service for the Californium Program will form the physical basis for the User Facility. Relevant applications include dosimetry and experiments for neutron tumor therapy; fast and thermal neutron activation analysis of materials; experimental configurations for prompt gamma neutron activation analysis; neutron shielding and material damage studies; and hardness testing of radiation detectors, cameras, and electronics. A formal User Facility simplifies working arrangements and agreements between US DOE facilities, academia, and commercial interests

  6. Biomedical neutron research at the Californium User Facility for neutron science

    International Nuclear Information System (INIS)

    Martin, R.C.; Byrne, T.E.; Miller, L.F.

    1997-01-01

    The Californium User Facility for Neutron Science has been established at Oak Ridge National Laboratory (ORNL). The Californium User Facility (CUF) is a part of the larger Californium Facility, which fabricates and stores compact 252 Cf neutron sources for worldwide distribution. The CUF can provide a cost-effective option for research with 252 Cf sources. Three projects at the CUF that demonstrate the versatility of 252 Cf for biological and biomedical neutron-based research are described: future establishment of a 252 Cf-based neutron activation analysis system, ongoing work to produce miniature high-intensity, remotely afterloaded 252 Cf sources for tumor therapy, and a recent experiment that irradiated living human lung cancer cells impregnated with experimental boron compounds to test their effectiveness for boron neutron capture therapy

  7. X-ray-diffraction study of californium metal to 16 GPa

    International Nuclear Information System (INIS)

    Peterson, J.R.; Benedict, U.; Dufour, C.; Birkel, I.; Haire, R.G.

    1983-01-01

    The first series of measurements to determine the structural behavior of californium (Cf) metal under pressure has been carried out. The initial dhcp structure transformed sluggishly with increasing pressure to a fcc structure. A bulk modulus of 50(5) GPa was derived for dhcp Cf metal from the relative volume (V/V 0 ) data to 10 GPa

  8. Study of the shielding for spontaneous fission sources of Californium-252

    International Nuclear Information System (INIS)

    Davila R, I.

    1991-06-01

    A shielding study is made to attenuate, until maximum permissible levels, the neutrons radiation and photons emitted by spontaneous fission coming from a source of Californium-252. The compound package by a database (Library DLC-23) and the ANISNW code is used, in it version for personal computer. (Author)

  9. Assessment of the neutron component in a neutron-gamma field of a californium-252 source

    International Nuclear Information System (INIS)

    Tetteh, G.K.

    1978-12-01

    Experiments have been performed to determine the percentages of the different components in the radiation field of californium-252 which has now some clinical applications. Using Rossi Chambers in conjunction with absorption investigations involving lead and aluminium thimbles, it is observed that the dose rates due to the different components are: neutrons 54%; gammas 30%; betas 16%

  10. Local Structure in Americium and Californium Hexa-cyanoferrates - Comparison with Their Lanthanide Analogues

    International Nuclear Information System (INIS)

    Dupouy, G.; Bonhoure, I.; Dumas, Th.; Moisy, Ph.; Petit, S.; Den Auwer, Ch.; Conradson, St.D.; Hennig, Ch.; Scheinost, A.C.; Le Naour, C.; Simoni, E.

    2011-01-01

    Metal hexa-cyanoferrates are well known molecular solids for a large variety of cations, although very little has been described for actinide adducts. Two new members of actinide(III) hexa-cyanoferrates were synthesized with the cations americium and californium. They were structurally characterized by infrared and X-ray absorption spectroscopy. Combined EXAFS data at the iron K edge and actinide L 3 edge provide evidence for a three-dimensional model for these two new compounds. Structural data in terms of bond lengths were compared to those reported for the parent lanthanide(III) compounds, neodymium and gadolinium hexa-cyanoferrates, respectively: the americium compound with (KNd(III)Fe(II)-Fe-III(CN) 6 .4H 2 O and the californium compound with (KGd(III)Fe(II)(CN) . 3.5H 2 O and (KGd(III)Fe(II)(CN) 6 .3H 2 O. This comparison between actinide and lanthanide homologues has been carried out on the basis of ionic radii considerations. The americium and neodymium environments appear to be very similar and are arranged in a tri-capped trigonal prism polyhedron of coordination number 9 (CN: 9), in which the americium atom is bonded to six nitrogen atoms and to three water molecules. For the californium adduct, a similar comparison and bond length and angle values derived from EXAFS studies suggest that the californium cation sits in a bi-capped trigonal prism (CN: 8) as in (KGd(III)Fe(II)(CN) 6 . 3H 2 O. This arrangement differs from that in the structure of (KGd(III)Fe(II)(CN) 6 .3.5H 2 O, in which the gadolinium atom is surrounded by 9 atoms. This is one of the rare pieces of information revealed by EXAFS spectroscopy for americium and californium in comparison to lanthanide atoms in molecular solid compounds. A discussion on the decrease in bond length and coordination number from americium to californium is also provided, on the basis of crystallographic results reported in the literature for actinide(III) and lanthanide(III) hydrate series. (authors)

  11. Atlantic Richfield Hanford Company californium multiplier/delayed neutron counter safety analysis

    International Nuclear Information System (INIS)

    Zimmer, W.H.

    1976-08-01

    The Californium Multiplier (CFX) is a subcritical assembly of uranium surrounding 252 Cf spontaneously fissioning neutron sources; its function is to multiply the neutron flux to a level useful for activation analysis. This document summarizes the safety analysis aspects of the CFX, DNC, pneumatic transfer system, and instrumentation and to detail all the aspects of the total facility as a starting point for the ARHCO Safety Analysis Review. Recognized hazards and steps already taken to neutralize them are itemized

  12. Instrumental neutron activation determination of gold in mineral raw materials using a californium neutron source

    International Nuclear Information System (INIS)

    Shilo, N.A.; Ippolitov, E.G.; Ivanenko, V.V.; Kustov, B.N.; Zheleznov, V.V.; Aristov, G.N.; Kovalenko, V.V.; Kondrat'ev, N.B.

    1983-01-01

    A facility using a californium neutron source and a method for the neutron activation analysis of gold were developed. The sensitivity of the determination is 0.1 g/t. The causes of random and systematic errors have been studied. It is concluded that in prospection and evaluation of gold ore deposists, the traditional test tube analysis for gold may be replaced with the developed method. (author)

  13. Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory TRU Californium Shipping Container

    International Nuclear Information System (INIS)

    Box, W.D.; Shappert, L.B.; Seagren, R.D.; Klima, B.B.; Jurgensen, M.C.; Hammond, C.R.; Watson, C.D.

    1980-01-01

    An analytical evaluation of the Oak Ridge National Laboratory TRU Californium Shipping Container was made in order to demonstrate its compliance with the regulations governing off-site shipment of packages that contain radioactive material. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of this evaluation demonstrate that the container complies with the applicable regulations

  14. Spectroscopic and redox properties of curium and californium ions in concentrated aqueous carbonate-bicarbonate media

    International Nuclear Information System (INIS)

    Hobart, D.E.; Varlashkin, P.G.; Samhoun, K.; Haire, R.G.; Peterson, J.R.

    1983-01-01

    Multimilligram quantities of trivalent curium-248 and californium-249 were investigated by absorption spectroscopy, cyclic voltammetry, and bulk solution electrolysis in concentrated aqueous carbonate-bicarbonate solution. Actinide concentrations between 10 -4 and 10 -2 M were studied in 2 M sodium carbonate and 5.5 M potassium carbonate solutions at pH values from 8 to 14. The solution absorption spectra of Cm(III) and Cf(III) in carbonate media are presented for the first time and compared to literature spectra of these species in noncomplexing aqueous solution. It was anticipated that carbonate complexation of the actinide ions could provide a sufficient negative shift in the formal potentials of the M(IV)/M(III) couples of Cm and Cf to permit the generation and stabilization of their tetravalent states in aqueous carbonate-bicarbonate medium. No conclusive evidence was found in the present work to indicate the existence of any higher oxidation states of curium or californium in carbonate solution. Some possible reasons for our inability to generate and detect oxidized species of curium and californium in this medium are discussed

  15. 12 CFR 19.242 - Definitions.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 1 2010-01-01 2010-01-01 false Definitions. 19.242 Section 19.242 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY RULES OF PRACTICE AND PROCEDURE Removal, Suspension, and Debarment of Accountants From Performing Audit Services § 19.242 Definitions. As used in this...

  16. 48 CFR 53.242 - Contract administration.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Contract administration. 53.242 Section 53.242 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION (CONTINUED) CLAUSES AND FORMS FORMS Prescription of Forms 53.242 Contract administration. ...

  17. 36 CFR 242.2 - Authority.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Authority. 242.2 Section 242... MANAGEMENT REGULATIONS FOR PUBLIC LANDS IN ALASKA General Provisions § 242.2 Authority. The Secretary of the Interior and Secretary of Agriculture issue the regulations in this part pursuant to authority vested in...

  18. 33 CFR 242.4 - Definitions.

    Science.gov (United States)

    2010-07-01

    ... MANAGEMENT SERVICES PROGRAM ESTABLISHMENT OF FEES FOR COST RECOVERY § 242.4 Definitions. As used in this part: Private persons means all entities in the private sector, including but not limited to individuals... 33 Navigation and Navigable Waters 3 2010-07-01 2010-07-01 false Definitions. 242.4 Section 242.4...

  19. 242-A evaporator hazards assessment

    International Nuclear Information System (INIS)

    Johnson, T.L.

    1998-01-01

    This document establishes the technical basis in support of Emergency Planning activities for the 242-A Evaporator, on the Hanford Site. Through this document the technical basis for the development of facility specific Emergency Action Levels and the Emergency Planning Zone is demonstrated. The evaporator sues a conventional, forced-circulation, vacuum evaporation system to concentrate radioactive waste solutions. This concentration results in the reduction in waste volume and reduces the number of double-shelled tanks required to store the waste

  20. Convenient method of simultaneously analyzing aluminum and magnesium in pharmaceutical dosage forms using californium-252 thermal neutron activation

    International Nuclear Information System (INIS)

    Landolt, R.R.; Hem, S.L.

    1983-01-01

    A commercial antacid suspension containing aluminum hydroxide and magnesium hydroxide products was used as a model sample to study the use of a californium-252 thermal neutron activation as a method for quantifying aluminum content as well as for the simultaneous assay of aluminum and magnesium. A 3.5-micrograms californium-252 source was used for the activation, and the induced aluminum-28 and magnesium-27 activity was simultaneously measured by sodium iodide crystal gamma-ray spectrometry using dual single-channel analyzers and scalers. The antacid suspension was contained in a chamber designed with the unique capability of serving as the container for counting the induced radioactivity in addition to being the irradiation chamber itself. This pilot study demonstrated that use of more intense californium-252 sources, which are commonly available, would provide a method that is competitive with the ethylenediaminetetraacetic acid titration method in precision and in other aspects as well

  1. Measurement of californium-252 gamma photons depth dose distribution in tissue equivalent material. Vol. 4

    Energy Technology Data Exchange (ETDEWEB)

    Fadel, M A; El-Fiki, M A; Eissa, H M; Abdel-Hafez, A; Naguib, S H [National Institute of Standards, Cairo (Egypt)

    1996-03-01

    Phantom of tissue equivalent material with and without bone was used measuring depth dose distribution of gamma-rays from californium-252 source. The source was positioned at center of perspex walled phantom. Depth dose measurements were recorded for X, Y and Z planes at different distances from source. TLD 700 was used for measuring the dose distribution. Results indicate that implantation of bone in tissue equivalent medium cause changes in the gamma depth dose distribution which varies according to variation in bone geometry. 9 figs.

  2. Measurements of integral cross sections in the californium-252 fission neutron spectrum

    International Nuclear Information System (INIS)

    Alberts, W.G.; Guenther, E.; Matzke, M.; Rassl, G.

    1977-01-01

    In a low-scattering arrangement cross sections averaged over the californium-252 spontaneous fission neutron spectrum were measured. The reactions 27 Al(n,α) 46 Ti, 47 Ti, 48 Ti(n,p), 54 Fe, 56 Fe(n,p), 58 Ni(n,p), 64 Zn(n,p), 115 In(n,n') were studied in order to obtain a consistent set of threshold detectors used in fast neutron flux density measurements. Overall uncertainties between 2 and 2.5% could be achieved; corrections due to neutron scattering in source and samples are discussed

  3. Neutron emission in fission of highly excited californium nuclei (E*=76 MeV)

    International Nuclear Information System (INIS)

    Blinov, M.V.; Bordyug, V.M.; Kozulin, Eh.M.; Mozhaev, A.N.; Levitovich, M.; Muzychka, Yu.A.; Penionzhkevich, Yu.Eh.; Pustyl'nik, B.I.

    1990-01-01

    The differential cross sections for neutron production in the fission of highly excited californium nuclei formed in the 238 U+ 12 C (105 MeV) reaction have been measured. From the analysis of the experimental data is follows that the number of pre-fission neutrons substantially exceeds the value obtained in the framework of the standard statistical model. The saddle-to-scission time of the excited nucleus is estimated on the basis of the neutron multiplicity. The dependences of the neutron number and neutron average energies upon the fragment mass are determined

  4. Neutron emission in fission of highly excited californium nuclei (E* = 76 MeV)

    International Nuclear Information System (INIS)

    Blinov, M.V.; Bordyug, V.M.; Kozulin, E.M.; Levitovich, M.; Mozhaev, A.N.; Muzychka, Yu.A.; Penionzhkevich, Yu.E.; Pustyl'nik, B.I.

    1990-01-01

    Differential cross sections for neutron production have been measured in fission of excited californium nuclei produced in the reaction 238 U + 12 C (105 MeV). It follows from analysis of the experimental results that the number of neutrons emitted before fission considerably exceeds the number obtained in the framework of the standard statistical model. On the basis of the multiplicity of neutrons they authors have estimated the time of fission of the excited nucleus. The dependence of the number of neutrons and their average energies on the mass of the fragments is determined

  5. Californium oxygen system for 1.50 < O/Cf < 1.72

    International Nuclear Information System (INIS)

    Turcotte, R.P.; Haire, R.G.

    1975-01-01

    The californium-oxygen system was studied as a function of temperature, oxygen pressure, and stoichiometry by manometric and x-ray diffraction methods. The results establish rhombohedral Cf 7 O 12 as the stable compound obtained by heating Cf 2 O 3 in air. The isobaric oxidation-reduction cycles Cf 2 O 3 → Cf 7 O 12 → Cf 2 O 3 , observed in constant rate of heating (cooling) experiments, occur with large hysteresis. A close parallel to other fluorite related lanthanide and actinide oxide systems is established. (auth)

  6. Possible stabilization of the tetravalent oxidation state of berkelium and californium in acetonitrile with triphenylarsine oxide

    International Nuclear Information System (INIS)

    Payne, G.F.; Peterson, J.R.

    1987-01-01

    It appears that we may have prepared Bk(IV) nitrate.nTPAs0 and Bk(IV) perchlorate.nTPAs0 complexes which formed the corresponding Cf(IV) complexes through the beta decay of Bk-249. Definitive proof should come from similar experiments with quantities of Bk-249 large enough to allow spectrophotometric detection of the characteristic f→f transitions in these berkelium and californium species. It is clear, however, that TPAs0 and acetonitrile can play a pivotal role in the stabilization of lanact(IV) species

  7. Comparison of the Savannah River Site billet active well coincidence counter and two Californium Shufflers

    International Nuclear Information System (INIS)

    Sadowski, E.T.; Griffin, J.C.; Rinard, P.M.

    1991-01-01

    A Scrap Californium Shuffler at the Savannah River Site (SRS) was calibrated to assay the U-Al cores of billets (an intermediate step in the SRS reactor fuel fabrication cycle.) The precision of the Scrap Shuffler over several years has been approximately 0.50%. A typical total uncertainty for the assay of a core on the Scrap Shuffler is approximately 0.33% for a twelve minute assay. The precision over several months and a typical total uncertainty for the Billet Active Well (neutron) Coincidence Counter (BAWCC) are approximately 1.0% and 1.9%, respectively, for a fifteen minute assay. A new Billet Californium Shuffler specifically designed for assaying SRS billets has yielded precision (over one month) and total uncertainty results of 0.40% and 0.69%, respectively, for an eight minute assay. The introduction of a measurement point into the fuel fabrication cycle to replace estimates based upon material weight will greatly enhance material and process control in the Reactor Materials area of SRS. The use of all three instruments provides a comparison of the relative merits of Active Well (neutron) Coincidence Counters (AWCCs) and shufflers for assay of homogeneous and geometrically simple material containing 235 U. The measurement precisions, systematic and random uncertainties, as well as the procurement and operation of each instrument will be compared. 3 refs., 5 figs., 1 tab

  8. 24 CFR 242.61 - Management.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Management. 242.61 Section 242.61... Management. The mortgagor shall provide for management of the hospital in a manner satisfactory to HUD. (a) Contract Management of Hospital. The mortgagor shall not execute a management agreement or any other...

  9. 24 CFR 242.52 - Construction contracts.

    Science.gov (United States)

    2010-04-01

    ...; a construction management contract with a guaranteed maximum price, the final costs of which are... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Construction contracts. 242.52... MORTGAGE INSURANCE FOR HOSPITALS Construction § 242.52 Construction contracts. (a) Awarding of contract. A...

  10. 42 CFR 24.2 - Allocation.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false Allocation. 24.2 Section 24.2 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES PERSONNEL SENIOR BIOMEDICAL RESEARCH SERVICE § 24... talent. (e) The Secretary will ensure that SBRS slots are used in support of high priority programs...

  11. 17 CFR 242.201 - Price test.

    Science.gov (United States)

    2010-04-01

    ... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Price test. 242.201 Section...-Regulation of Short Sales § 242.201 Price test. Link to an amendment published at 75 FR 11323, Mar. 10, 2010. (a) No short sale price test, including any short sale price test of any self-regulatory organization...

  12. Spectral investigation of neutron radiation in three-sectional concrete labyrinth from a californium-252 source

    International Nuclear Information System (INIS)

    Belogorlov, E.A.; Britvich, G.I.; Getmanov, V.B.

    1985-01-01

    Construction of labyrinths in points of communication output from the storage-ring under construction is accompanied by numerous difficulties due to a considerable number of gas and cryogenic pipelines, which require large cross sections at the minimal length of the pipelines proper for their location. It results in unfavourable for radiation attenuation ratios between cross section and length of the labyrinth separate sections. Neutron spectra in a model concrete labyrinth, at the entrance to which a neutron source with fission spectrum (californium-252) and the same source in a polyethylene moderator are located, are measured. On the basis of the spectra obtained the formation of fluence and equivalent dose along the labyrinth geometric axis is analyzed. Conditions permitting actually to reduce radiation dose in the labyrinth (dead end provision, the use of cover materials, construction of diaphragms and shielding plates) are simulated

  13. Transport calculations of. gamma. -ray flux density and dose rate about implantable californium-252 sources

    Energy Technology Data Exchange (ETDEWEB)

    Shapiro, A; Lin, B I [Cincinnati Univ., Ohio (USA). Dept. of Chemical and Nuclear Engineering; Windham, J P; Kereiakes, J G

    1976-07-01

    ..gamma.. flux density and dose rate distributions have been calculated about implantable californium-252 sources for an infinite tissue medium. Point source flux densities as a function of energy and position were obtained from a discrete-ordinates calculation, and the flux densities were multiplied by their corresponding kerma factors and added to obtain point source dose rates. The point dose rates were integrated over the line source to obtain line dose rates. Container attenuation was accounted for by evaluating the point dose rate as a function of platinum thickness. Both primary and secondary flux densities and dose rates are presented. The agreement with an independent Monte Carlo calculation was excellent. The data presented should be useful for the design of new source configurations.

  14. Dicty_cDB: SLH242 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available SL (Link to library) SLH242 (Link to dictyBase) - - - Contig-U16343-1 SLH242Z (Link... to Original site) - - SLH242Z 476 - - - - Show SLH242 Library SL (Link to library) Clone ID SLH242 (Link to...ycdb.biol.tsukuba.ac.jp/CSM/SL/SLH2-B/SLH242Q.Seq.d/ Representative seq. ID SLH24...2Z (Link to Original site) Representative DNA sequence >SLH242 (SLH242Q) /CSM/SL/SLH2-B/SLH242Q.Seq.d/ XXXXX...d/ 910 0.0 SLI231 (SLI231Q) /CSM/SL/SLI2-B/SLI231Q.Seq.d/ 910 0.0 SLH242 (SLH242Q) /CSM/SL/SLH2-B/SLH2

  15. Dicty_cDB: VFK242 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available VF (Link to library) VFK242 (Link to dictyBase) - - - Contig-U16260-1 VFK242P (Link to Original site) VFK2...42F 606 VFK242Z 292 VFK242P 878 - - Show VFK242 Library VF (Link to library) Clone ID VFK2... URL http://dictycdb.biol.tsukuba.ac.jp/CSM/VF/VFK2-B/VFK242Q.Seq.d/ Representative seq. ID VFK2...42P (Link to Original site) Representative DNA sequence >VFK242 (VFK242Q) /CSM/VF/VFK2-B/VFK2...eum cDNA clone:ddv63n23, 5' ... 1142 0.0 1 ( BJ427875 ) Dictyostelium discoideum cDNA clone:ddv63k24, 5' ...

  16. Fast and efficient charge breeding of the Californium rare isotope breeder upgrade electron beam ion source

    International Nuclear Information System (INIS)

    Ostroumov, P. N.; Barcikowski, A.; Dickerson, C. A.; Perry, A.; Sharamentov, S. I.; Vondrasek, R. C.; Zinkann, G. P.; Pikin, A. I.

    2015-01-01

    The Electron Beam Ion Source (EBIS), developed to breed Californium Rare Isotope Breeder Upgrade (CARIBU) radioactive beams at Argonne Tandem Linac Accelerator System (ATLAS), is being tested off-line. A unique property of the EBIS is a combination of short breeding times, high repetition rates, and a large acceptance. Overall, we have implemented many innovative features during the design and construction of the CARIBU EBIS as compared to the existing EBIS breeders. The off-line charge breeding tests are being performed using a surface ionization source that produces singly charged cesium ions. The main goal of the off-line commissioning is to demonstrate stable operation of the EBIS at a 10 Hz repetition rate and a breeding efficiency into single charge state higher than 15%. These goals have been successfully achieved and exceeded. We have measured (20% ± 0.7%) breeding efficiency into the single charge state of 28+ cesium ions with the breeding time of 28 ms. In general, the current CARIBU EBIS operational parameters can provide charge breeding of any ions in the full mass range of periodic table with high efficiency, short breeding times, and sufficiently low charge-to-mass ratio, 1/6.3 for the heaviest masses, for further acceleration in ATLAS. In this paper, we discuss the parameters of the EBIS and the charge breeding results in a pulsed injection mode with repetition rates up to 10 Hz

  17. Manganese determination om minerals by activation analysis, using the californium-252 as a neutron source

    International Nuclear Information System (INIS)

    Cardoso, Antonio

    1976-01-01

    Neutron Activation Analysis, using a Californium-252 neutron source, has been applied for the determination of manganese in ores such as pyrolusite, rodonite (manganese silicate)' and blending used in dry-batteries The favorable nuclear properties of manganese, such as high thermal neutron cross-section for the reaction 55 Mn (n.gamma) 56 Mn, high concentration of manganese in the matrix and short half - life of 56 Mn, are an ideal combination for non-destructive analysis of manganese in ores. Samples and standards of manganese dioxide were irradiated for about 20 minutes, followed by a 4 to 15 minutes decay and counted in a single channel pulse-height discrimination using a NaI(Tl) scintillation detector. Counting time was equal to 10 minutes. The interference of nuclear reactions 56 Fe(n,p) 56 Mn and 59 Co (n, α) 56 were studied, as well as problems in connection with neutron shadowing during irradiation, gamma-rays attenuation during counting and influence of granulometry of samples. One sample,was also analysed by wet-chemical method (sodium bismuthate) in order to compare results. As a whole, i t was shown that the analytical method of neutron activation for manganese in ores and blending, is a method simple, rapid and with good precision and accuracy. (author)

  18. Long-term effects of an intracavitary treatment with californium-252 on normal tissue

    International Nuclear Information System (INIS)

    Sullivan, M.F.; Beamer, J.L.; Mahony, T.D.; Cross, F.T.; Lund, J.E.; Endres, G.W.R.

    1976-01-01

    About one hundred fifty swine were exposed to either radium-226 or californium-252 sources in the uterine cervix to determine an RBE for both acute and long-term effects. That value for early changes in the tissues at risk in the treatment of cervical cancer was between 6.2 and 6.8. The incidence of complications increased with time after exposure, especially among animals treated with 252 Cf. Analysis of rectal injury showed that ulceration occurred frequently within a year postexposure at doses between 1600 and 2400 rad calculated at 2 cm lateral to the source midline. Fat necrosis and smooth muscle atrophy, resulting in a local rectal stricture, were delayed changes observed in some animals. The lower ureter was the site for a greater frequency of complications than the GI tract. Ureteral stricture often occurred at doses of 1200 rad from 252 Cf and 7000 rad from 226 Ra. Observation of delayed effects in the uterine-cervix in animals held up to 4 years postexposure indicate that the RBE for 252 Cf may be increased to a value as high as 18, while repair may have even decreased it to about 5.6 in the rectum. Fifty swine are still being observed for long-term effects after doses above 800 rad from 252 Cf and 5000 rad from 226 Ra

  19. Neutron activation analysis at the Californium User Facility for Neutron Science

    International Nuclear Information System (INIS)

    Martin, R.C.; Smith, E.H.; Glasgow, D.C.; Jerde, E.A.; Marsh, D.L.; Zhao, L.

    1997-12-01

    The Californium User Facility (CUF) for Neutron Science has been established to provide 252 Cf-based neutron irradiation services and research capabilities including neutron activation analysis (NAA). A major advantage of the CUF is its accessibility and controlled experimental conditions compared with those of a reactor environment The CUF maintains the world's largest inventory of compact 252 Cf neutron sources. Neutron source intensities of ≤ 10 11 neutrons/s are available for irradiations within a contamination-free hot cell, capable of providing thermal and fast neutron fluxes exceeding 10 8 cm -2 s -1 at the sample. Total flux of ≥10 9 cm -2 s -1 is feasible for large-volume irradiation rabbits within the 252 Cf storage pool. Neutron and gamma transport calculations have been performed using the Monte Carlo transport code MCNP to estimate irradiation fluxes available for sample activation within the hot cell and storage pool and to design and optimize a prompt gamma NAA (PGNAA) configuration for large sample volumes. Confirmatory NAA irradiations have been performed within the pool. Gamma spectroscopy capabilities including PGNAA are being established within the CUF for sample analysis

  20. 242-A evaporator vacuum condenser system

    International Nuclear Information System (INIS)

    Smith, V.A.

    1994-01-01

    This document is written for the 242-A evaporator vacuum condenser system (VCS), describing its purpose and operation within the evaporator. The document establishes the operating parameters specifying pressure, temperature, flow rates, interlock safety features and interfacing sub-systems to support its operation

  1. 32 CFR 242.7 - Responsibilities.

    Science.gov (United States)

    2010-07-01

    ... ADMISSION POLICIES AND PROCEDURES FOR THE SCHOOL OF MEDICINE, UNIFORMED SERVICES UNIVERSITY OF THE HEALTH SCIENCES § 242.7 Responsibilities. (a) The President of the University shall: (1) Develop and prescribe... procedures prescribed in this part. (3) Coordinate, as required, with the Military Department Secretaries or...

  2. 32 CFR 242.2 - Applicability.

    Science.gov (United States)

    2010-07-01

    ... ADMISSION POLICIES AND PROCEDURES FOR THE SCHOOL OF MEDICINE, UNIFORMED SERVICES UNIVERSITY OF THE HEALTH SCIENCES § 242.2 Applicability. This part applies to the Office of the Secretary of Defense, the Military Departments, the Uniformed Services University of the Health Sciences (USUHS), and the Department of Defense...

  3. Feasibility and market potential of protein determination of wheat using californium-252

    International Nuclear Information System (INIS)

    Roberts, T.C. Jr.; Eckhoff, N.D.; Clack, R.W.; Roberts, T.C. Sr.

    1976-01-01

    To evaluate the feasibility of protein determination by capture gamma-ray analysis using californium-252 neutrons, an in-situ protein analysis system for use by grain handlers has been examined. Three 227 kilogram (approximately) lots of wheat were used to determine the amount of nitrogen present. Protein analyses by the Kjeldahl method were obtained from samples taken before and after the capture gamma-ray analyses. The 5.267-MeV gamma-ray was selected for use in this study as a compromise between efficiency and interference from other elements. The associated counting equipment was a multichannel analyzer with pulse shaping electronic and analysis computing equipment. A linear regression program was used to compare the regions of interest to the Kjeldahl protein averages. The counts composing each peak were summed and normalized using the total count of the hydrogen peak. The normalized nitrogen percentages indicate a significant correlation between the spectral regions and the Kjeldahl analyses. To a first approximation, the value of wheat is the wheat protein. At the present time, protein testing of wheat is destructive, cumbersome, and time-consuming as compared to the potential for capture gamma-ray analysis testing. Assuming that such a protein analysis unit can analyze 42 tonne of wheat per hour, over 120 units would be needed to monitor one-half the U.S. annual wheat production. A 0.5% improvement in processor realizations and grain throughput value of $167.00 per tonne will result in a projected savings of $150,000 per year per unit

  4. 17 CFR 242.301 - Requirements for alternative trading systems.

    Science.gov (United States)

    2010-04-01

    ... trading systems. 242.301 Section 242.301 Commodity and Securities Exchanges SECURITIES AND EXCHANGE... FUTURES Regulation Ats-Alternative Trading Systems § 242.301 Requirements for alternative trading systems. (a) Scope of section. An alternative trading system shall comply with the requirements in paragraph...

  5. 48 CFR 2052.242-70 - Resolving differing professional views.

    Science.gov (United States)

    2010-10-01

    ... resolution of differing professional views (DPVs) of health and safety related concerns associated with the... professional views. 2052.242-70 Section 2052.242-70 Federal Acquisition Regulations System NUCLEAR REGULATORY....242-70 Resolving differing professional views. As prescribed in 2042.570-1, the contracting officer...

  6. 25 CFR 242.5 - Disposition of unmarketable fish.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false Disposition of unmarketable fish. 242.5 Section 242.5 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR FISH AND WILDLIFE COMMERCIAL FISHING ON RED LAKE INDIAN RESERVATION § 242.5 Disposition of unmarketable fish. All unmarketable live fish taken...

  7. 7 CFR 1220.242 - Books and records.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 10 2010-01-01 2010-01-01 false Books and records. 1220.242 Section 1220.242... CONSUMER INFORMATION Soybean Promotion and Research Order Reports, Books, and Records § 1220.242 Books and... subpart shall maintain and make available for inspection by the Board or Secretary such books and records...

  8. 42 CFR 438.242 - Health information systems.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 4 2010-10-01 2010-10-01 false Health information systems. 438.242 Section 438.242... Measurement and Improvement Standards § 438.242 Health information systems. (a) General rule. The State must ensure, through its contracts, that each MCO and PIHP maintains a health information system that collects...

  9. Neutron reflector design with Californium 252 neutron for Boron neutron chapter therapy facility using MCNP5 simulation method

    International Nuclear Information System (INIS)

    Muhammad Fakhrurreza; Kusminanto; Y Sardjono

    2014-01-01

    In this research has made a reflector design to provide beams of Neutron for BNCT with Californium-252 radioactive source. This collimator is useful to obtain optimum epithermal neutron flux with the smallest impurity radiation (thermal neutron, fast neutron, and gamma). The design process is done using Monte Carlo N-Particle simulation version 5 (MCNP5) code to calculate the neutron flux tally form. The chosen reflector design is the reflectors which use material such as BeO ceramic with 13 cm thick. Moderator use sulfur material with the slope angle of the cone is 30°. From the calculation result, it is obtained that Reflector with 1 gram Californium-252 source can produce a neutron output thermal which has thermal neutron specification 2.23189 x 10 9 n/s.cm 2 , epithermal neutron 3.51548 x 10 9 n/s.cm 2 , and fast neutron 4.82241 x 10 9 n/s.cm 2 From the result, it needs additional collimator because the BNCT requirement. (author)

  10. Hypoxic versus normoxic external-beam irradiation of cervical carcinoma combined with californium-252 neutron brachytherapy. Comparative treatment results of a 5-year randomized study

    Czech Academy of Sciences Publication Activity Database

    Tačev, T.; Vacek, Antonín; Ptáčková, B.; Strnad, V.

    2005-01-01

    Roč. 181, č. 5 (2005), s. 273-284 ISSN 0179-7158 Institutional research plan: CEZ:AV0Z50040507 Keywords : cervical carcinoma * hypoxyradiotherapy * californium-252 Subject RIV: BO - Biophysics Impact factor: 3.490, year: 2005

  11. Study of the shielding for spontaneous fission sources of Californium-252; Estudio de blindaje para fuentes de fision espontanea de Californio-252

    Energy Technology Data Exchange (ETDEWEB)

    Davila R, I

    1991-06-15

    A shielding study is made to attenuate, until maximum permissible levels, the neutrons radiation and photons emitted by spontaneous fission coming from a source of Californium-252. The compound package by a database (Library DLC-23) and the ANISNW code is used, in it version for personal computer. (Author)

  12. What's new with the FHA's Section 242?

    Science.gov (United States)

    Spidel, Alan J

    2008-11-01

    FHA hospital mortgage insurance, also called the Section 242 program, acts as a credit enhancement that allows borrowers to issue bonds up to the equivalent of an "AAA" rating, with the benefits of lower interest rates. Although the program has operated in relative obscurity over its 40 years of existence, the FHA has undertaken a new marketing campaign to raise its profile. Federal backing may make the program an attractive option amid today's financial turmoil in the capital markets.

  13. Evaluation of neutron data for plutonium-242

    International Nuclear Information System (INIS)

    Maslov, V.M.; Porodzinkij, Yu.V.; Sukhovitskij, E.Sh.; Morogovskij, G.B.

    1997-11-01

    The evaluation of neutron data for 242 Pu is made in the energy region from 10 -5 eV up to 20 MeV. The results of the evaluation are compiled in the ENDF/B-VI format. This work is performed under the Project Agreement CIS-03-95 with the International Science and Technology Center (Moscow). The Financing Party for the Project is Japan. The evaluation was requested by Japan Nuclear Data Center (JAERI). (author)

  14. 242-A evaporator dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-01-01

    The 242-A Evaporator is a waste management unit within the Hanford Facility that consists of process vessels and support systems for heating, evaporating, and condensing double-shell tank (DST) waste generated by Hanford Site operations. Operation of the 242-A Evaporator serves to reduce the volume of waste solutions within the DSTs that do not self-boil, while separating inorganic and radionuclide constituents from organic constituents. This operation reduces the number of underground DSTs required for waste storage and also makes the mixed waste more suitable for future treatment and disposal (i.e., grouting and vitrification). The 242-A Evaporator receives mixed-waste streams from the DSTs that contain organic and inorganic constituents and radionuclides. The waste is a dangerous waste (DW) because of corrosivity, reactivity, and toxicity characteristics, and is an extremely hazardous waste (EHW) as a result of toxicity (state criteria only), carcinogenicity, and persistence under the state mixture rule. The waste also contains spent nonhalogenated solvents

  15. Simulation and design of an electron beam ion source charge breeder for the californium rare isotope breeder upgrade

    Directory of Open Access Journals (Sweden)

    Clayton Dickerson

    2013-02-01

    Full Text Available An electron beam ion source (EBIS will be constructed and used to charge breed ions from the californium rare isotope breeder upgrade (CARIBU for postacceleration into the Argonne tandem linear accelerator system (ATLAS. Simulations of the EBIS charge breeder performance and the related ion transport systems are reported. Propagation of the electron beam through the EBIS was verified, and the anticipated incident power density within the electron collector was identified. The full normalized acceptance of the charge breeder with a 2 A electron beam, 0.024π  mm mrad for nominal operating parameters, was determined by simulating ion injection into the EBIS. The optics of the ion transport lines were carefully optimized to achieve well-matched ion injection, to minimize emittance growth of the injected and extracted ion beams, and to enable adequate testing of the charge bred ions prior to installation in ATLAS.

  16. Neutron activation analysis of the calcium content in vivo, using a 50μg source of californium 252

    International Nuclear Information System (INIS)

    Guey, A.; Zech, P.Y.; Meary, M.F.; Leitienne, P.

    1975-01-01

    Owing to the recent commercialisation of californium 252 it is now possible to obtain neutron fluxes strong enough for precise activation of the calcium content of biological targets. After the preliminary measurements necessary to establish the most suitable conditions for irradiating 3 to 5cm thick targets, two parallel sets of experiments were developed. In the first the medium-term total calcium variation was studied in 20 rats, 16 suffering from chronic kidney deficiency. In the second the precision expected as a function of the calcium content of the irradiated target was examined, using 3 sets of tissue equivalent standards of calcium contents 5, 20 and 50g respectively. The first results obtained on calcium 49 in vivo show that a calcium content variation can be followed with a sensitivity threshold below that obtained by conventional methods [fr

  17. Extraction of Trivalent Actinides and Lanthanides from Californium Campaign Rework Solution Using TODGA-based Solvent Extraction System

    Energy Technology Data Exchange (ETDEWEB)

    Benker, Dennis [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Delmau, Laetitia Helene [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dryman, Joshua Cory [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-07-01

    This report presents the studies carried out to demonstrate the possibility of quantitatively extracting trivalent actinides and lanthanides from highly acidic solutions using a neutral ligand-based solvent extraction system. These studies stemmed from the perceived advantage of such systems over cationexchange- based solvent extraction systems that require an extensive feed adjustment to make a low-acid feed. The targeted feed solutions are highly acidic aqueous phases obtained after the dissolution of curium targets during a californium (Cf) campaign. Results obtained with actual Cf campaign solutions, but highly diluted to be manageable in a glove box, are presented, followed by results of tests run in the hot cells with Cf campaign rework solutions. It was demonstrated that a solvent extraction system based on the tetraoctyl diglycolamide molecule is capable of quantitatively extracting trivalent actinides from highly acidic solutions. This system was validated using actual feeds from a Cf campaign.

  18. 242mAm Fueled Nuclear Battery

    International Nuclear Information System (INIS)

    Yigal Ronen, Y.; Hatav, A.; Hazenshprung, N.

    2004-01-01

    A nuclear battery based on a direct energy conversion of the fission products is presented. The principal behind direct-charging or direct-conversion [1] is based on the direct conversion of fission product energy into electrical energy, using a high voltage potential. The kinetic energy of the fission products is thus converted to potential energy and the charges collected in the conductive electrodes create an electrical current. High-power nuclear batteries are important due to the fact that they have almost no moving parts. As a result, maintenance problems (especially important in outer space) are considerably reduced. Such energy conversion is possible by using a nuclear reactor with ultra-thin fuel elements of 0.2 m of 242m Am. The amount of nuclear fuel is 376g and the dimensions of the battery are 2.4*2.4*2.4m (including the vacuum spacing), with a BeO moderator and Be electrodes. The total power of the reactor is 10.6 MW and the electrical power is 0.672 MW. The reactor is composed of 242m Am as a nuclear fuel with a thickness of 0.2μm and a moderator of 4 cm of BeO and two 0.5 cm thickness electrodes of Be, as presented in Fig. 1. The moderator-to-fuel-volume ratio is V m /V f = 250000. The infinite multiplication factor for this design is [2] k ∞ = 1.8

  19. 242-A evaporator safety analysis report

    International Nuclear Information System (INIS)

    CAMPBELL, T.A.

    1999-01-01

    This report provides a revised safety analysis for the upgraded 242-A Evaporator (the Evaporator). This safety analysis report (SAR) supports the operation of the Evaporator following life extension upgrades and other facility and operations upgrades (e.g., Project B-534) that were undertaken to enhance the capabilities of the Evaporator. The Evaporator has been classified as a moderate-hazard facility (Johnson 1990). The information contained in this SAR is based on information provided by 242-A Evaporator Operations, Westinghouse Hanford Company, site maintenance and operations contractor from June 1987 to October 1996, and the existing operating contractor, Waste Management Hanford (WMH) policies. Where appropriate, a discussion address the US Department of Energy (DOE) Orders applicable to a topic is provided. Operation of the facility will be compared to the operating contractor procedures using appropriate audits and appraisals. The following subsections provide introductory and background information, including a general description of the Evaporator facility and process, a description of the scope of this SAR revision,a nd a description of the basic changes made to the original SAR

  20. 242-A evaporator safety analysis report

    Energy Technology Data Exchange (ETDEWEB)

    CAMPBELL, T.A.

    1999-05-17

    This report provides a revised safety analysis for the upgraded 242-A Evaporator (the Evaporator). This safety analysis report (SAR) supports the operation of the Evaporator following life extension upgrades and other facility and operations upgrades (e.g., Project B-534) that were undertaken to enhance the capabilities of the Evaporator. The Evaporator has been classified as a moderate-hazard facility (Johnson 1990). The information contained in this SAR is based on information provided by 242-A Evaporator Operations, Westinghouse Hanford Company, site maintenance and operations contractor from June 1987 to October 1996, and the existing operating contractor, Waste Management Hanford (WMH) policies. Where appropriate, a discussion address the US Department of Energy (DOE) Orders applicable to a topic is provided. Operation of the facility will be compared to the operating contractor procedures using appropriate audits and appraisals. The following subsections provide introductory and background information, including a general description of the Evaporator facility and process, a description of the scope of this SAR revision,a nd a description of the basic changes made to the original SAR.

  1. Californium-252 Brachytherapy Combined With External-Beam Radiotherapy for Cervical Cancer: Long-Term Treatment Results

    International Nuclear Information System (INIS)

    Lei Xin; Qian Chengyuan; Qing Yi; Zhao Kewei; Yang Zhengzhou; Dai Nan; Zhong Zhaoyang; Tang Cheng; Li Zheng; Gu Xianqing; Zhou Qian; Feng Yan; Xiong Yanli; Shan Jinlu; Wang Dong

    2011-01-01

    Purpose: To observe, by retrospective analysis, the curative effects and complications due to californium-252 ( 252 Cf) neutron intracavitary brachytherapy (ICBT) combined with external-beam radiotherapy (EBRT) in the treatment of cervical cancer. Methods and Materials: From February 1999 to December 2007, 696 patients with cervical cancer (Stages IB to IIIB) were treated with 252 Cf-ICBT in combination of EBRT. Of all, 31 patients were at Stage IB, 104 at IIA, 363 at IIB, 64 at IIIA, and 134 at IIIB. Californium-252 ICBT was delivered at 7–12 Gy per insertion per week, with a total dose of 29–45 Gy to reference point A in three to five insertions. The whole pelvic cavity was treated with 8-MV X-ray external irradiation at 2 Gy per fraction, four times per week. After 16–38 Gy of external irradiation, the center of the whole pelvic field was blocked with a 4-cm-wide lead shield, with a total external irradiation dose of 44–56 Gy. The total treatment course was 5 to 6 weeks. Results: Overall survival rate at 3 and 5 years for all patients was 76.0% and 64.9%, respectively. Disease-free 3- and 5-year survival rates of patients were 71.2% and 58.4%, respectively. Late complications included vaginal contracture and adhesion, radiation proctitis, radiation cystitis, and inflammatory bowel, which accounted for 5.8%, 7.1%, 6.2%, and 4.9%, respectively. Univariate analysis results showed significant correlation of stage, age, histopathologic grade, and lymph node status with overall survival. Cox multiple regression analysis showed that the independent variables were stage, histopathologic grade, tumor size, and lymphatic metastasis in all patients. Conclusion: Results of this series suggest that the combined use of 252 Cf-ICBT with EBRT is an effective method for treatment of cervical cancer.

  2. Beyond Californium-A Neutron Generator Alternative for Dosimetry and Instrument Calibration in the U.S.

    Science.gov (United States)

    Piper, Roman K; Mozhayev, Andrey V; Murphy, Mark K; Thompson, Alan K

    2017-09-01

    Evaluations of neutron survey instruments, area monitors, and personal dosimeters rely on reference neutron radiations, which have evolved from the heavy reliance on (α,n) sources to a shared reliance on (α,n) and the spontaneous fission neutrons of californium-252 (Cf). Capable of producing high dose equivalent rates from an almost point source geometry, the characteristics of Cf are generally more favorable when compared to the use of (α,n) and (γ,n) sources or reactor-produced reference neutron radiations. Californium-252 is typically used in two standardized configurations: unmoderated, to yield a fission energy spectrum; or with the capsule placed within a heavy-water moderating sphere to produce a softened spectrum that is generally considered more appropriate for evaluating devices used in nuclear power plant work environments. The U.S. Department of Energy Cf Loan/Lease Program, a longtime origin of affordable Cf sources for research, testing and calibration, was terminated in 2009. Since then, high-activity sources have become increasingly cost-prohibitive for laboratories that formerly benefited from that program. Neutron generators, based on the D-T and D-D fusion reactions, have become economically competitive with Cf and are recognized internationally as important calibration and test standards. Researchers from the National Institute of Standards and Technology and the Pacific Northwest National Laboratory are jointly considering the practicality and technical challenges of implementing neutron generators as calibration standards in the U.S. This article reviews the characteristics of isotope-based neutron sources, possible isotope alternatives to Cf, and the rationale behind the increasing favor of electronically generated neutron options. The evaluation of a D-T system at PNNL has revealed characteristics that must be considered in adapting generators to the task of calibration and testing where accurate determination of a dosimetric quantity is

  3. 242-A evaporator safety analysis report

    International Nuclear Information System (INIS)

    Campbell, T.A.

    1998-01-01

    In compliance with DOE Orders, an update of the 242-A SAR has been prepared, as documented in the referenced ECN. Several categories of changes were identified for inclusion in this revision of the SAR. These categories will be utilized to simplify the discussion of the changes for this USQ document. However, it is important to note that no new tests or experiments were included in this revision of the SAR. Editorial changes and/or informational updates to Chapters 9 and 11 were included as part of this revision. However, no changes to Operational Safety Requirements (OSRs) contained in Chapter 11 were required. General categories of changes included in this revision are listed

  4. 36 CFR 242.13 - Board/agency relationships.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Board/agency relationships. 242.13 Section 242.13 Parks, Forests, and Public Property FOREST SERVICE, DEPARTMENT OF AGRICULTURE... relationships. (a) General. (1) The Board, in making decisions or recommendations, shall consider and ensure...

  5. 17 CFR 242.405 - Withdrawal of margin.

    Science.gov (United States)

    2010-04-01

    ... related positions in the account under this Regulation (§§ 242.400 through 242.406). (b) By the security... the CEA (7 U.S.C. 7a-1); (2) Interest charged on credit maintained in the account; (3) Communication or shipping charges with respect to transactions in the account; (4) Payment of commissions...

  6. 32 CFR 242b.7 - Officers of the University.

    Science.gov (United States)

    2010-07-01

    ..., developing, and directing the military activities and functions of the University. (ii) In the absence of the... Services University of the Health Sciences. (9) Dean of the Military Medical Education Institute. (i) The... 32 National Defense 2 2010-07-01 2010-07-01 false Officers of the University. 242b.7 Section 242b...

  7. 24 CFR 242.26 - Agreed interest rate.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Agreed interest rate. 242.26... MORTGAGE INSURANCE FOR HOSPITALS Mortgage Requirements § 242.26 Agreed interest rate. (a) The mortgage shall bear interest at the rate or rates agreed upon by the mortgagee and the mortgagor. (b) The amount...

  8. 40 CFR 86.242-94 - Records required.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 18 2010-07-01 2010-07-01 false Records required. 86.242-94 Section 86.242-94 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED... Later Model Year Gasoline-Fueled New Light-Duty Vehicles, New Light-Duty Trucks and New Medium-Duty...

  9. 17 CFR 242.505 - Exclusion for news media.

    Science.gov (United States)

    2010-04-01

    ... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Exclusion for news media. 242...-Analyst Certification § 242.505 Exclusion for news media. No provision of this Regulation AC shall apply to any person who: (a) Is the publisher of any bona fide newspaper, news magazine or business or...

  10. 17 CFR 242.610 - Access to quotations.

    Science.gov (United States)

    2010-04-01

    ... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Access to quotations. 242.610...-Regulation of the National Market System § 242.610 Access to quotations. (a) Quotations of SRO trading... national securities exchange or national securities association to the quotations in an NMS stock displayed...

  11. Use of californium-252 neutron irradiator for in-vivo analysis of the bone calcium content of the hand

    International Nuclear Information System (INIS)

    Guey, A.; Leitienne, P.; Zech, P.Y.; Traeger, J.; Doyen, J.B.; Breton, J.P.

    1979-01-01

    With californium-252 it is easy to obtain a high neutron flux of the order of 10 9 n/s. The mean energy of this radiation, which is close on 2 MeV, activates calcium very well. The authors describe a storage and irradiator unit with a 100 μg californium source, with which it will henceforth be possible to develop this technique of measuring the calcium of the hand in a hospital. The test programme has three distinct phases: (1) irradiation of the biological target for 10 min; (2) after a transfer period of 30 s, detection of the radiation emitted by the 49 Ca for 600 s; (3) processing of the numerical data received, which are transmitted on line to a T 1600 calculator. The weight is found by comparing the activity induced in the unknown calcium mass with that induced in a phantom chosen as the activity standard. The reproducibility of the method is of the order of 3% (5% at the worst). The gross standardized result is edited automatically. For physical and clinical reasons, the hand is chosen as the reference part of the body in 70 control subjects. The local irradiation dose is less than 2 rem. The bone calcium content is 14.3+-1.9 g in men and 10.1+-1.3 g in women. In clinical application of the technique it is necessary to differentiate between the normal calcium content and the calcium content found with a pathological state. This makes it necessary to express the measurement in the form of a volume mass (rho). The volume of the hand skeleton (V in cm 3 ) is calculated from the corresponding bone surface (S in cm 2 ) measured by planimetry with the relationship V=8.925 exp 0.0205.S, found after studying 80 hand skeletons. In our control subjects the calcium bone volume mass was 0.288 g/cm 3 in men and 0.282 g/cm 3 in women. There is a very significant difference (p<0.001) in a population of 88 subjects with chronic renal insufficiencies at the terminal stage: rho=0.233 in men and 0.235 in women

  12. 24 CFR 242.67 - New corporations, subsidiaries, affiliations, and mergers.

    Science.gov (United States)

    2010-04-01

    ..., affiliations, and mergers. 242.67 Section 242.67 Housing and Urban Development Regulations Relating to Housing... Reporting, and Financial Requirements § 242.67 New corporations, subsidiaries, affiliations, and mergers... written approval for all future mergers. ...

  13. Long-term effects of an intracavitary treatment with californium-252 on normal tissue. [Swine, /sup 226/Ra

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, M.F.; Beamer, J.L.; Mahony, T.D.; Cross, F.T.; Lund, J.E.; Endres, G.W.R.

    1976-01-01

    About one hundred fifty swine were exposed to either radium-226 or californium-252 sources in the uterine cervix to determine an RBE for both acute and long-term effects. That value for early changes in the tissues at risk in the treatment of cervical cancer was between 6.2 and 6.8. The incidence of complications increased with time after exposure, especially among animals treated with /sup 252/Cf. Analysis of rectal injury showed that ulceration occurred frequently within a year postexposure at doses between 1600 and 2400 rad calculated at 2 cm lateral to the source midline. Fat necrosis and smooth muscle atrophy, resulting in a local rectal stricture, were delayed changes observed in some animals. The lower ureter was the site for a greater frequency of complications than the GI tract. Ureteral stricture often occurred at doses of 1200 rad from /sup 252/Cf and 7000 rad from /sup 226/Ra. Observation of delayed effects in the uterine-cervix in animals held up to 4 years postexposure indicate that the RBE for /sup 252/Cf may be increased to a value as high as 18, while repair may have even decreased it to about 5.6 in the rectum. Fifty swine are still being observed for long-term effects after doses above 800 rad from /sup 252/Cf and 5000 rad from /sup 226/Ra.

  14. Neutron flux characterization of californium-252 Neutron Research Facility at the University of Texas - Pan American by nuclear analytical technique

    Science.gov (United States)

    Wahid, Kareem; Sanchez, Patrick; Hannan, Mohammad

    2014-03-01

    In the field of nuclear science, neutron flux is an intrinsic property of nuclear reaction facilities that is the basis for experimental irradiation calculations and analysis. In the Rio Grande Valley (Texas), the UTPA Neutron Research Facility (NRF) is currently the only neutron facility available for experimental research purposes. The facility is comprised of a 20-microgram californium-252 neutron source surrounded by a shielding cascade containing different irradiation cavities. Thermal and fast neutron flux values for the UTPA NRF have yet to be fully investigated and may be of particular interest to biomedical studies in low neutron dose applications. Though a variety of techniques exist for the characterization of neutron flux, neutron activation analysis (NAA) of metal and nonmetal foils is a commonly utilized experimental method because of its detection sensitivity and availability. The aim of our current investigation is to employ foil activation in the determination of neutron flux values for the UTPA NSRF for further research purposes. Neutron spectrum unfolding of the acquired experimental data via specialized software and subsequent comparison for consistency with computational models lends confidence to the results.

  15. 24 CFR 242.62 - Releases of lien.

    Science.gov (United States)

    2010-04-01

    ... DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES MORTGAGE INSURANCE FOR HOSPITALS Regulatory Agreement, Accounting and Reporting, and Financial Requirements § 242.62...

  16. 242-A Evaporator quality assurance plan. Revision 2

    International Nuclear Information System (INIS)

    Basra, T.S.

    1995-01-01

    The purpose of this quality assurance project plan (Plan) is to provide requirements for activities pertaining to sampling, shipping, and analyses associated with candidate feed tank samples for the 242-A Evaporator project. The purpose of the 242-A Evaporator project is to reduce the volume of aqueous waste in the Double Shell Tank (DST) System and will result in considerable savings to the disposal of mixed waste. The 242-A Evaporator feed stream originates from DSTs identified as candidate feed tanks. The 242-A Evaporator reduces the volume of aqueous waste contained in DSTs by boiling off water and sending the condensate (called process condensate) to the Liquid Effluent Retention Facility (LEPF) storage basin where it is stored prior to treatment in the Effluent Treatment Facility (ETF). The objective of this quality assurance project plan is to provide the planning, implementation, and assessment of sample collection and analysis, data issuance, and validation activities for the candidate feed tanks

  17. 24 CFR 242.56 - Form of regulation.

    Science.gov (United States)

    2010-04-01

    ... INSURANCE FOR HOSPITALS Regulatory Agreement, Accounting and Reporting, and Financial Requirements § 242.56... contractors, on an ongoing basis for the life of the insured mortgage to ensure against the risk of default...

  18. Page 1 242 Ethiopian Journal of Environmental Studies ...

    African Journals Online (AJOL)

    USER

    2015-03-17

    Mar 17, 2015 ... Ethiopian Journal of Environmental Studies & Management 8(3): 242 – 251, 2015. .... Central Kenya hardly used innovations on botanical pesticides. ..... science of the pests. Similarly ... Management Project in Western. Kenya ...

  19. 242-A Campaign 99-1 process control plan; FINAL

    International Nuclear Information System (INIS)

    LE, E.Q.

    1999-01-01

    242-A Evaporator 99-1 will process approximately one million gallons of waste from tank 102-AW in June 1999. The process control Plan provides a general description of activities, which will occur during 242-A Evaporator Campaign 99-1 and to document analyses conducted to demonstrate that 102-AW waste is acceptable for processing. Predict is a registered trademark of Risk Decisions England Corporation, United Kingdom

  20. 17 CFR 242.302 - Recordkeeping requirements for alternative trading systems.

    Science.gov (United States)

    2010-04-01

    ... alternative trading systems. 242.302 Section 242.302 Commodity and Securities Exchanges SECURITIES AND... SECURITY FUTURES Regulation Ats-Alternative Trading Systems § 242.302 Recordkeeping requirements for alternative trading systems. To comply with the condition set forth in paragraph (b)(8) of § 242.301, an...

  1. National Low-Level Waste Management Program radionuclide report series. Volume 13, Curium-242

    International Nuclear Information System (INIS)

    Adams, J.P.

    1995-08-01

    This report, Volume 13 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of curium-242 ( 242 Cm). This report also includes discussions about waste types and forms in which 242 Cm can be found and 242 Cm behavior in the environment and in the human body

  2. National Low-Level Waste Management Program radionuclide report series. Volume 13, Curium-242

    Energy Technology Data Exchange (ETDEWEB)

    Adams, J.P.

    1995-08-01

    This report, Volume 13 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of curium-242 ({sup 242}Cm). This report also includes discussions about waste types and forms in which {sup 242}Cm can be found and {sup 242}Cm behavior in the environment and in the human body.

  3. Ab initio full-potential study of mechanical properties and magnetic phase stability of californium monopnictides (CfN and CfP)

    Energy Technology Data Exchange (ETDEWEB)

    Amari, S., E-mail: siham_amari@yahoo.fr [Faculté des Sciences de la Nature et de la Vie, Université Hassiba Benbouali, Chlef, 02000 (Algeria); Bouhafs, B. [Laboratoire de Modélisation et Simulation en Sciences des Matériaux, Université Djillali Liabès de Sidi Bel-Abbés, Sidi Bel-Abbés, 22000 (Algeria)

    2016-09-15

    Based on the first-principles methods, the structural, elastic, electronic, properties and magnetic ordering of californium monopnictides CfX (X = P) have been studied using the full-potential augmented plane wave plus local orbitals (FP-L/APW + lo) method within the framework of density functional theory (DFT). The electronic exchange correlation energy is described by generalized gradient approximation GGA and GGA+U (U is the Hubbard correction). The GGA+U method is applied to the rare-earth 5f states. We have calculated the lattice parameters, bulk modulii and the first pressure derivatives of the bulk modulii. The elastic properties of the studied compounds are only investigated in the most stable calculated phase. In order to gain further information, we have calculated Young’s modulus, shear modulus, anisotropy factor and Kleinman parameter by the aid of the calculated elastic constants. The results mainly show that californium monopnictides CfX (X = P) have an antiferromagnetic spin ordering. Density of states (DOS) and charge densities for both compounds are also computed in the NaCl (B1) structure.

  4. Use of polyethylene pellets in the design and construction of a storage safe, a transport vessel and a portable shield for californium-252

    International Nuclear Information System (INIS)

    Sharma, S.

    1986-01-01

    A storage and shielding facility for 300 μg of Californium-252 sources was designed and constructed. Though the safe was in a permanent location, the fact that it consisted of a lead bucket surrounded by polyethylene pellets made it simple, movable and inexpensive. If need be, more quantities of Cf-252 could be added without altering the basic design and sacrificing the radiation protection guidelines. The measured radiation levels from 300 μg of stored Cf-252 in and around the storage vault were lower than the expected dose rates by a factor of 5. The measured radiation levels around the occupied environs of the facility were below the maximum permissible yearly dose of 500mrem for non-occupational workers. A transport vessel was designed and constructed to carry up to 50 μg of Californium-252 sources. It consisted of a standard 55 gallon steel drum on casters containing cylindrical lead shield surrounded by polyethylene pellets. The measured maximum surface dose rates on the drum and at one meter away were within the radiation protection guidelines and were less than the expected dose rates. A portable shield was designed and constructed to protect the body in afterloading operations and handling of the sources. It consisted of polyethylene pellets in an aluminum box and an attached 10 cm thick plexiglass eye shield. The simple design, with the ease of using polyethylene pellets can be extended to construct bedside shields

  5. Process Control Plan for 242-A Evaporator Campaign

    International Nuclear Information System (INIS)

    LE, E.Q.

    2000-01-01

    The wastes in tanks 107-AP and 108-AP are designated as feed for 242-A Evaporator Campaign 2000-1, which is currently scheduled for the week of April 17, 2000. Waste in tanks 107-AP and 108-AP is predominantly comprised of saltwell liquor from 200 West Tank Farms

  6. 17 CFR 256.242 - Miscellaneous current and accrued liabilities.

    Science.gov (United States)

    2010-04-01

    ... 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 § 256.242... as to show the nature of each liability included herein. 8. deferred credits ...

  7. 27 CFR 70.242 - Wages, salary and other income.

    Science.gov (United States)

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 2 2010-04-01 2010-04-01 false Wages, salary and other... Collection of Excise and Special (Occupational) Tax Limitations § 70.242 Wages, salary and other income. (a... as wages, salary or other income are exempt from levy. This section described the income of a...

  8. 24 CFR 242.30 - Application of payments.

    Science.gov (United States)

    2010-04-01

    ... insurance; (b) Ground rents, taxes, special assessments, and fire and other hazard insurance premiums; (c... URBAN DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES MORTGAGE INSURANCE FOR HOSPITALS Mortgage Requirements § 242.30 Application of payments. All payments to be...

  9. 17 CFR 242.607 - Customer account statements.

    Science.gov (United States)

    2010-04-01

    ... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Customer account statements... (CONTINUED) REGULATIONS M, SHO, ATS, AC, AND NMS AND CUSTOMER MARGIN REQUIREMENTS FOR SECURITY FUTURES Regulation Nms-Regulation of the National Market System § 242.607 Customer account statements. (a) No broker...

  10. 24 CFR 242.58 - Books, accounts, and financial statements.

    Science.gov (United States)

    2010-04-01

    ... Requirements § 242.58 Books, accounts, and financial statements. (a) Books and accounts. The mortgagor's books...: (i) Annual audited financial statements in accordance with the guidance below; (ii) Quarterly... (if the annual audited financial statement has not yet been filed with HUD) and at such other times as...

  11. 48 CFR 952.242-70 - Technical direction.

    Science.gov (United States)

    2010-10-01

    ... contract. (d) All technical direction shall be issued in writing by the COR. (e) The Contractor must... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Technical direction. 952... FORMS SOLICITATION PROVISIONS AND CONTRACT CLAUSES Text of Provisions and Clauses 952.242-70 Technical...

  12. 48 CFR 2452.242-71 - Contract management system.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Contract management system... 2452.242-71 Contract management system. As prescribed in 2442.1107, insert the following clause: Contract Management System (FEB 2006) (a) The contractor shall use contract management baseline planning...

  13. 48 CFR 242.803 - Disallowing costs after incurrence.

    Science.gov (United States)

    2010-10-01

    ... from contractors; (B) Approving interim vouchers for provisional payment (this includes approving the... interim vouchers for provisional payment to the disbursing office for contractors with approved billing... of Costs 242.803 Disallowing costs after incurrence. (a) Contracting officer receipt of vouchers...

  14. 36 CFR 242.11 - Regional advisory councils.

    Science.gov (United States)

    2010-07-01

    ... SUBSISTENCE MANAGEMENT REGULATIONS FOR PUBLIC LANDS IN ALASKA Program Structure § 242.11 Regional advisory... participate in the Federal subsistence management program. The Regional Councils shall be established, and... the members represent commercial and sport interests within a region. The portion of membership that...

  15. 36 CFR 242.15 - Rural determination process.

    Science.gov (United States)

    2010-07-01

    ... SUBSISTENCE MANAGEMENT REGULATIONS FOR PUBLIC LANDS IN ALASKA Program Structure § 242.15 Rural determination...) Development and diversity of the economy; (iii) Community infrastructure; (iv) Transportation; and (v... years shall be required before the non-rural determination becomes effective. (c) Current determinations...

  16. 17 CFR 242.604 - Display of customer limit orders.

    Science.gov (United States)

    2010-04-01

    ... such security; and (ii) The full size of each customer limit order held by the OTC market maker that... in relation to the size associated with the OTC market maker's bid or offer. (b) Exceptions. The... Regulation Nms-Regulation of the National Market System § 242.604 Display of customer limit orders. (a...

  17. 48 CFR 3052.242-71 - Dissemination of contract information.

    Science.gov (United States)

    2010-10-01

    ... CONTRACT CLAUSES Text of Provisions and Clauses 3052.242-71 Dissemination of contract information. As prescribed in (HSAR) 48 CFR 3042.202-70, insert the following clause: Dissemination of Contract Information... 48 Federal Acquisition Regulations System 7 2010-10-01 2010-10-01 false Dissemination of contract...

  18. 48 CFR 1252.242-72 - Dissemination of contract information.

    Science.gov (United States)

    2010-10-01

    ....242-72 Dissemination of contract information. As prescribed in (TAR) 48 CFR 1242.7000(c), insert the following clause: Dissemination of Contract Information (OCT 1994) The Contractor shall not publish, permit... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Dissemination of contract...

  19. 48 CFR 242.705-2 - Auditor determination procedure.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Auditor determination... Indirect Cost Rates 242.705-2 Auditor determination procedure. (b) Procedures. (2)(iii) When agreement cannot be reached with the contractor, the auditor will issue a DCAA Form 1, Notice of Contract Costs...

  20. 17 CFR 242.303 - Record preservation requirements for alternative trading systems.

    Science.gov (United States)

    2010-04-01

    ... requirements for alternative trading systems. 242.303 Section 242.303 Commodity and Securities Exchanges... REQUIREMENTS FOR SECURITY FUTURES Regulation Ats-Alternative Trading Systems § 242.303 Record preservation requirements for alternative trading systems. (a) To comply with the condition set forth in paragraph (b)(9) of...

  1. 48 CFR 2052.242-71 - Procedures for Resolving Differing Professional Views.

    Science.gov (United States)

    2010-10-01

    ... Differing Professional Views. 2052.242-71 Section 2052.242-71 Federal Acquisition Regulations System NUCLEAR... Clauses 2052.242-71 Procedures for Resolving Differing Professional Views. As prescribed in 2042.570-2(b... contracting officer. Procedures for Resolving NRC Contractor Differing Professional Views (DPVs) (OCT 1999) (a...

  2. 24 CFR 242.68 - Disclosure and verification of Social Security and Employer Identification Numbers.

    Science.gov (United States)

    2010-04-01

    ... Social Security and Employer Identification Numbers. 242.68 Section 242.68 Housing and Urban Development... Requirements § 242.68 Disclosure and verification of Social Security and Employer Identification Numbers. The requirements set forth in 24 CFR part 5, regarding the disclosure and verification of Social Security Numbers...

  3. 46 CFR 308.306 - Second Seamen's War Risk Policy, Form MA-242.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false Second Seamen's War Risk Policy, Form MA-242. 308.306... RISK INSURANCE Second Seamen's War Risk Insurance § 308.306 Second Seamen's War Risk Policy, Form MA-242. (a) The standard form of Second Seamen's War Risk Policy Form MA-242, may be obtained from the...

  4. 19 CFR 24.2 - Persons authorized to receive Customs collections.

    Science.gov (United States)

    2010-04-01

    ... 19 Customs Duties 1 2010-04-01 2010-04-01 false Persons authorized to receive Customs collections. 24.2 Section 24.2 Customs Duties U.S. CUSTOMS AND BORDER PROTECTION, DEPARTMENT OF HOMELAND SECURITY; DEPARTMENT OF THE TREASURY CUSTOMS FINANCIAL AND ACCOUNTING PROCEDURE § 24.2 Persons authorized to receive...

  5. Hanford facility dangerous waste permit application, 242-A evaporator

    International Nuclear Information System (INIS)

    Engelmann, R.H.

    1997-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, 'operating' treatment, storage, and/or disposal units, such as the 242-A Evaporator (this document, DOE/RL-90-42)

  6. 1998 242-A interim evaporator tank system integrity assessment plan

    Energy Technology Data Exchange (ETDEWEB)

    Jensen, C.E.

    1998-03-31

    Portions of the 242-A Evaporator on the Hanford Site must be assessed to meet the requirements of the Washington State Department of Ecology`s Dangerous Waste Regulation, Washington Administrative Code (WAC) 173-303. The assessment is limited to the provisions of Section 173-303-640. This Integrity Assessment Plan (IAP) identifies tasks which will be performed during the assessment phase and describes the intended assessment techniques. The 242-A Evaporator facility processes waste solutions from most of the operating laboratories and plants of the Hanford Site. The waste solutions are concentrated in the evaporator to a slurry of liquid and crystallized salts. This concentrated slurry is returned to the Tank Farms at a significantly reduce volume. The water vapor from the evaporation process is condensed, filtered, and can be pumped through an ion exchange bed before transfer to a retention basin. The non-condensable portion of the vapor is filtered and continuously monitored before venting to the atmosphere. The 242-A Evaporator will be assessed as seven subsystems. Four of the subsystems store, transport or treat Washington State Dangerous wastes, the other three subsystems are integral parts of the process, however, they do not directly store, transfer, or treat listed dangerous wastes. The facility will be inspected, tested, and analyzed through this assessment. The seven subsystems, defined in detail in Appendix B, are: Evaporator Process and Slurry Subsystem; Vapor Condenser Subsystem; Vessel Vent Subsystem; Process Condensate Subsystem; Steam Condensate Subsystem; Raw Water Disposal Subsystem; and Building and Secondary Containment Subsystem.

  7. 242-A evaporator quality assurance project plan: Revision 1

    International Nuclear Information System (INIS)

    Tucker, B.J.

    1994-01-01

    The scope of this quality assurance project plan (Plan) is sampling and analytical services including, but not limited to, sample receipt, handling and storage, analytical measurements, submittal of data deliverables, archiving selected portions of samples, returning unneeded sample material to Westinghouse Hanford Company (WHC), and/or sample disposal associated with candidate feed samples and process condensate compliance samples. Sampling and shipping activities are also included within the scope. The purpose of this project is to provide planning, implementation, and assessment guidance for achieving established data quality objectives measurement parameters. This Plan requires onsite and offsite laboratories to conform to that guidance. Laboratory conformance will help ensure that quality data are being generated and therefore, that the 242-A evaporator is operating in a safe and compliant manner. The 242-A evaporator feed stream originates from double-shell tanks (DSTs) identified as candidate feed tanks. The 242-A evaporator reduces the volume of aqueous waste contained in DSTs by boiling off water and sending it to the Liquid Effluent Retention Facility (LERF) storage basin before further treatment. The slurry product is returned to DSTs. Evaporation results in considerable savings by reducing the volume of mixed waste for disposal

  8. 242-A Evaporator waste analysis plan. Revision 4

    International Nuclear Information System (INIS)

    Basra, T.S.; Mulkey, C.H.

    1994-01-01

    This waste analysis plan (WAP) provides the plan for obtaining information needed for proper waste handling and processing in the 242-A Evaporator located on the Hanford Site. Regulatory and safety issues are addressed by establishing boundary conditions for waste received and treated at the 242-A Evaporator. The boundary conditions are set by establishing limits for items such as potential exothermic reactions, waste compatibility, and control of vessel vent organic emissions. Boundary conditions are also set for operational considerations and to ensure waste acceptance at receiving facilities. The issues that are addressed in this plan include prevention of exotherms in the waste, waste compatibility, vessel vent emissions, and compatibility with the liner in the Liquid Effluent Retention Facility (LERF). The 242-A Evaporator feed stream is separated into two liquid streams: a concentrated slurry stream and a process condensate. A gaseous exhaust stream is also produced. The slurry contains the majority of the radionuclides and inorganic constituents. This stream is pumped back to the double shell tanks (DSTs) and stored for further treatment after being concentrated to target levels. The process condensate (PC) is primarily water that contains trace amounts of organic material and a greatly reduced concentration of radionuclides. The process condensate is presently stored in the (LERF) until it can be further processed in the Effluent Treatment Facility once it is operational

  9. 1998 242-A interim evaporator tank system integrity assessment plan

    International Nuclear Information System (INIS)

    Jensen, C.E.

    1998-01-01

    Portions of the 242-A Evaporator on the Hanford Site must be assessed to meet the requirements of the Washington State Department of Ecology's Dangerous Waste Regulation, Washington Administrative Code (WAC) 173-303. The assessment is limited to the provisions of Section 173-303-640. This Integrity Assessment Plan (IAP) identifies tasks which will be performed during the assessment phase and describes the intended assessment techniques. The 242-A Evaporator facility processes waste solutions from most of the operating laboratories and plants of the Hanford Site. The waste solutions are concentrated in the evaporator to a slurry of liquid and crystallized salts. This concentrated slurry is returned to the Tank Farms at a significantly reduce volume. The water vapor from the evaporation process is condensed, filtered, and can be pumped through an ion exchange bed before transfer to a retention basin. The non-condensable portion of the vapor is filtered and continuously monitored before venting to the atmosphere. The 242-A Evaporator will be assessed as seven subsystems. Four of the subsystems store, transport or treat Washington State Dangerous wastes, the other three subsystems are integral parts of the process, however, they do not directly store, transfer, or treat listed dangerous wastes. The facility will be inspected, tested, and analyzed through this assessment. The seven subsystems, defined in detail in Appendix B, are: Evaporator Process and Slurry Subsystem; Vapor Condenser Subsystem; Vessel Vent Subsystem; Process Condensate Subsystem; Steam Condensate Subsystem; Raw Water Disposal Subsystem; and Building and Secondary Containment Subsystem

  10. Review of fission product yields and delayed neutron data for the actinides NP-237, PU-242, AM-242M, AM-243, CM-243 and CM-245

    International Nuclear Information System (INIS)

    Mills, R.W.

    1990-07-01

    A review of fission product yields and delayed neutron data for Np-237, Pu-242, Am-242m, Am-243, Cm-243 and Cm-245 has been undertaken. Gaps in understanding and inconsistencies in existing data were identified and priority areas for further experimental, theoretical and evaluation investigation detailed

  11. 242-A Control System device logic software documentation. Revision 2

    International Nuclear Information System (INIS)

    Berger, J.F.

    1995-01-01

    A Distributive Process Control system was purchased by Project B-534. This computer-based control system, called the Monitor and Control System (MCS), was installed in the 242-A Evaporator located in the 200 East Area. The purpose of the MCS is to monitor and control the Evaporator and Monitor a number of alarms and other signals from various Tank Farm facilities. Applications software for the MCS was developed by the Waste Treatment System Engineering Group of Westinghouse. This document describes the Device Logic for this system

  12. 242-A campaign 95-1 post run document

    International Nuclear Information System (INIS)

    Guthrie, M.D.

    1996-01-01

    The 242-A Evaporator Campaign 95-1 was started on June 6, 1995 and finished July 27, 1995. An overall Waste Volume Reduction (WVR) of 8.18 million liters (2.16 mGAL OR 87.6% WVRF) was achieved from 9.35 million liters (2.47 Mgal) of processable waste contained in 108-AP, 107-AP, 106-AW and 102-AW. Slurry generated from Campaign 95-1 consisted of 1.05 million liters (278,000 gal) of dilute double-shell slurry feed (DDSSF) with a SpG of approximately 1.34. Total process condensate discharged to LERF was 10.3 million liters (2.72 Mgal), achieving a condensate/WVR efficiency ratio of 1.26. Total throughout for Campaign 95-1 was 18.1 million liters (4.79 Mgal). B Pond discharges from steam condensate and cooling water were 15.8 and 583 million liters (4.17 and 154 Mgal) respectively. Based on 145 hours of unplanned downtime, the 242-A Evaporator maintained an operating efficiency of 86% during the 49 day campaign

  13. Restart oversight assessment of Hanford 242-A evaporator: Technical report

    International Nuclear Information System (INIS)

    Lagdon, R.; Lasky, R.

    1994-08-01

    An assessment team from the Office of Environment, Safety and Health (EH), US Department of Energy (DOE), conducted an independent assessment of the 242-A Evaporator at the Hanford Site during January 17--28, 1994. An EH team member remained on-site following the assessment to track corrective actions and resolve prestart findings. The primary objective of this assessment was independent assurance that the DOE Office of Environmental Management (EM), the DOE Richland Operations Office (DOE-RL), and Westinghouse Hanford Company (WHC) can safely restart the evaporator. Another objective of the EH team was to assess EM's Operational Readiness Evaluation (ORE) to determine if the programs, procedures, and management systems implemented for operation of the 241-A Evaporator ensure the protection of worker safety and health. The following section of this report provides background information on the 242-A Evaporator and Operational Readiness Review (ORR) activities conducted to date. The next chapter is divided into sections that address the results of discrete assessment activities. Each section includes a brief statement of conclusions for the functional area in question, descriptions of the review bases and methods, and a detailed discussion of the results. Concerns identified during the assessment are listed for the section to which they apply, and the specific findings upon which the concern is based can be found immediately thereafter

  14. 242A Distributed Control System Year 2000 Acceptance Test Report

    Energy Technology Data Exchange (ETDEWEB)

    TEATS, M.C.

    1999-08-31

    This report documents acceptance test results for the 242-A Evaporator distributive control system upgrade to D/3 version 9.0-2 for year 2000 compliance. This report documents the test results obtained by acceptance testing as directed by procedure HNF-2695. This verification procedure will document the initial testing and evaluation of the potential 242-A Distributed Control System (DCS) operating difficulties across the year 2000 boundary and the calendar adjustments needed for the leap year. Baseline system performance data will be recorded using current, as-is operating system software. Data will also be collected for operating system software that has been modified to correct year 2000 problems. This verification procedure is intended to be generic such that it may be performed on any D/3{trademark} (GSE Process Solutions, Inc.) distributed control system that runs with the VMSTM (Digital Equipment Corporation) operating system. This test may be run on simulation or production systems depending upon facility status. On production systems, DCS outages will occur nine times throughout performance of the test. These outages are expected to last about 10 minutes each.

  15. 242A Distributed Control System Year 2000 Acceptance Test Report

    International Nuclear Information System (INIS)

    TEATS, M.C.

    1999-01-01

    This report documents acceptance test results for the 242-A Evaporator distributive control system upgrade to D/3 version 9.0-2 for year 2000 compliance. This report documents the test results obtained by acceptance testing as directed by procedure HNF-2695. This verification procedure will document the initial testing and evaluation of the potential 242-A Distributed Control System (DCS) operating difficulties across the year 2000 boundary and the calendar adjustments needed for the leap year. Baseline system performance data will be recorded using current, as-is operating system software. Data will also be collected for operating system software that has been modified to correct year 2000 problems. This verification procedure is intended to be generic such that it may be performed on any D/3(trademark) (GSE Process Solutions, Inc.) distributed control system that runs with the VMSTM (Digital Equipment Corporation) operating system. This test may be run on simulation or production systems depending upon facility status. On production systems, DCS outages will occur nine times throughout performance of the test. These outages are expected to last about 10 minutes each

  16. 242-A Evaporator crystallizer facility integrated annual safety appraisal

    International Nuclear Information System (INIS)

    1991-01-01

    This report provides the results of the Fiscal Year (FY) 1991 Annual Integrated Safety Appraisal of the 242-A Evaporator Crystallizer Facility in the Hanford 200 East Area. The appraisal was conducted in December 1990 and January 1991, by the Waste Tank Safety Assurance (WTSA) organizations in conjunction with Radiological Engineering, Criticality Safety, Packaging and Shipping Safety, Emergency Preparedness, Environmental Compliance, and Quality Assurance. Reports of these eight organizations are presented as Sections 2 through 7 of this report. The purpose of the appraisal was to verify that the 242-A Evaporator meets US Department of Energy (DOE) and Westinghouse Hanford Company (WHC) requirements and current industry standards of good practice for the areas being appraised. A further purpose was to identify areas in which program effectiveness could be improved. In accordance with the guidance of WHC Management Requirements and Procedures (MRP)5.6, previously identified deficiencies which are being resolved by line management were not repeated as Findings or Observations unless progress or intended disposition was considered to be unsatisfactory

  17. 1998 interim 242-A Evaporator tank system integrity assessment report

    Energy Technology Data Exchange (ETDEWEB)

    Jensen, C.E.

    1998-07-02

    This Integrity Assessment Report (IAR) is prepared by Fluor Daniel Northwest (FDNW) under contract to Lockheed-Martin Hanford Company (LMHC) for Waste Management Hanford (WMH), the 242-A Evaporator (facility) operations contractor for Fluor Daniel Hanford, and the US Department of Energy, the system owner. The contract specifies that FDNW perform an interim (5 year) integrity assessment of the facility and prepare a written IAR in accordance with Washington Administrative Code (WAC) 173-303-640. The WAC 173-303 defines a treatment, storage, or disposal (TSD) facility tank system as the ``dangerous waste storage or treatment tank and its ancillary equipment and containment.`` This integrity assessment evaluates the two tank systems at the facility: the evaporator vessel, C-A-1 (also called the vapor-liquid separator), and the condensate collection tank, TK-C-100. This IAR evaluates the 242-A facility tank systems up to, but not including, the last valve or flanged connection inside the facility perimeter. The initial integrity assessment performed on the facility evaluated certain subsystems not directly in contact with dangerous waste, such as the steam condensate and used raw water subsystems, to provide technical information. These subsystems were not evaluated in this IAR. The last major upgrade to the facility was project B-534. The facility modifications, as a result of project B-534, were evaluated in the 1993 facility interim integrity assessment. Since that time, the following upgrades have occurred in the facility: installation of a process condensate recycle system, and installation of a package steam boiler to provide steam for the facility. The package boiler is not within the scope of the facility TSD.

  18. 1998 interim 242-A Evaporator tank system integrity assessment report

    International Nuclear Information System (INIS)

    Jensen, C.E.

    1998-01-01

    This Integrity Assessment Report (IAR) is prepared by Fluor Daniel Northwest (FDNW) under contract to Lockheed-Martin Hanford Company (LMHC) for Waste Management Hanford (WMH), the 242-A Evaporator (facility) operations contractor for Fluor Daniel Hanford, and the US Department of Energy, the system owner. The contract specifies that FDNW perform an interim (5 year) integrity assessment of the facility and prepare a written IAR in accordance with Washington Administrative Code (WAC) 173-303-640. The WAC 173-303 defines a treatment, storage, or disposal (TSD) facility tank system as the ''dangerous waste storage or treatment tank and its ancillary equipment and containment.'' This integrity assessment evaluates the two tank systems at the facility: the evaporator vessel, C-A-1 (also called the vapor-liquid separator), and the condensate collection tank, TK-C-100. This IAR evaluates the 242-A facility tank systems up to, but not including, the last valve or flanged connection inside the facility perimeter. The initial integrity assessment performed on the facility evaluated certain subsystems not directly in contact with dangerous waste, such as the steam condensate and used raw water subsystems, to provide technical information. These subsystems were not evaluated in this IAR. The last major upgrade to the facility was project B-534. The facility modifications, as a result of project B-534, were evaluated in the 1993 facility interim integrity assessment. Since that time, the following upgrades have occurred in the facility: installation of a process condensate recycle system, and installation of a package steam boiler to provide steam for the facility. The package boiler is not within the scope of the facility TSD

  19. Organic emission calculations for the 242-A evaporator vessel vent system

    International Nuclear Information System (INIS)

    Bowman, M.R.

    1996-01-01

    This document contains historical calculations originally published in the 242-A Evaporator Dangerous Waste Permit Application, DOE/RL-90-42, Rev 0. They are being released as a supporting document, along with brief explanatory information, to be used as a reference in Rev 1 of the permit application and in other supporting documents, such as the 242-A Evaporator Data Quality Objectives

  20. 48 CFR 252.242-7004 - Material management and accounting system.

    Science.gov (United States)

    2010-10-01

    ... CLAUSES Text of Provisions And Clauses 252.242-7004 Material management and accounting system. As prescribed in 242.7204, use the following caluse: Material Management and Accounting System (JUL 2009) (a) Definitions. As used in this clause— (1) Material management and accounting system (MMAS) means the Contractor...

  1. 21 CFR 1.242 - What does assignment of a registration number mean?

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 1 2010-04-01 2010-04-01 false What does assignment of a registration number mean? 1.242 Section 1.242 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL GENERAL ENFORCEMENT REGULATIONS Registration of Food Facilities Additional Provisions § 1...

  2. 30 CFR 250.242 - What information must accompany the DPP or DOCD?

    Science.gov (United States)

    2010-07-01

    ... § 250.248; (g) Air emissions information required by § 250.249; (h) Oil and hazardous substance spills...? 250.242 Section 250.242 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR....258; (q) Sulphur operations information required by § 250.259; (r) Coastal zone management information...

  3. Neutron spectra of /sup 242/Cm-Be and /sup 244/Cm-Be neutron sources

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, A; Nagarajan, P S [Bhabha Atomic Research Centre, Bombay (India). Div. of Radiation Protection

    1977-02-15

    Neutron spectra of /sup 242/Cm-Be(..cap alpha..,n) and /sup 244/Cm-Be(..cap alpha..,n) sources have been calculated including the spontaneous fission contribution which is negligible for /sup 242/Cm and amounts to about 4% for /sup 244/Cm. The agreement of the present work with experimental results is poor.

  4. 24 CFR 242.49 - Funds and finances: deposits and letters of credit.

    Science.gov (United States)

    2010-04-01

    ... collection under the letter of credit. In the event a demand for payment thereunder is not immediately met... letters of credit. 242.49 Section 242.49 Housing and Urban Development Regulations Relating to Housing and...: deposits and letters of credit. (a) Deposits. Where HUD requires the mortgagor to make a deposit of cash or...

  5. 242-A MCS Logic Acceptance Test Report for Year 2000 Upgrade

    International Nuclear Information System (INIS)

    TEATS, M.C.

    1999-01-01

    242-A Evaporator distributive control system upgrade to D/3 version 9.0-2 for year 2000 compliance. Testing was performed per test procedure HNF-3568. There were no unresolved exceptions. The system responded correctly to all testing and meets the requirements to operate the 242-A This report documents the acceptance test results for the Evaporator facility

  6. Analysis of Windscale and Bikini atoll sediments for Am-242m

    International Nuclear Information System (INIS)

    Beasley, T.M.

    1976-01-01

    Bowen and Livingston have recently reported the existence of 242 Am in both 1962 nuclear test debris and in a marine algae sample (kelp) contaminated by nuclear fuel reprocessing wastes. The presence of 242m Am (T 1/2 = 152y) was deduced by measuring its daughter product, 242C m. In the case of the fallout debris, the long decay time (25 years) between collection and analysis was argued to preclude the possibility of unsupported 242 Cm being present in the sample. The non-adherence to simple radiometric decay of the 242 Cm measured in two aliquots of the algae sample suggested that a small percentage of the isotope (≈ 3%) was in fact supported by its longer lived parent

  7. Californium interrogation prompt neutron (CIPN) instrument for non-destructive assay of spent nuclear fuel—Design concept and experimental demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Henzlova, D., E-mail: henzlova@lanl.gov [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Menlove, H.O.; Rael, C.D.; Trellue, H.R.; Tobin, S.J. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Park, Se-Hwan; Oh, Jong-Myeong; Lee, Seung-Kyu; Ahn, Seong-Kyu; Kwon, In-Chan; Kim, Ho-Dong [Korea Atomic Energy Research Institute, Daejeong (Korea, Republic of)

    2016-01-11

    This paper presents results of the first experimental demonstration of the Californium Interrogation Prompt Neutron (CIPN) instrument developed within a multi-year effort launched by the Next Generation Safeguards Initiative Spent Fuel Project of the United States Department of Energy. The goals of this project focused on developing viable non-destructive assay techniques with capabilities to improve an independent verification of spent fuel assembly characteristics. For this purpose, the CIPN instrument combines active and passive neutron interrogation, along with passive gamma-ray measurements, to provide three independent observables. This paper describes the initial feasibility demonstration of the CIPN instrument, which involved measurements of four pressurized-water-reactor spent fuel assemblies with different levels of burnup and two initial enrichments. The measurements were performed at the Post-Irradiation Examination Facility at the Korea Atomic Energy Institute in the Republic of Korea. The key aim of the demonstration was to evaluate CIPN instrument performance under realistic deployment conditions, with the focus on a detailed assessment of systematic uncertainties that are best evaluated experimentally. The measurements revealed good positioning reproducibility, as well as a high degree of insensitivity of the CIPN instrument's response to irregularities in a radial burnup profile. Systematic uncertainty of individual CIPN instrument signals due to assembly rotation was found to be <4.5%, even for assemblies with fairly extreme gradients in the radial burnup profile. These features suggest that the CIPN instrument is capable of providing a good representation of assembly average characteristics, independent of assembly orientation in the instrument.

  8. Californium interrogation prompt neutron (CIPN) instrument for non-destructive assay of spent nuclear fuel—Design concept and experimental demonstration

    International Nuclear Information System (INIS)

    Henzlova, D.; Menlove, H.O.; Rael, C.D.; Trellue, H.R.; Tobin, S.J.; Park, Se-Hwan; Oh, Jong-Myeong; Lee, Seung-Kyu; Ahn, Seong-Kyu; Kwon, In-Chan; Kim, Ho-Dong

    2016-01-01

    This paper presents results of the first experimental demonstration of the Californium Interrogation Prompt Neutron (CIPN) instrument developed within a multi-year effort launched by the Next Generation Safeguards Initiative Spent Fuel Project of the United States Department of Energy. The goals of this project focused on developing viable non-destructive assay techniques with capabilities to improve an independent verification of spent fuel assembly characteristics. For this purpose, the CIPN instrument combines active and passive neutron interrogation, along with passive gamma-ray measurements, to provide three independent observables. This paper describes the initial feasibility demonstration of the CIPN instrument, which involved measurements of four pressurized-water-reactor spent fuel assemblies with different levels of burnup and two initial enrichments. The measurements were performed at the Post-Irradiation Examination Facility at the Korea Atomic Energy Institute in the Republic of Korea. The key aim of the demonstration was to evaluate CIPN instrument performance under realistic deployment conditions, with the focus on a detailed assessment of systematic uncertainties that are best evaluated experimentally. The measurements revealed good positioning reproducibility, as well as a high degree of insensitivity of the CIPN instrument's response to irregularities in a radial burnup profile. Systematic uncertainty of individual CIPN instrument signals due to assembly rotation was found to be <4.5%, even for assemblies with fairly extreme gradients in the radial burnup profile. These features suggest that the CIPN instrument is capable of providing a good representation of assembly average characteristics, independent of assembly orientation in the instrument.

  9. Waste volume reduction factors for potential 242-A evaporator feed

    International Nuclear Information System (INIS)

    Sederburg, J.P.

    1995-01-01

    Double-shell tank (DST) storage space requirements have been shown to be highly dependent on the end point of 242-A operations. Consequences to the DST of various waste volumes, and concentrations, are evaluated. Only waste streams that are currently planned to be stored in the DST system before the year 2004 are discussed. As of January 1, 1995, approximately 27-million L (7.2-million gal) of dilute wastes are stored in the DSTs available for evaporator processing. Waste streams planned to be transferred to the DSTs before December 31, 2004, are identified. The DST volume for storing slurry from these wastes is presented in this document. At a final slurry specific gravity of -1.35, 22.5-million L (5.93-million gal) of DST space would be needed on December 31, 2004, to store the product from evaporator processing of these feedstocks. The expected volume needed if the resultant slurry were concentrated to the traditional double-shell slurry feed (DSSF) phase boundary (a specific gravity of ∼1.5) would be 17.7-million L (4.67-million gal). An additional 4.8-million L (1.26-million gal) is therefore needed if these wastes are concentrated to a specific gravity of 1.35 instead of the DSSF limit

  10. Restart oversight assessment of Hanford 242-A evaporator: Summary report

    International Nuclear Information System (INIS)

    1994-08-01

    This report summarizes a January 17--28, 1994, oversight assessment of restart activities for the 242-A Evaporator at the US Department of Energy's (DOE's) Hanford Site about 25 miles northeast of Hanford, Washington. The assessment was conducted by qualified staff and consultants from the DOE Office of Environment, Safety and Health (EH). Its focus was the readiness of the facility for the resumption of safe operations, in particular those operations involved in the treatment and disposal of condensate from the evaporation of liquid radioactive waste, a key element of the tank waste remediation project administered by the DOE Richland Operations Office (DOE-RL). Overall, the assessment yielded eight programmatic concerns, supported by 38 individual findings. Of the concerns, four have already been closed, and the other four have been resolved. Results pointed up strengths in management and engineering design, as well as effective support of facility training programs by the management and operating contractor, Westinghouse Hanford Company (WHC). Weaknesses were evident, however, in conduct of operations, maintenance, and radiological practices. Furthermore, problems in the submittal and approval of Compliance Schedule Approvals--that is, WHC documentation of the status of compliance with DOE orders--were indicative of a programmatic breakdown in the DOE Order compliance process. According to the results of this assessment, there are no safety and health issues that would preclude or delay restart of the evaporator

  11. 24 CFR 1000.242 - When does the requirement for exemption from taxation apply to affordable housing activities?

    Science.gov (United States)

    2010-04-01

    ... exemption from taxation apply to affordable housing activities? 1000.242 Section 1000.242 Housing and Urban... ACTIVITIES Indian Housing Plan (IHP) § 1000.242 When does the requirement for exemption from taxation apply to affordable housing activities? The requirement for exemption from taxation applies only to rental...

  12. 27 CFR 24.242 - Authority to use greater quantities of decolorizing material in juice or wine.

    Science.gov (United States)

    2010-04-01

    ... quantities of decolorizing material in juice or wine. 24.242 Section 24.242 Alcohol, Tobacco Products and Firearms ALCOHOL AND TOBACCO TAX AND TRADE BUREAU, DEPARTMENT OF THE TREASURY LIQUORS WINE Storage, Treatment and Finishing of Wine § 24.242 Authority to use greater quantities of decolorizing material in...

  13. 242-A Campaign 94-1 post run document

    International Nuclear Information System (INIS)

    Guthrie, M.D.

    1994-01-01

    The purpose of this post-run document is to summarize the results of 242-A Evaporator Campaign 94-1 as required. Campaign 94-1 represents the first Evaporator operation since 1989, following completion of the B-534 upgrades and Liquid Effluent Retention Facility (LERF) construction. The purpose of Campaign 94-1 was to concentrate dilute waste from TK-102-AW, TK-106-AW, and TK-103-AP. From an available 2.87 million gallon feedstock of dilute waste contained in 102-AW, 106-AW and 103-AP, an overall Waste Volume Reduction (WVR) of 2.39 million gallons (83% WVRF) was achieved. At the completion of the campaign, approximately 477,000 gallons of dilute double-shell slurry feed (DDSSF) was produced with a SpG. of 1.25--1.30. Total process condensate discharged to LERF was 3.09 million gallons, achieving a condensate/WVR ratio of 1.29. Throughput for Campaign 94-1 was 5.27 million gallons. Total steam condensate and cooling water discharge to B-pond was 4.7 and 216 million gallons respectively. The evaporator operated approximately 43 days of the 60 day campaign for a total operating efficiency of 73%. Campaign 94-1 was completed without any discharge limit, Operating Specification Document, or Operational Safety Requirement violations. Major problems encountered during the run included the following: (1) high CA1 deentrainment pad dP's caused by foaming, (2) condensate pump P-C100 failure, and (3) ion exchange column dP's and efficiency

  14. Thermochemical Erosion Modeling of the 25-MM M242/M791 Gun System

    National Research Council Canada - National Science Library

    Sopok, Samuel

    1997-01-01

    The MACE gun barrel thermochemical erosion modeling code addresses wall degradations due to transformations, chemical reactions, and cracking coupled with pure mechanical erosion for the 25-mm M242/M791 gun system...

  15. 24 CFR 242.47 - Insured advances for building components stored off-site.

    Science.gov (United States)

    2010-04-01

    ... HOUSING ACT AND OTHER AUTHORITIES MORTGAGE INSURANCE FOR HOSPITALS Construction § 242.47 Insured advances... only for components stored off-site in a quantity required to permit uninterrupted installation at the...

  16. 1998 Annual Cathodic Protection Survey Report for the 242-A Evaporator Area

    International Nuclear Information System (INIS)

    BOWMAN, T.J.

    1999-01-01

    This report is the second annual cathodic protection report for the 242-A evaporator. The report documents and trends annual polarization survey data, rectifier inspection data, and continuity data from 1994 through mid-1999

  17. 29 CFR 779.242 - Goods that “have been moved in” commerce.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 3 2010-07-01 2010-07-01 false Goods that âhave been moved inâ commerce. 779.242 Section... Commerce by Any Person § 779.242 Goods that “have been moved in” commerce. For the purpose of section 3(s), goods will be considered to “have been moved * * * in commerce” when they have moved across State lines...

  18. Process Control Plan for 242-A Evaporator Campaign January 2001

    International Nuclear Information System (INIS)

    LE, E.Q.

    2001-01-01

    Wastewater stored in 104-AW that was generated during the terminal cleanout of the PUREX facility is the primary feed to be processed during the 242-A Evaporator Campaign 01-01, Approximately 801,600 gallons of 104-AW waste was transferred to feed tank 102-AW at the end of January 2001, in preparation for the campaign. The total feed volume that will be processed during Campaign 01-01 is 8 15,200 gallons, which includes the waste from 104-AW and residual waste from the previous evaporator campaign, 00-01, Additional feed will be generated during the pre-campaign cold run and processed during campaign 01-01. Based on characterization data from 104-AW feed waste 'and the evaluation of waste processability presented in Section 5 of this PCP, Campaign 01-01 does not pose any unacceptable risks to the facility, safety, environmental, human health offsite, or onsite personnel. Evaporator Campaign 01-01 is essential in supporting the River Protection Project (RPP) to maintaining its critical mission schedule and regulator commitments for tank waste systems. Several of RPP critical activities requiring completion of Campaign 01-01 by April 1, 2001 are highlighted below. Availability of DST space: Additional tank space that will be made available by this campaign is needed to support the continued interim stabilization of Single-Shell Tanks (SSTs). This additional space will also be used to move waste among Double-Shell Tanks (DSTs) to support the demonstrations of SST waste retrieval. DST life extension: An electrical outage in the AW Tank Farm is scheduled to begin following completion of the Campaign 01-01. This outage is a critical step in identifying and completing life extension upgrades to the DST systems. DST upgrades: Project W-314 plans significant upgrades to the AW Tank Farm to retrieve and supply waste feed to the Waste Treatment (Vitrification) Plant using a system that complies with current environmental requirements. These upgrades will commence on

  19. Determination of the neutron-induced fission cross section of {sup 242}Pu; Bestimmung des neutroneninduzierten Spaltquerschnitts von {sup 242}Pu

    Energy Technology Data Exchange (ETDEWEB)

    Koegler, Toni Joerg

    2016-04-26

    Neutron induced fission cross sections of actinides like the Pu-isotopes are of relevance for the development of nuclear transmutation technologies. For {sup 242}Pu, current uncertainties are of around 21%. Sensitivity studies show that the total uncertainty has to be reduced to below 5% to allow for reliable neutron physics simulations. This challenging task was performed at the neutron time-of-flight facility of the new German National Center for High Power Radiation Sources at HZDR, Dresden. Within the TRAKULA project, thin, large and homogeneous deposits of {sup 235}U and {sup 242}Pu have been produced successfully. Using two consecutively placed fission chambers allowed the determination of the neutron induced fission cross section of {sup 242}Pu relative to {sup 235}U. The areal density of the Plutonium targets was calculated using the measured spontaneous fission rate. Experimental results of the fast neutron induced fission of {sup 242}Pu acquired at nELBE will be presented and compared to recent experiments and evaluated data. Corrections addressing the neutron scattering are discussed by using results of different neutron transport simulations (Geant 4, MCNP 6 and FLUKA).

  20. Non-destructive assay of 242Pu by resonance neutron capture

    International Nuclear Information System (INIS)

    Kane, W.R.; Lu, Ming-Shih; Aronson, A.; Forman, L.; Vanier, P.E.

    1995-01-01

    For the accurate assay of plutonium by neutron correlation measurements, especially for material derived from high-burnup reactor fuel, the content of 242 Pu in a sample must be determined. Since 242 Pu has a long half-life (387,000 yr) and decays to 238 U by alpha particle emission with the accompanying emission of only weak, low-energy gamma rays, gamma-ray spectrometry methods which are ordinarily employed to determine the isotopic composition of a plutonium sample are not feasible for 242 Pu. The existence of a resonance in the neutron capture cross section of 242 Pu at an energy of 2.67 electron volts (eV) with a large (72, 000 barn) cross section affords the possibility for the quantitative assay of this isotope by epithermal neutron capture. Essential for this purpose is an appropriately designed geometry of neutron moderators and absorbers which will provide maximum flux in the eV region while suppressing thermal neutron capture by the fissile plutonium isotopes. Signatures for neutron capture in 242 Pu include the decay of 243 Pu (4.9 hr), prompt capture gamma rays (total energy 5.034 MeV), and the decay of an isomeric state (330 nanosecond). Experiments to determine the feasibility of this approach are currently in progress

  1. Estimation of radioactive contaminants in Cm242 and Cm244 isotopic fuels

    International Nuclear Information System (INIS)

    Terent'ev, V.P.; Makarenko, A.I.

    1972-01-01

    The radiation properties of Cm 242 and Cm 244 preparations and the effect on them of possible contaminants are considered. One of the most important requirements for K alpha active fuels for radioisotope thermoelectric batteries is ensuring a low ionizing radiation background. In determining the effect of impurities on the radiation properties of a preparation, quantitative evaluation of certain factors is sufficient. In a Cm 242 preparation it is possible to show that Am 241 and Cm 243 are undesirable impurities. The presence of Am 241 increases the soft gamma output by 20%. The presence of Cm 243 may double the dose rate from an unshielded preparation and increase the hard gamma output 10-fold. The properties of Cm 242 preparations deteriorate when Am 243 and Cm 243 are present

  2. Delisting strategy for the Hanford Site 242-A Evaporator PUREX Plant Condensate Treatment Facility

    International Nuclear Information System (INIS)

    1992-04-01

    This document describes the strategy that the US Department of Energy, Richland Field Office intends to use in preparing the delisting petition for the 242-A Evaporator/PUREX Plant Condensate Treatment Facility. Because the 242-A Evaporator/PUREX Plant Condensate Treatment Facility will not be operational until 1994, the delisting petition will be structured as an up-front petition based on the ''multiple waste treatment facility'' approach outline in the 1985 US Environmental Protection Agency's Petitions to Delist Hazardous Waste. The 242-A evaporator/PUREX Plant Condensate Treatment Facility effluent characterization data will not be available to support the delisting petition, because the delisting petition will be submitted to the US Environmental Protection Agency before start-up of the 242-A Evaporator/PUREX Plant Condensate Treatment Facility. Therefore, the delisting petition will be based on data collected during the pilot plant testing for the 242-A Evaporator/PUREX Plant Condensate Treatment Facility. This pilot plant testing will be conducted on synthetic waste. The composition of the synthetic waste will be based on: (1) constituents of regulatory concern, and (2) on process knowledge. The pilot plant testing will be performed to determine the removal efficiencies of the process equipment at concentrations greater than reasonably could be expected in the actual waste. This strategy document also describes the logic used to develop the synthetic waste, to develop the pilot plant testing program, and to prepare the delisting petition. This strategy document also described how full-scale operating data will be collected during initial operation of the 242-A Evaporator/PUREX Plant Condensate Treatment Facility to verify information presented in the delisting petition

  3. Fast-neutron-induced fission of 242Pu at nELBE

    Directory of Open Access Journals (Sweden)

    Kögler Toni

    2017-01-01

    Full Text Available The fast neutron-induced fission cross section of 242Pu was determined in the range of 0.5 MeV to 10 MeV relative to 235U(n,f at the neutron time-of-flight facility nELBE. The number of target nuclei was calculated by means of measuring the spontaneous fission rate of 242Pu. Neutron transport simulations with Geant4 and MCNP6 are used to correct the relative cross section for neutron scattering. The determined results are in good agreement with current experimental and evaluated data sets.

  4. Californium-252 Program Equipment Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Chattin, Fred Rhea [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wilson, Kenton [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ezold, Julie G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-12-01

    To successfully continue the 252Cf production and meet the needs of the customers, a comprehensive evaluation of the Building 7920 processing equipment was requested to identify equipment critical to the operational continuity of the program.

  5. Californium Recovery from Palladium Wire

    Energy Technology Data Exchange (ETDEWEB)

    Burns, Jon D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2014-08-01

    The recovery of 252Cf from palladium-252Cf cermet wires was investigated to determine the feasibility of implementing it into the cermet wire production operation at Oak Ridge National Laboratory’s Radiochemical Engineering Development Center. The dissolution of Pd wire in 8 M HNO3 and trace amounts of HCl was studied at both ambient and elevated temperatures. These studies showed that it took days to dissolve the wire at ambient temperature and only 2 hours at 60°C. Adjusting the ratio of the volume of solvent to the mass of the wire segment showed little change in the kinetics of dissolution, which ranged from 0.176 mL/mg down to 0.019 mL/mg. A successful chromatographic separation of 153Gd, a surrogate for 252Cf, from Pd was demonstrated using AG 50x8 cation exchange resin with a bed volume of 0.5 mL and an internal diameter of 0.8 cm.

  6. Possibility of obtaining enriched americium-242g by the elution of recoil atoms from zeolite

    Energy Technology Data Exchange (ETDEWEB)

    Shafiev, A I; Vityutnev, V M; Ivanov, V M; Yakovlev, G N

    1974-12-31

    On the example of production the possibility of obtaining enriched actinide isotopes by the elution of recotl atoms with the use of a zeolite- americium-241 target was shown. The enrichment factor and the recoil atoms of / sup 242g/Am yield depend on preliminary target treatment and solution composition used for elution. (auth)

  7. In Vitro Probiotic Properties of Lactobacillus salivarius MG242 Isolated from Human Vagina.

    Science.gov (United States)

    Kang, Chang-Ho; Han, Seul Hwa; Kim, YongGyeong; Paek, Nam-Soo; So, Jae-Seong

    2017-08-31

    Vulvovaginal candidiasis (VVC) is a very common infection worldwide that is mainly caused by Candida albicans. In a previous study, we showed that Lactobacillus salivarius MG242 has anti-Gardnerella vaginalis activity. In this study, we investigated the potential of using L. salivarius MG242 for biocontrol of C. albicans. In line with the results from a spot overlay assay, MG242 inhibited the growth of C. albicans by 99.99 ± 0.01% in co-culture, suggesting that L. salivarius MG242 has the potential to be developed into a probiotic formula to treat or prevent VVC. Accelerated storage tests using dehydrated live cell powder at 50, 60, and 70 °C were performed, and the results showed that immobilization with 10% skim milk effectively increased the thermal resistance of entrapped microorganisms, resulting in sevenfold longer shelf-life than the control (in PBS). Lower storage temperatures also increased the shelf-life up to 8.31 months.

  8. Determination of the neutron-induced fission cross section of 242Pu

    International Nuclear Information System (INIS)

    Koegler, Toni Joerg

    2016-01-01

    Neutron induced fission cross sections of actinides like the Pu-isotopes are of relevance for the development of nuclear transmutation technologies. For 242 Pu, current uncertainties are of around 21%. Sensitivity studies show that the total uncertainty has to be reduced to below 5% to allow for reliable neutron physics simulations. This challenging task was performed at the neutron time-of-flight facility of the new German National Center for High Power Radiation Sources at HZDR, Dresden. Within the TRAKULA project, thin, large and homogeneous deposits of 235 U and 242 Pu have been produced successfully. Using two consecutively placed fission chambers allowed the determination of the neutron induced fission cross section of 242 Pu relative to 235 U. The areal density of the Plutonium targets was calculated using the measured spontaneous fission rate. Experimental results of the fast neutron induced fission of 242 Pu acquired at nELBE will be presented and compared to recent experiments and evaluated data. Corrections addressing the neutron scattering are discussed by using results of different neutron transport simulations (Geant 4, MCNP 6 and FLUKA).

  9. 48 CFR 1252.242-70 - Dissemination of information-educational institutions.

    Science.gov (United States)

    2010-10-01

    ... Provisions and Clauses 1252.242-70 Dissemination of information—educational institutions. As prescribed in (TAR) 48 CFR 1242.7000(a), insert the following clause: Dissemination of Information—Educational... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Dissemination of...

  10. Estimation of 242Cm neutron cross sections for total file creation

    International Nuclear Information System (INIS)

    Bakhanovich, L.A.; Klepatskij, A.B.; Maslov, V.M.; Porodzinskij, Yu.V.; Sukhovitskij, E.Sh.

    1989-01-01

    Description of evaluation of 242 Cm neutron cross sections in 10 -5 eV-20 MeV energy range is given. Due to the lack of experimental data the evaluation is largely based on the application of theoretical models and systematics. The data obtained are compared to evaluations by other authors. 10 refs.; 2 figs.; 2 tabs

  11. Yields of correlated fragment pairs and neutron multiplicity in spontaneous fission of {sup 242}Pu

    Energy Technology Data Exchange (ETDEWEB)

    Veselsky, M.; Kliman, J.; Morhaccaron, M. [Institute of Physics of Slovak Academy of Sciences, Dubravska 9, 84228 Bratislava (Slovakia); Ramayya, A.V.; Kormicki, J.; Daniel, A.V. [Physics Department, Vanderbilt University, Nashville (United States)] Rasmussen, J.O. [Lawrence Berkeley National Laboratory, Berkeley (United States)] Stoyer, M.A. [Lawrence Livermore National Laboratory, Livermore (United States); Daniel, A.V.; Popeko, G.S.; Oganessian, Yu. Ts. [Joint Institute for Nuclear Research, Dubna (Russia)] Greiner, W. [Institut fur Theoretische Physik, J. W. Goethe Universitaet, Frankfurt a. M. (Germany); Aryaeinejad, R. [Idaho National Engineering Laboratory, Idaho Falls (United States)

    1998-10-01

    Yields of correlated fragment pairs were obtained in spontaneous fission of {sup 242}Pu. Charge, mass and neutron multiplicity distributions of fragment pairs were determined and compared to available data. The yield of cold fission without neutron emission was determined to about 10{percent} for the set of observed correlated fragment pairs. {copyright} {ital 1998 American Institute of Physics.}

  12. 17 CFR 242.602 - Dissemination of quotations in NMS securities.

    Science.gov (United States)

    2010-04-01

    ... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Dissemination of quotations in... FUTURES Regulation Nms-Regulation of the National Market System § 242.602 Dissemination of quotations in... establish and maintain procedures and mechanisms for collecting bids, offers, quotation sizes, and aggregate...

  13. 48 CFR 1852.242-73 - NASA contractor financial management reporting.

    Science.gov (United States)

    2010-10-01

    ... Provisions and Clauses 1852.242-73 NASA contractor financial management reporting. As prescribed in 1842.7202, insert the following clause: NASA Contractor Financial Management Reporting (NOV 2004) (a) The Contractor... instructions in NASA Procedures and Guidelines (NPR) 9501.2, NASA Contractor Financial Management Reporting...

  14. 77 FR 55800 - Foreign-Trade Zone 242-Boundary County, ID; Application for Subzone AREVA Enrichment Services...

    Science.gov (United States)

    2012-09-11

    ... DEPARTMENT OF COMMERCE Foreign-Trade Zones Board [B-68-2012] Foreign-Trade Zone 242--Boundary County, ID; Application for Subzone AREVA Enrichment Services, LLC; Bonneville County, ID An application... FTZ 242, requesting special-purpose subzone status for the facility of AREVA Enrichment Services, LLC...

  15. Sequence and batch language programs and alarm related C Programs for the 242-A MCS

    International Nuclear Information System (INIS)

    Berger, J.F.

    1996-01-01

    A Distributive Process Control system was purchased by Project B-534, 242-A Evaporator/Crystallizer Upgrades. This control system, called the Monitor and Control system (MCS), was installed in the 242-A evaporator located in the 200 East Area. The purpose of the MCS is to monitor and control the Evaporator and monitor a number of alarms and other signals from various Tank Farm facilities. Applications software for the MCS was developed by the Waste Treatment Systems Engineering (WTSE) group of Westinghouse. The standard displays and alarm scheme provide for control and monitoring, but do not directly indicate the signal location or depict the overall process. To do this, WTSE developed a second alarm scheme

  16. 242Pu: Preliminary evaluation with consideration of 240Pu, and some sensitivity results

    International Nuclear Information System (INIS)

    Jary, J.; Lagrange, C.; Philis, C.

    1978-01-01

    A preliminary evaluation of 242 Pu nuclear data is presented for the neutron energy range from 10 keV to 20 MeV. The fission cross section is based upon recent experimental measurements on 242 Pu. The remaining cross sections have been calculated using various nuclear models with parameters obtained mainly by both fits on 240 Pu experimental data and general reflexions on the actinides. Particular care has been taken of the direct interactions. The laws of secondary neutron energy spectra and the average number of neutrons produced per fission have been evaluated. The results have been placed in ENDF/BIV format and combined with the low energy region of ENDF/BIV MAT = 1161 data to make complete the evaluation over the whole energy range 10 -5 eV - 20 MeV. Finally, the sensitivities of some of these nuclear data available for reactor calculations are given in terms of the variation of the calculated critical masses

  17. Separation negatives from Kodak film types SO-368 and SO-242

    Science.gov (United States)

    Weinstein, M. S.

    1972-01-01

    Two master resolution friskets were produced on Kodak film types SO-368 and SO-242. These target masters consisted of 21 density steps with three-bar resolution targets at five modulation levels within each step. The target masters were contact printed onto Kodak separation negative film, type 4131, using both a contact printing frame and enlarger as one method of exposure, and a Miller-Holzwarth contact printer as the other exposing device. Red, green, and blue Wratten filters were used to filter the exposing source. Tray processing was done with DK-50 developer diluted 1:2 at a temperature of 70 F. The resolution values were read for the SO-368 and SO-242 target masters, and the red, green, and blue separation negatives.

  18. Temperature thresholds for surface blistering of platinum and stainless steel exposed to curium-242 alpha radiations

    International Nuclear Information System (INIS)

    McDonell, W.R.; Dillich, S.

    1981-01-01

    Implantation of helium in materials exposed to alpha-emitting radionuclides such as 242 Cm causes surface blistering at elevated temperatures. The temperature thresholds for such blistering are of practical importance to the selection of suitable container materials for radionuclides, and are of fundamental interest with regard to the mechanisms of helium blistering of materials in radiation environments. The purpose of this investigation was to establish temperature thresholds for surface blistering of platinum and stainless-steel container materials by post-irradiation heating of specimens exposed at room temperature to alpha particles from an external 242 Cm source. These thresholds were compared with (1) the analogous temperature thresholds for surface blistering of materials exposed to external beams of accelerator helium ions, and (2) thresholds for swelling and grain-boundary cracking of materials in which helium is generated internally by (n,α) reactions during reactor exposures

  19. [Replication of Streptomyces plasmids: the DNA nucleotide sequence of plasmid pSB 24.2].

    Science.gov (United States)

    Bolotin, A P; Sorokin, A V; Aleksandrov, N N; Danilenko, V N; Kozlov, Iu I

    1985-11-01

    The nucleotide sequence of DNA in plasmid pSB 24.2, a natural deletion derivative of plasmid pSB 24.1 isolated from S. cyanogenus was studied. The plasmid amounted by its size to 3706 nucleotide pairs. The G-C composition was equal to 73 per cent. The analysis of the DNA structure in plasmid pSB 24.2 revealed the protein-encoding sequence of DNA, the continuity of which was significant for replication of the plasmid containing more than 1300 nucleotide pairs. The analysis also revealed two A-T-rich areas of DNA, the G-C composition of which was less than 55 per cent and a DNA area with a branched pin structure. The results may be of value in investigation of plasmid replication in actinomycetes and experimental cloning of DNA with this plasmid as a vector.

  20. Optical and statistical model calculation of the americium 242m capture cross section

    International Nuclear Information System (INIS)

    Tellier, Henry.

    1981-04-01

    The capture cross sections of Am 242m can be deduced from resonances analysis at low energy and computed with theoretical models at high energy. In this work, a coherent set of cross sections which reproduced the experimental values of the fission cross sections is computed. These calculations were performed for an energy of the incoming neutron between 1 keV and 1 MeV

  1. Total cross section of 242Pu between 0.7 and 170 MeV

    International Nuclear Information System (INIS)

    Moore, M.S.; Lisowski, P.W.; Morgan, G.L.; Auchampaugh, G.F.

    1979-01-01

    Various evaluations of the neutron cross sections of 242 Pu lead to widely different predictions of bulk neutronics properties such as critical mass. These evaluations also show rather different behavior of the energy dependence of the total cross section. The total cross section of 242 Pu from 0.7 to 170 MeV was measured to a statistical accuracy of = 0.5% below 6 MeV, using 8 g of high purity material and the WNR pulsed neutron facility. Recent evaluations by Madland and Young and by Lagrange and Jary are found to be reasonably consistent with the data obtained. Best agreement, however, is found by using a relationship between the total cross sections for 238 U, 239 Pu, and 235 U. The remarkable accuracy of this description for 242 Pu suggests that it could be extended to other deformed actinides for which inadequate amounts of material exist for direct measurements of sigma/sub T/ in the MeV region, as an evaluation constraint

  2. Critical mass calculations for 241Am, 242mAm and 243Am

    International Nuclear Information System (INIS)

    Dias, Hemanth; Tancock, Nigel; Clayton, Angela

    2003-01-01

    Criticality mass calculations are reported for 241 Am, 242m Am and 243 Am using the MONK and MCNP computer codes with the UKNDL, JEF-2.2, ENDF/B-VI and JENDL-3.2 nuclear data libraries. Results are reported for spheres of americium metal and dioxide in bare, water reflected and steel reflected systems. Comparison of results led to the identification of a serious inconsistency in the 241 Am ENDF/B-VI DICE library used by MONK - this demonstrates the importance of using different codes to verify critical mass calculations. The 241 Am critical mass estimates obtained using UKNDL and ENDF/B-VI show good agreement with experimentally inferred data, whilst both JEF-2.2 and JENDL-3.2 produce higher estimates of critical mass. The computed critical mass estimates for 242m Am obtained using ENDF/B-VI are lower than the results produced using the other nuclear data libraries - the ENDF/B-VI fission cross-section for 242m Am is significantly higher than the other evaluations in the fast region and is not supported by recent experimental data. There is wide variation in the computed 243 Am critical mass estimates suggesting that there is still considerable uncertainty in the 243 Am nuclear data. (author)

  3. Manganese determination om minerals by activation analysis, using the californium-252 as a neutron source; Determinacao de manganes em minerios, por analise por ativacao, usando californio-252 como fonte de neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Cardoso, Antonio

    1976-07-01

    Neutron Activation Analysis, using a Californium-252 neutron source, has been applied for the determination of manganese in ores such as pyrolusite, rodonite (manganese silicate)' and blending used in dry-batteries The favorable nuclear properties of manganese, such as high thermal neutron cross-section for the reaction {sup 55}Mn (n.gamma){sup 56} Mn, high concentration of manganese in the matrix and short half - life of {sup 56}Mn, are an ideal combination for non-destructive analysis of manganese in ores. Samples and standards of manganese dioxide were irradiated for about 20 minutes, followed by a 4 to 15 minutes decay and counted in a single channel pulse-height discrimination using a NaI(Tl) scintillation detector. Counting time was equal to 10 minutes. The interference of nuclear reactions {sup 56}Fe(n,p){sup 56}Mn and {sup 59} Co (n, {alpha}){sup 56} were studied, as well as problems in connection with neutron shadowing during irradiation, gamma-rays attenuation during counting and influence of granulometry of samples. One sample,was also analysed by wet-chemical method (sodium bismuthate) in order to compare results. As a whole, i t was shown that the analytical method of neutron activation for manganese in ores and blending, is a method simple, rapid and with good precision and accuracy. (author)

  4. Design of a homogeneous subcritical nuclear reactor based on thorium with a source of californium 252; Diseno de un reactor nuclear subcritico homogeneo a base de Torio con una fuente de Californio 252

    Energy Technology Data Exchange (ETDEWEB)

    Delgado H, C. E.; Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas, Zac. (Mexico); Sajo B, L., E-mail: ce_delgado89@hotmail.com [Universidad Simon Bolivar, Laboratorio de Fisica Nuclear, Apdo. 89000, 1080A Caracas (Venezuela, Bolivarian Republic of)

    2015-10-15

    Full text: One of the energy alternatives to fossil fuels which do not produce greenhouse gases is the nuclear energy. One of the drawbacks of this alternative is the generation of radioactive wastes of long half-life and its relation to the generation of nuclear materials to produce weapons of mass destruction. An option to these drawbacks of nuclear energy is to use Thorium as part of the nuclear fuel which it becomes in U{sup 233} when capturing neutrons, that is a fissile material. In this paper Monte Carlo methods were used to design a homogeneous subcritical reactor based on thorium. As neutron reflector graphite was used. The reactor core is homogeneous and is formed of 70% light water as moderator, 12% of enriched uranium UO{sub 2}(NO{sub 3}){sub 4} and 18% of thorium Th(NO{sub 3}){sub 4} as fuel. To start the nuclear fission chain reaction an isotopic source of californium 252 was used with an intensity of 4.6 x 10{sup 7} s{sup -1}. In the design the value of the effective multiplication factor, whose value turned out k{sub eff} <1 was calculated. Also, the neutron spectra at different distances from the source and the total fluence were calculated, as well as the values of the ambient dose equivalent in the periphery of the reactor. (Author)

  5. Manganese determination om minerals by activation analysis, using the californium-252 as a neutron source; Determinacao de manganes em minerios, por analise por ativacao, usando californio-252 como fonte de neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Cardoso, Antonio

    1976-07-01

    Neutron Activation Analysis, using a Californium-252 neutron source, has been applied for the determination of manganese in ores such as pyrolusite, rodonite (manganese silicate)' and blending used in dry-batteries The favorable nuclear properties of manganese, such as high thermal neutron cross-section for the reaction {sup 55}Mn (n.gamma){sup 56} Mn, high concentration of manganese in the matrix and short half - life of {sup 56}Mn, are an ideal combination for non-destructive analysis of manganese in ores. Samples and standards of manganese dioxide were irradiated for about 20 minutes, followed by a 4 to 15 minutes decay and counted in a single channel pulse-height discrimination using a NaI(Tl) scintillation detector. Counting time was equal to 10 minutes. The interference of nuclear reactions {sup 56}Fe(n,p){sup 56}Mn and {sup 59} Co (n, {alpha}){sup 56} were studied, as well as problems in connection with neutron shadowing during irradiation, gamma-rays attenuation during counting and influence of granulometry of samples. One sample,was also analysed by wet-chemical method (sodium bismuthate) in order to compare results. As a whole, i t was shown that the analytical method of neutron activation for manganese in ores and blending, is a method simple, rapid and with good precision and accuracy. (author)

  6. Tumor markers CA19-9, CA242 and CEA in the diagnosis of pancreatic cancer: a meta-analysis.

    Science.gov (United States)

    Zhang, Yimin; Yang, Jun; Li, Hongjuan; Wu, Yihua; Zhang, Honghe; Chen, Wenhu

    2015-01-01

    Pancreatic cancer has the worst prognosis and early detection is crucial for improving patient prognosis. Therefore, we performed a meta-analysis to evaluate and compare the sensitivity and specificity of single test of CA19-9, CA242, and CEA, as well as combination test in pancreatic cancer detection. We searched PubMed, Embase, Medline, and Wanfang databases for studies that evaluated the diagnostic validity of CA19-9, CA242, and CEA between January 1990 and September 2014. Data were analyzed by Meta-Disc and STATA software. A total of 21 studies including 3497 participants, which fulfilled the inclusion criteria were considered for analysis. The pooled sensitivities for CA19-9, CA242, and CEA were 75.4 (95% CI: 73.4-77.4), 67.8 (95% CI: 65.5-70), and 39.5 (95% CI: 37.3-41.7), respectively. The pooled specificities of CA19-9, CA242, and CEA were 77.6 (95% CI: 75.4-79.7), 83 (95% CI: 81-85), and 81.3 (95% CI: 79.3-83.2), respectively. Parallel combination of CA19-9+CA242 has a higher sensitivity (89, 95% CI: 80-95) without impairing the specificity (75, 95% CI: 67-82). Our meta-analysis showed that CA242 and CA19-9 have better performance in the diagnosis of pancreatic cancer than CEA. Furthermore, parallel combination test of CA19-9+CA242 could be of better diagnostic value than individual CA242 or CA19-9 test.

  7. Project C-018H, 242-A Evaporator/PUREX Plant Process Condensate Treatment Facility, functional design criteria. Revision 3

    International Nuclear Information System (INIS)

    Sullivan, N.

    1995-01-01

    This document provides the Functional Design Criteria (FDC) for Project C-018H, the 242-A Evaporator and Plutonium-Uranium Extraction (PUREX) Plant Condensate Treatment Facility (Also referred to as the 200 Area Effluent Treatment Facility [ETF]). The project will provide the facilities to treat and dispose of the 242-A Evaporator process condensate (PC), the Plutonium-Uranium Extraction (PUREX) Plant process condensate (PDD), and the PUREX Plant ammonia scrubber distillate (ASD)

  8. Flurbiprofen benzyl nitrate (NBS-242) inhibits the growth of A-431 human epidermoid carcinoma cells and targets β-catenin.

    Science.gov (United States)

    Nath, Niharika; Liu, Xiaoping; Jacobs, Lloydine; Kashfi, Khosrow

    2013-01-01

    The Wnt/β-catenin/T cell factor (TCF) signaling pathway is important in the development of nonmelanoma skin cancers (NMSCs). Nitric-oxide-releasing nonsteroidal anti-inflammatory drugs (NO-NSAIDs) are chemopreventive agents consisting of a traditional NSAID attached to an NO-releasing moiety through a chemical spacer. Previously we showed that an aromatic spacer enhanced the potency of a particular NO-NSAID compared to an aliphatic spacer. We synthesized an NO-releasing NSAID with an aromatic spacer (flurbiprofen benzyl nitrate, NBS-242), and using the human skin cancer cell line A-431, we evaluated its effects on cell kinetics, Wnt/β-catenin, cyclin D1, and caspase-3. NBS-242 inhibited the growth of A-431 cancer cells, being ~15-fold more potent than flurbiprofen and up to 5-fold more potent than NO-flurbiprofen with an aliphatic spacer, the half maximal inhibitory concentrations (IC50) for growth inhibition being 60 ± 4 μM, 320 ± 20 μM, and 880 ± 65 μM for NBS-242, NO-flurbiprofen, and flurbiprofen, respectively. This effect was associated with inhibition of proliferation, accumulation of cells in the G0/G1 phase of the cell cycle, and an increase in apoptotic cell population. NBS-242 cleaved β-catenin both in the cytoplasm and the nucleus of A-431 cells. NBS-242 activated caspase-3 whose activation was reflected in the cleavage of procaspase-3. To test the functional consequence of β-catenin cleavage, we determined the expression of cyclin D1, a Wnt-response gene. NBS-242 reduced cyclin D1 levels in a concentration dependent manner. These findings establish a strong inhibitory effect of NBS-242 in A-431 human epidermoid carcinoma cells. NBS-242 modulates parameters that are important in determining cellular mass.

  9. Functional design criteria for the 242-A evaporator and PUREX [Plutonium-Uranium Extraction] Plant condensate interim retention basin

    International Nuclear Information System (INIS)

    Cejka, C.C.

    1990-01-01

    This document contains the functional design criteria for a 26- million-gallon retention basin and 10 million gallons of temporary storage tanks. The basin and tanks will be used to store 242-A Evaporator process condensate, the Plutonium-Uranium Extraction (PUREX) Plant process distillate discharge stream, and the PUREX Plant ammonia scrubber distillate stream. Completion of the project will allow both the 242-A Evaporator and the PUREX Plant to restart. 4 refs

  10. 242-A Evaporator/Liquid Effluent Retention Facility data quality objectives

    International Nuclear Information System (INIS)

    Von Bargen, B.H.

    1994-01-01

    The purpose of data quality objectives (DQO) is to determine the most cost effective methods of gathering the essential data necessary to make decisions to support successful operation of the facility. The essential data is defined by such information as sample amount, sample location, required analyses, and how sampling and analyses are performed. Successful operation is defined as meeting the campaign objectives while operating within established requirements. This DQO document addresses that portion of the system from 242-A Evaporator candidate feed tanks through discharge of process condensate to the Liquid Effluent Retention of Facility (LERF). Later revisions will incorporate and integrate the entire system, including the Effluent Treatment Facility (ETF)

  11. 242-A Evaporator/Liquid Effluent Retention Facility data quality objectives

    Energy Technology Data Exchange (ETDEWEB)

    Von Bargen, B.H.

    1994-09-29

    The purpose of data quality objectives (DQO) is to determine the most cost effective methods of gathering the essential data necessary to make decisions to support successful operation of the facility. The essential data is defined by such information as sample amount, sample location, required analyses, and how sampling and analyses are performed. Successful operation is defined as meeting the campaign objectives while operating within established requirements. This DQO document addresses that portion of the system from 242-A Evaporator candidate feed tanks through discharge of process condensate to the Liquid Effluent Retention of Facility (LERF). Later revisions will incorporate and integrate the entire system, including the Effluent Treatment Facility (ETF).

  12. Process control plan for 242-A Evaporator Campaign 95-1

    Energy Technology Data Exchange (ETDEWEB)

    Le, E.Q.; Guthrie, M.D.

    1995-05-18

    The wastes from tanks 106-AP, 107-AP, and 106-AW have been selected to be candidate feed wastes for Evaporator Campaign 95-1. The wastes in tank 106-AP and 107-AP are primarily from B-Plant strontium processing and PUREX neutralized cladding removal, respectively. The waste in tank 106-AW originated primarily from the partially concentrated product from 242-A Evaporator Campaign 94-2. Approximately 8.67 million liters of waste from these tanks will be transferred to tank 102-AW during the campaign. Tank 102-AW is the dedicated waste feed tank for the evaporator and currently contains 647,000 liters of processable waste. The purpose of the 242-A Evaporator Campaign 95-1 Process Control Plan (hereafter referred to as PCP) is to certify that the wastes in tanks 106-AP, 107-AP, 102-AW, and 106-AW are acceptable for processing through evaporator and provide a general description of process strategies and activities which will take place during Campaign 95-1. The PCP also summarizes and presents a comprehensive characterization of the wastes in these tanks.

  13. Process control plan for 242-A Evaporator Campaign 95-1

    International Nuclear Information System (INIS)

    Le, E.Q.; Guthrie, M.D.

    1995-01-01

    The wastes from tanks 106-AP, 107-AP, and 106-AW have been selected to be candidate feed wastes for Evaporator Campaign 95-1. The wastes in tank 106-AP and 107-AP are primarily from B-Plant strontium processing and PUREX neutralized cladding removal, respectively. The waste in tank 106-AW originated primarily from the partially concentrated product from 242-A Evaporator Campaign 94-2. Approximately 8.67 million liters of waste from these tanks will be transferred to tank 102-AW during the campaign. Tank 102-AW is the dedicated waste feed tank for the evaporator and currently contains 647,000 liters of processable waste. The purpose of the 242-A Evaporator Campaign 95-1 Process Control Plan (hereafter referred to as PCP) is to certify that the wastes in tanks 106-AP, 107-AP, 102-AW, and 106-AW are acceptable for processing through evaporator and provide a general description of process strategies and activities which will take place during Campaign 95-1. The PCP also summarizes and presents a comprehensive characterization of the wastes in these tanks

  14. Tumour associated antigen CA-50, CA-242 immunoradiometric assay (IRMA) in genitourinary malignancy and gastrointestinal carcinoma early diagnosis

    International Nuclear Information System (INIS)

    Chen Zhizhou.

    1992-04-01

    Tumour markers CA-50 and CA-242 were measured by immunometric assay (IRMA) to investigate their usefulness in the diagnosis of cancer of the pancreas, biliary tract, liver, breast, lung, gastrointestinal and genitourinary systems. The cutoff points, derived from studies on normal subjects and those with proven benign disease, were 20 u/ml and 12 u/ml for CA-50 and CA-242 respectively. Both markers were found to be generally useful with significant differences between malignant and non malignant disease. The highest positive rates, were found in cancers of the pancreas and gall bladder. The overall rate of false positives was low. It is concluded that measurements of CA-50 and CA-242 are useful in the detection of malignancy, particularly of the pancreas and biliary tract. 2 figs, 2 tabs

  15. Determination of transfer coefficient between oyster mushrooms and cultivating medium using 242Pu and 241Am tracers

    International Nuclear Information System (INIS)

    Galanda, D.; Matel, L.

    2003-01-01

    The present work is devoted to an estimation of the transfer coefficient between reared oyster mushrooms and their support die, which was injected with known activity of Am-241 and Pu-242. After 2 months when we get the reared mushrooms of cane oyster mushrooms were dried and prepared by liquid extraction with Aliquat 336. The samples were measured by α-spectrometry. The results of activity Am-241 and Pu-242 in the mushrooms body and residual activity in the support were detected and calculated. (authors)

  16. Flurbiprofen benzyl nitrate (NBS-242 inhibits the growth of A-431 human epidermoid carcinoma cells and targets ß-catenin

    Directory of Open Access Journals (Sweden)

    Nath N

    2013-05-01

    Full Text Available Niharika Nath,1,2 Xiaoping Liu,3 Lloydine Jacobs,1 Khosrow Kashfi1,3 1Department of Physiology, Pharmacology, and Neuroscience, Sophie Davis School of Biomedical Education, City University of New York Medical School, New York, NY, USA; 2Department of Life Sciences, New York Institute of Technology, New York, NY, USA; 3Division of Cancer Prevention, Department of Medicine, Stony Brook University, Stony Brook, NY, USA Background: The Wnt/ß-catenin/T cell factor (TCF signaling pathway is important in the development of nonmelanoma skin cancers (NMSCs. Nitric-oxide-releasing nonsteroidal anti-inflammatory drugs (NO-NSAIDs are chemopreventive agents consisting of a traditional NSAID attached to an NO-releasing moiety through a chemical spacer. Previously we showed that an aromatic spacer enhanced the potency of a particular NO-NSAID compared to an aliphatic spacer. Methods: We synthesized an NO-releasing NSAID with an aromatic spacer (flurbiprofen benzyl nitrate, NBS-242, and using the human skin cancer cell line A-431, we evaluated its effects on cell kinetics, Wnt/ß-catenin, cyclin D1, and caspase-3. Results: NBS-242 inhibited the growth of A-431 cancer cells, being ~15-fold more potent than flurbiprofen and up to 5-fold more potent than NO-flurbiprofen with an aliphatic spacer, the half maximal inhibitory concentrations (IC50 for growth inhibition being 60 ± 4 µM, 320 ± 20 µM, and 880 ± 65 µM for NBS-242, NO-flurbiprofen, and flurbiprofen, respectively. This effect was associated with inhibition of proliferation, accumulation of cells in the G0/G1 phase of the cell cycle, and an increase in apoptotic cell population. NBS-242 cleaved ß-catenin both in the cytoplasm and the nucleus of A-431 cells. NBS-242 activated caspase-3 whose activation was reflected in the cleavage of procaspase-3. To test the functional consequence of ß-catenin cleavage, we determined the expression of cyclin D1, a Wnt-response gene. NBS-242 reduced cyclin D1 levels

  17. Determination of the fast-neutron-induced fission cross-section of 242Pu at nELBE

    Science.gov (United States)

    Kögler, Toni; Beyer, Roland; Junghans, Arnd R.; Schwengner, Ronald; Wagner, Andreas

    2018-03-01

    The fast-neutron-induced fission cross section of 242Pu was determined in the energy range of 0.5 MeV to 10MeV at the neutron time-of-flight facility nELBE. Using a parallel-plate fission ionization chamber this quantity was measured relative to 235U(n,f). The number of target nuclei was thereby calculated by means of measuring the spontaneous fission rate of 242Pu. An MCNP 6 neutron transport simulation was used to correct the relative cross section for neutron scattering. The determined results are in good agreement with current experimental and evaluated data sets.

  18. Determination of the fast-neutron-induced fission cross-section of 242Pu at nELBE

    Directory of Open Access Journals (Sweden)

    Kögler Toni

    2018-01-01

    Full Text Available The fast-neutron-induced fission cross section of 242Pu was determined in the energy range of 0.5 MeV to 10MeV at the neutron time-of-flight facility nELBE. Using a parallel-plate fission ionization chamber this quantity was measured relative to 235U(n,f. The number of target nuclei was thereby calculated by means of measuring the spontaneous fission rate of 242Pu. An MCNP 6 neutron transport simulation was used to correct the relative cross section for neutron scattering. The determined results are in good agreement with current experimental and evaluated data sets.

  19. Measurement of the neutron-induced fission cross-section of 240,242Pu

    International Nuclear Information System (INIS)

    Salvador-Castineira, P.; Hambsch, F.J.; Brys, T.; Oberstedt, S.; Vidali, M.; Pretel, C.

    2014-01-01

    Fast spectrum neutron-induced fission cross-section data for transuranic isotopes are in high demand in the nuclear data community. In particular, highly accurate data are needed for the new Generation-IV nuclear applications. The aim is to obtain precise neutron-induced fission cross-sections for 240 Pu and 242 Pu. In this context accurate data on spontaneous fission half-lives have also been measured. To minimise the total uncertainty on the fission cross-sections the detector efficiency has been studied in detail. Both isotopes have been measured using a twin Frisch-grid ionisation chamber (TFGIC) due to its superiority compared to other detector systems in view of radiation hardness, 2 x 2π solid angle coverage and very good energy resolution. (authors)

  20. The evaluation of the mass distribution data for 238U, 239Pu and 242Pu fission

    International Nuclear Information System (INIS)

    Liu Tingjin

    2002-01-01

    The mass distribution data for 238 U at E n =1.5, 5.5, 8.3, 11.3, 14.9, 22.0, 27.5, 50.0, 99.5, 160.0 MeV, E p =20.0, 60.0 MeV 239 Pu at E n =0.17, 7.9, 14.5 MeV and 242 Pu at E n =15.1 MeV were evaluated and recommended based on the main available experimental data up to now. The experimental data were make necessary corrections and their errors were also made necessary adjustments. The problems concerned were discussed

  1. Operational test report for LERF Basin 242AL-44 integrity test

    International Nuclear Information System (INIS)

    Galioto, T.M.

    1994-01-01

    This operational test report documents the results of LERF operational testing per operational test procedure (OTP) TFPE-WP-0231, ''LERF Basin Integrity Testing.'' The primary purpose of the OTP was to resolve test exceptions generated as a result of TFPE-WP-0184. The TOP was prepared and performed in accordance with WHC-SD-534-OTP-002, ''Operational Test Plan for the 242-A Evaporator Upgrades and the Liquid Effluent Retention Facility.'' WHC-S-086, ''Specification for Operational Testing of the Liquid Effluent Retention Facility, Basin Integrity Testing,'' identified the test requirements and acceptance criteria. The completed, signed-off test procedure is contained in Appendix A. The test log is contained in Appendix B. Section 2.1 describes all the test exceptions written during performance of the Operational Test Procedure. The test revisions generated during the testing are discussed in Section 2.2. The dispositioned test exception forms are contained in Appendix C

  2. Fission cross section measurement of Am-242m using lead slowing-down spectrometer

    Energy Technology Data Exchange (ETDEWEB)

    Kai, Tetsuya; Kobayashi, Katsuhei; Yamamoto, Shuji; Fujita, Yoshiaki [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.; Kimura, Itsuro; Ohkawachi, Yasushi; Wakabayashi, Toshio

    1998-03-01

    By making use of double fission chamber and lead slowing-down spectrometer coupled to an electron linear accelerator, fission cross section for the {sup 242m}Am(n,f) reaction has been measured relative to that for the {sup 235}U(n,f) reaction in the energy range from 0.1 eV to 10 keV. The measured result was compared with the evaluated nuclear data appeared in ENDF/B-VI and JENDL-3.2, of which evaluated data were broadened by the energy resolution function of the spectrometer. Although the JENDL-3.2 data seem to be a little smaller than the present measurement, good agreement can be seen in the general shape and the absolute values. The ENDF/B-VI data are larger more than 50 % than the present values above 3 eV. (author)

  3. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 5

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 5) outlines the standards and requirements for the Fire Protection and Packaging and Transportation sections

  4. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 4) presents the standards and requirements for the following sections: Radiation Protection and Operations.

  5. High level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 6

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 6) outlines the standards and requirements for the sections on: Environmental Restoration and Waste Management, Research and Development and Experimental Activities, and Nuclear Safety.

  6. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Document (S/RID) is contained in multiple volumes. This document (Volume 2) presents the standards and requirements for the following sections: Quality Assurance, Training and Qualification, Emergency Planning and Preparedness, and Construction.

  7. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 2

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Document (S/RID) is contained in multiple volumes. This document (Volume 2) presents the standards and requirements for the following sections: Quality Assurance, Training and Qualification, Emergency Planning and Preparedness, and Construction

  8. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID)

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 3) presents the standards and requirements for the following sections: Safeguards and Security, Engineering Design, and Maintenance

  9. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID)

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 3) presents the standards and requirements for the following sections: Safeguards and Security, Engineering Design, and Maintenance.

  10. 25 CFR 1000.242 - What provisions relating to a construction program may be included in an AFA?

    Science.gov (United States)

    2010-04-01

    ..., DEPARTMENT OF THE INTERIOR ANNUAL FUNDING AGREEMENTS UNDER THE TRIBAL SELF-GOVERNMENT ACT AMENDMENTS TO THE INDIAN SELF-DETERMINATION AND EDUCATION ACT Construction § 1000.242 What provisions relating to a... specific provisions of the Office of Federal Procurement and Policy Act and Federal Acquisition Regulations...

  11. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 4

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 4) presents the standards and requirements for the following sections: Radiation Protection and Operations

  12. 17 CFR 242.603 - Distribution, consolidation, and display of information with respect to quotations for and...

    Science.gov (United States)

    2010-04-01

    ..., and display of information with respect to quotations for and transactions in NMS stocks. 242.603... with respect to quotations for and transactions in NMS stocks. (a) Distribution of information. (1) Any... source, that distributes information with respect to quotations for or transactions in an NMS stock to a...

  13. High level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 6

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 6) outlines the standards and requirements for the sections on: Environmental Restoration and Waste Management, Research and Development and Experimental Activities, and Nuclear Safety

  14. Determination of isotope fractionation effect using a double spike (242Pu+240Pu) during the mass spectrometric analysis of plutonium

    International Nuclear Information System (INIS)

    Chitambar, S.A.; Parab, A.R.; Khodade, P.S.; Jain, H.C.

    1986-01-01

    Isotope fractionation effect during the mass spectrometric analysis of plutonium has been investigated using a double spike ( 242 Pu+ 240 Pu) and the determination of concentration of plutonium in dissolver solution of irradiated fuel is reported. (author). 6 refs., 2 tables

  15. ? Tranzitornyy? neonatal'nyy diabet vsledstvie duplikatsii v 6-y khromosome [dup(6(q24.2q24.2 de novo

    Directory of Open Access Journals (Sweden)

    Ivan Ivanovich Dedov

    2002-06-01

    оксикозом во II половине, беременности. Роды на 41-42-й нед. Масса тела при рождении 2100 г, длина 49 см. На 19-м дне жизни в связи беспокойством, непрерывным плачем, отсутствием аппетита, белым налетом на языке ребенок был госпитализирован. При обследовании выявлена гипергликемия натощак (17- 25 ммоль/л, глюкозурия ? 1,5 %. Реакция на ацетон отрицательная. Диагностирован СД 1 типа, назначен инсулин 0,5 Ед 2 раза в сутки. В возрасте 1,5 мес. у девочки появились гипогликемии, доза инсулина была снижена до 0,5 Ед/сут. В связи с повторением гипогликемических состояний в возрасте 2 мес. мать самосто-ятельно отменила инсулин. При повторном поступлении в клинику в возрасте 14 лет: рост 157,9 см (25-50 перц., вес 36 кг (25 перц.. Гликированный гемоглобин А1с 12,6 % (норма до 6,4 %, HbAl 15,3 % (норма до 7,8 %. На глазном дне без отрицательной динамики. С-пептид 0,45 нг/мл (норма 1,1-3,2 нг/мл. Антитела к островковым клеткам и глютаматдекарбоксилазе не обнаружены. Результаты: Кариотип: 46,XX,dup(6(q24.2q24.2. У пациентки женский кариотип с дополнительным G-материалом в локусе 6q24.2 длинного плеча 6 хромосомы ? дупликация локуса 6q24.2, специфичная для ?транзиторного? нео

  16. Effect Of Cooling Rate On Thermal And Mechanical Properties Of Cu-%24.2Mn Alloy

    International Nuclear Information System (INIS)

    Celik, H.

    2010-01-01

    In this research, different heat and mechanical treatments have been applied to the Cu-%24.2Mn and some samples have been obtained from this alloy. On these samples, phase transformations have been formed by thermal and mechanical effect. Morphological, mechanical and crystallographic properties of the phase transformations have been examined by using different physical methods. Austenite phase has been obtained in the samples which have been applied slow and rapid cooling according to the SEM analysis. It has been observed that the grain size obtained by the rapid cooling is smaller than the grain size obtained by the slow cooling. Therefore, it has been concluded that the cooling process differences, changes the grain size of the alloy. Compression stress has been applied to the alloy in order to search the deformation effect on the austenite phase transformation. The structural features of the phase transformations have been examined. Slip lines and martensite structural were observed on the surface of the alloys after the deformation. Changes in phase structure of the alloy are also examined by means of XRD technique.

  17. FAST, LOW-IONIZATION EMISSION REGIONS OF THE PLANETARY NEBULA M2-42

    Energy Technology Data Exchange (ETDEWEB)

    Danehkar, A.; Parker, Q. A. [Department of Physics and Astronomy, Macquarie University, Sydney, NSW 2109 (Australia); Steffen, W., E-mail: ashkbiz.danehkar@cfa.harvard.edu [Instituto de Astronomía, Universidad Nacional Autónoma de México, C.P.22860, Ensenada (Mexico)

    2016-02-15

    Spatially resolved observations of the planetary nebula M2-42 (PN G008.2−04.8) obtained with the Wide Field Spectrograph on the Australian National University 2.3 m telescope have revealed the remarkable features of bipolar collimated jets emerging from its main structure. Velocity-resolved channel maps derived from the [N ii] λ6584 emission line disentangle different morphological components of the nebula. This information is used to develop a three-dimensional morpho-kinematic model, which consists of an equatorial dense torus and a pair of asymmetric bipolar outflows. The expansion velocity of about 20 km s{sup −1} is measured from the spectrum integrated over the main shell. However, the deprojected velocities of the jets are found to be in the range of 80–160 km s{sup −1} with respect to the nebular center. It is found that the mean density of the collimated outflows, 595 ± 125 cm{sup −3}, is five times lower than that of the main shell, 3150 cm{sup −3}, whereas their singly ionized nitrogen and sulfur abundances are about three times higher than those determined from the dense shell. The results indicate that the features of the collimated jets are typical of fast, low-ionization emission regions.

  18. Monitoring the fast neutrons in a high flux: The case for 242Pu fission chambers

    International Nuclear Information System (INIS)

    Filliatre, P.; Jammes, C.; Oriol, L.; Geslot, B.; Vermeeren, L.

    2009-01-01

    Fission chambers are widely used for on-line monitoring of neutron fluxes in irradiation reactors. A selective measurement of a component of interest of the neutron flux is possible in principle thanks to a careful choice of the deposit material. However, measuring the fast component is challenging when the flux is high (up to 10 15 n/cm 2 /s) with a significant thermal component. The main problem is that the isotopic content of a material selected for its good response to fast neutrons evolves with irradiation, so that the material is more and more sensitive to thermal neutrons. Within the framework of the FNDS (Fast Neutron Detector System) project, we design tools that simulate the evolution of the isotopic composition and fission rate for several deposits under any given flux. In the case of a high flux with a significant thermal component, 242 Pu is shown after a comprehensive study of all possibilities to be the best choice for measuring the fast component, as long as its purity is sufficient. If an estimate of the thermal flux is independently available, one can correct the signal for that component. This suggests a system of two detectors, one of which being used for such a correction. It is of very high interest when the detectors must be operated up to a high neutron fluence. (authors)

  19. Monitoring the fast neutrons in a high flux: The case for {sup 242}Pu fission chambers

    Energy Technology Data Exchange (ETDEWEB)

    Filliatre, P.; Jammes, C.; Oriol, L.; Geslot, B. [Commissariat a l' Energie Atomique, DEN/SPEX/LDCI, Centre de Cadarache, F-13108 Saint-Paul-lez-Durance (France); Vermeeren, L. [SCK-CEN, Boeretang 200, B-2400 Mol (Belgium)

    2009-07-01

    Fission chambers are widely used for on-line monitoring of neutron fluxes in irradiation reactors. A selective measurement of a component of interest of the neutron flux is possible in principle thanks to a careful choice of the deposit material. However, measuring the fast component is challenging when the flux is high (up to 10{sup 15} n/cm{sup 2}/s) with a significant thermal component. The main problem is that the isotopic content of a material selected for its good response to fast neutrons evolves with irradiation, so that the material is more and more sensitive to thermal neutrons. Within the framework of the FNDS (Fast Neutron Detector System) project, we design tools that simulate the evolution of the isotopic composition and fission rate for several deposits under any given flux. In the case of a high flux with a significant thermal component, {sup 242}Pu is shown after a comprehensive study of all possibilities to be the best choice for measuring the fast component, as long as its purity is sufficient. If an estimate of the thermal flux is independently available, one can correct the signal for that component. This suggests a system of two detectors, one of which being used for such a correction. It is of very high interest when the detectors must be operated up to a high neutron fluence. (authors)

  20. Engineering work plan for implementing the Process Condensate Recycle Project at the 242-A evaporator

    International Nuclear Information System (INIS)

    Haring, D.S.

    1995-01-01

    The 242-A Evaporator facility is used to reduce the volume of waste stored in the Hanford double shell tanks. This facility uses filtered raw water for cooling, de-entrainment pad sprays, pump seal water, and chemical tank make-up. Some of these uses result in the introduction of filtered raw water into the process, thus increasing the volume of waste requiring evaporation and subsequent treatment by the 200 East Effluent Treatment Facility. The pump seal water and the de-entrainment pad spray systems were identified as candidates for a waste minimization upgrade. This work plan describes the activities associated with the design, installation, testing and initial operation of the process condensate recycle system. Implementation of the process condensate recycle system will permit the use of process condensate in place of raw water for the de-entrainment pad sprays and pump seals. This will reduce the amount of low-level liquid waste and generated during facility operation through source reduction and recycling

  1. Neutron diffraction study of δ-alloy Pu{sup 242}–Ga aging

    Energy Technology Data Exchange (ETDEWEB)

    Somenkov, V.A. [National Research Center “Kurchatov Institute”, Moscow (Russian Federation); Blanter, M.S., E-mail: mike.blanter@gmail.com [Moscow State University of Instrumental Engineering and Information Science, Moscow (Russian Federation); Glazkov, V.P. [National Research Center “Kurchatov Institute”, Moscow (Russian Federation); Laushkin, A.V.; Orlov, V.K. [JSC VNIINM n.a. A.A. Bochvar, Moscow (Russian Federation)

    2014-09-15

    In this paper, we report on a continuing neutron diffraction study of the mean-square atom displacements occurring during the long-term self-irradiation of a Pu–Ga alloy. The measurements were performed at room temperature using the sample based on the isotope Pu{sup 242} with low neutron absorption cross-section to which the short-lived isotope Pu{sup 238} (1.4 wt.%) was added to accelerate self-irradiation. We obtain the maximum self-irradiation equivalent time of 35.5 years, 12 years longer than in our previous papers. In the entire range of self-irradiation time a single fcc phase is preserved. It was found that after the two stages of change in the mean-square displacements we observed earlier (rapid growth up to ∼5–6 equivalent years and a slow decline in the range of ∼6–25 years), comes a stage of stabilization (after ∼25 years). The stabilization can be explained by the emergence of a balance between the formation of point defects and their absorption by helium bubbles and dislocation loops which accumulated over time.

  2. Common variants on 8p12 and 1q24.2 confer risk of schizophrenia

    DEFF Research Database (Denmark)

    Shi, Yongyong; Li, Zhiqiang; Xu, Qi

    2011-01-01

    Schizophrenia is a severe mental disorder affecting ~1% of the world population, with heritability of up to 80%. To identify new common genetic risk factors, we performed a genome-wide association study (GWAS) in the Han Chinese population. The discovery sample set consisted of 3,750 individuals...... with schizophrenia and 6,468 healthy controls (1,578 cases and 1,592 controls from northern Han Chinese, 1,238 cases and 2,856 controls from central Han Chinese, and 934 cases and 2,020 controls from the southern Han Chinese). We further analyzed the strongest association signals in an additional independent cohort...... of 4,383 cases and 4,539 controls from the Han Chinese population. Meta-analysis identified common SNPs that associated with schizophrenia with genome-wide significance on 8p12 (rs16887244, P = 1.27 × 10(-10)) and 1q24.2 (rs10489202, P = 9.50 × 10(-9)). Our findings provide new insights...

  3. Measurement of the $^{242}$Pu(n,f) reaction cross-section at the CERN n_TOF facility

    CERN Document Server

    AUTHOR|(CDS)2080481; Kokkoris, Michael; Vlachoudis, Vasilis

    The accurate knowledge of relevant nuclear data, such as the neutron-induced fission cross sections of various plutonium isotopes and other minor actinides, is crucial for the design of advanced nuclear systems as well as the development of comprehensive theoretical models of the fission process. The $^{242}$Pu(n,f) cross section was measured at the CERN n_TOF facility taking advantage of the wide energy range and the high instantaneous flux of the neutron beam. In this work, results for the $^{242}$Pu(n,f) measurement are presented along with a detailed description of the experimental setup, Monte-Carlo simulations and the analysis procedure, and a theoretical cross section calculation performed with the EMPIRE code.

  4. Use of 236Pu and 242Pu as a radiochemical tracer for estimation of Pu in bioassay samples by fission track analysis

    International Nuclear Information System (INIS)

    Sawant, Pramilla D.; Prabhu, Supreetha P.; Kalsi, P.C.

    2008-01-01

    236 Pu and 242 Pu are routinely used as radiochemical yield monitors in India for bioassay monitoring of occupational workers by alpha spectrometry. Fission Track Analysis (FTA) is also being standardized for trace level determination of Pu in bioassay samples. The present study, reports the utility of 236 Pu and 242 Pu as radiochemical tracers in estimation of Pu in bioassay samples by FTA technique. The advantages of using 236 Pu tracer in FTA over 242 Pu as well as the interference caused due to presence of 241 Pu in the bioassay samples of occupational workers handling power reactor grade Pu is discussed. (author)

  5. Diagnostic value of combined determination of serum tumor markers (NSE, CA-242, TPA, CEA) levels in patients with lung cancer

    International Nuclear Information System (INIS)

    Liu Juzhen; Cai Tietie; Qin Shana

    2007-01-01

    Objective: To investigate the diagnostic value of combined determination of serum NSE, CA242, tissue polypeptide antigen (TPA) and CEA levels in patients with primary lung cancer. Methods: Serum NSE, CA242, TPA and CEA levels were determined with ELISA in (1) 102 patients with various types of primary lung carcinoma (adenocarcinoma 38, squamous cell carcinoma 32, small cell lung carcinoma 32) (2) 33 patients with open lung T. B. and (3) 30 controls. Results: (1) In patients with lung cancer, serum levels of all the four markers were increased and significantly higher than their respective values in patients with open lung T.B. and controls. (2) Positive rate of combined any two markers were 75% for adenocarcinoma, 50% for squamous cell carcinoma and 65% for small cell lung carcinoma, while false positive rate was only 9% for T.B patients and none for the controls. (3) The most appropriate single marker for each specific type of lung cancer was: NSE for SCLC (sensitivity 72%, specificity 97%, CA242 for adenocarcinoma sensitivity 62%, specificity 90%). Conclusion: Combined determination of these tumor markers would improve the sensitivity and specificity for diagnosis of primary lung carcinoma. (authors)

  6. A Diagnostic and Therapeutic Algorithm for Impacted Teeth for Plastic Surgeons: Outcomes of 242 Extracted Teeth

    Directory of Open Access Journals (Sweden)

    Nebil Yeşiloğlu

    2016-09-01

    Full Text Available Objective: Impacted teeth are important for plastic surgeons that frequently perform maxillofacial operations because of their tendency to affect dental occlusion, and thus, cephalometric results. Moreover, severe complications are also caused by the tooth and its surgical removal. In this study, retrospective analysis of 242 extracted teeth and 24 extracted roots was performed and an algorithmic approach to different types and the localizations of impacted teeth was presented. Possible complications and salvage procedures were also discussed. Material and Methods: A retrospective analysis of 128 patients who underwent impacted teeth removal surgery between 2013 and 2015 was performed. Mean age was 26 years (Range: 18–42 years, and the female to male ratio was 39/89. Sixteen of the patients were operated under regional nerve block, whereas the remaining were operated under general anesthesia. In 107 patients, the whole tooth was removed, whereas the residual root of the tooth was removed in 21 patients. In 89 patients, bone interventions like the creation of bone window or peridental milling to loosen the tooth were needed, whereas only oral mucosal incisions were performed in the remaining patients. Results: The most common onset symptom was localized pain, and the most common complications were swelling and edema. The most common extracted tooth was the mandibular 3rd molar. Lower lip hypoesthesia, which was continued up to eight months, was encountered in six patients who underwent mandibular 3rd molar extraction. Conclusion: In our opinion, a wide range of possible complications secondary to impacted teeth surgery makes them important for plastic surgeons who are more experienced than other disciplines, and learning teeth extraction is essential to learn in plastic surgery specialty training.

  7. Preparation and study of elemental californium-249

    International Nuclear Information System (INIS)

    Noe, M.; Peterson, J.R.

    1975-01-01

    Bulk samples of 249 Cf metal were prepared on the 10 μg scale via the Li metal vapor reduction of 249 CfF 3 . Above about 725 0 C elemental Cf exhibits a face-centered cubic (fcc) structure with an average, room-temperature lattice parameter of 5.75(1)A. Between about 600 0 C and 725 0 C, the stable form of Cf metal is another fcc structure with an average, room-temperature lattice parameter of 4.94(1)A. Below 600 0 C metallic Cf exhibits a double hexagonal closest packed (dhcp) structure with average, room temperature lattice parameters of a 0 = 3.39(1)A and c 0 = 11.01(5)A. By comparison of the metallic radii calculated for these three forms with those of the receding transuranium elements, it is suggested that the two, lower temperature modifications represent Cf with a metallic valence of three, while the highest temperature form represents a metallic valence of two. Although the data reported here are from the most complete study to date of elemental Cf, the limitations accompanying such microscale research are duly noted. (U.S.)

  8. Californium Cf-252 for pelvic radiotherapy

    Energy Technology Data Exchange (ETDEWEB)

    Maruyama, Y; Feola, J M; Tai, D; Wilson, L C; Van Nagell, J R; Yoneda, J

    1978-01-01

    Clinical data about therapy concerning tumors of the female gynecological cancers of the cervix, vagina and uterus are reviewed. Dosimetric, laboratory and radiobiological research data form the basis for an approach to such tumors using Cf-252 as a form of boost brachytherapy. Extreme personnel hazards are a real and important consideration and indicate that maximal containment and isolation procedures should be exercised in its use.

  9. Measurement of Am-242 fission yields at the Lohengrin spectrometer; improvement and Benchmarking of the semi-empirical code GEF

    International Nuclear Information System (INIS)

    Amouroux, Charlotte

    2014-01-01

    The study of fission yields has a major impact on the characterization and understanding of the fission process and is mandatory for reactor applications. While the yields are known for the major actinides (U-235, Pu-239) in the thermal neutron-induced fission, only few measurements were performed on Am-242. Moreover, the two main data libraries do not agree among each other on the light peak. Am-241 and Am-242 are nuclei of interest for the MOX-fuel reactors and for the reduction of nuclear waste radiotoxicity using transmutation reactions. Thus, a campaign of precise measurement of the fission mass yields from the reaction Am-241(2n,f) was performed at the Lohengrin mass spectrometer (ILL, France) for both the light and the heavy peak. Forty-one masses were measured. Moreover, the measurement of the isotopic fission yields on the heavy peak by gamma-ray spectrometry led to the extraction of 20 independent isotopic yields. Our measurement was also meant to determine whether there is a difference in fission yields between the Am-242 isomeric state and its ground state as it exists in fission cross sections. The experimental method used to answer this question is based on the measurement a set of fission mass yields as a function of the ratio of Am-242gs to Am-242m fission rate. Results show that the mass yields are independent of the fission rate ratio. A future experimental campaign is proposed to observe a possible influence on the isomeric yields. The theoretical models are nowadays unable to predict the fission yields with enough accuracy and therefore we have to rely on experimental data and phenomenological models. The accuracy of the predictions of the semi empirical GEF fission model predictions makes it a useful tool for evaluation. This thesis also presents the physical content and part of the development of this model. Validation of the kinetic energy distributions, isomeric yields and fission yields predictions was performed. The extension of the GEF

  10. Changes in the expression of serum markers CA242, CA199, CA125, CEA, TNF-α and TSGF after cryosurgery in pancreatic cancer patients.

    Science.gov (United States)

    Zhou, Gang; Niu, Lizhi; Chiu, David; He, Lihua; Xu, Kecheng

    2012-07-01

    The presence of serum tumor markers, carbohydrate antigen 242 (CA242), carbohydrate antigen 199 (CA199), carbohydrate antigen 125 (CA125), carcinoembryonic antigen (CEA), tumor-supplied group of factors (TSGF) and tumor necrosis factor-α (TNF-α), is closely associated with invasion and metastasis of many malignancies. The expression of these markers were measured in serum taken from 37 pancreatic cancer patients prior to treatment. Levels of CA242, CA199, CA125, CEA and TNF-α expression correlated with tumor size, clinical stage, tumor differentiation, lymph node and liver metastasis (P markers were significantly reduced compared with levels prior to cryosurgery (P 0.05). Thus, cryosurgery is more effective than chemotherapy for decreasing CA242, CA199, CA125, CEA, TSGF and TNF-α serum levels in these patients.

  11. Combined detection of preoperative serum CEA, CA19-9 and CA242 improve prognostic prediction of surgically treated colorectal cancer patients.

    Science.gov (United States)

    Wang, Jingtao; Wang, Xiao; Yu, Fudong; Chen, Jian; Zhao, Senlin; Zhang, Dongyuan; Yu, Yang; Liu, Xisheng; Tang, Huamei; Peng, Zhihai

    2015-01-01

    We assessed the prognostic significance of preoperative serum carcinoembryonic antigen (CEA), carbohydrate antigen 19-9 (CA19-9) and carbohydrate antigen 242 (CA242) levels in surgically treated colorectal cancer patients. The relationship of preoperative serum CEA, CA19-9 and CA242 levels with disease characteristics was investigated in 310 patients. Correlation between tumor markers was investigated using Pearson correlation test. Univariate and multivariate survival analyses were used to study the relationship between preoperative tumor markers and prognosis [disease free survival (DFS) and overall survival (OS)]. Kaplan-Meier analysis with log rank test was used to assess the impact of tumor marker levels on survival. Positive rate of preoperative serum CEA, CA19-9 and CA242 were 54.84%, 47.42% and 37.10%, respectively. High preoperative CEA level was associated with tumor size (P = 0.038), T stage (P tumor AJCC stage (P = 0.023). Preoperative CA242 positively correlated with CEA (P markers was of independent prognostic value in CRC (HR = 2.532, 95% CI: 1.400-4.579, P = 0.002 for OS; and HR = 2.366, 95% CI: 1.334-4.196, P = 0.003 for DFS). Combined detection of preoperative serum CEA, CA19-9 and CA242 is of independent prognostic value for management of CRC patients treated surgically.

  12. Measurements of ice nucleating particle concentrations at 242 K in the free troposphere

    Science.gov (United States)

    Lacher, L.; Lohmann, U.; Boose, Y.; Zipori, A.; Herrmann, E.; Bukowiecki, N.; Steinbacher, M.; Gute, E.; Kanji, Z. A.

    2017-12-01

    Clouds containing ice play an important role in the Earth's system, but some fundamental knowledge on their formation and further development is still missing. The phase change from vapor or liquid to ice in the atmosphere can occur heterogeneously in the presence of ice nucleating particles (INPs) at temperatures warmer, and supersaturations lower than required for homogeneous freezing. Only a small fraction of particles in an environment relevant for the occurrence of ice- and mixed-phase clouds are INPs, and their identification and quantification remains challenging. We measure INP concentrations with the ETH Horizontal Ice Nucleation Chamber (HINC) at the High Altitude Research Station Jungfraujoch (JFJ) during several field campaigns in different seasons and years. The measurements are performed at 242 K and above water saturation, representing ice- and mixed-phase clouds conditions. Due to its elevation of 3580 m a.s.l. the site encounters mostly free tropospheric conditions, and is influenced by boundary layer injections up to 80% of the time in summer. JFJ regularly encounters Saharan dust events and receives air masses of marine origin, which can both occur within the free troposphere. Our measurements show that INP concentrations in the free troposphere do not follow a seasonal cycle. They are remarkably constant, with concentrations from 0.5 - 8 L-1 (interquartile range), which compares well to measurements performed under the same conditions at another location within the free troposphere, the Izaña Atmospheric Research Station in Tenerife. At JFJ, correlations with parameters of physical properties of ambient particles, meteorology and air mass characteristics do not show a single best estimator to predict INP concentrations, emphasizing the complexity of ice nucleation in the free troposphere. Increases in INP concentrations of a temporary nature were observed in the free troposphere during Saharan dust events and marine air mass influence, which

  13. The solubility of {sup 242}PuO{sub 2} in the presence of aqueous Fe(II). The impact of precipitate preparation

    Energy Technology Data Exchange (ETDEWEB)

    Felmy, Andrew R.; Moore, Dean A.; Buck, Edgar; Kukkadapu, Ravi; Sweet, Lucas; Abrecht, David; Ilton, Eugene S. [Pacific Northwest National Laboratory, Richland, WA (United States); Conrados, Steven D. [Los Alamos National Laboratory, Los Alamos, NM (United States)

    2014-07-01

    The solubility of different forms of precipitated {sup 242}PuO{sub 2}(am) were examined in solutions containing aqueous Fe(II) over a range of pH values. The first series of {sup 242}PuO{sub 2}(am) suspensions were prepared from a {sup 242}Pu(IV) stock that had been treated with thenoyltrifluoroacetone (TTA) to remove the {sup 241}Am originating from the decay of {sup 241}Pu. These {sup 242}PuO{sub 2}(am) suspensions showed much higher solubilities at the same pH value and Fe(II) concentration than previous studies using {sup 239}PuO{sub 2}(am). X-ray absorption fine structure (XAFS) spectroscopy of the precipitates showed a substantially reduced Pu-Pu backscatter over that previously observed in {sup 239}PuO{sub 2}(am) precipitates, indicating that the {sup 242}PuO{sub 2}(am) precipitates purified using TTA lacked the long range order previously found in{sup 239}PuO{sub 2}(am) precipitates. The Pu(IV) stock solution was subsequently re-purified using an ion exchange resin and an additional series of {sup 242}PuO{sub 2}(am) precipitates prepared. These suspensions showed higher redox potentials and total aqueous Pu concentrations than the TTA purified stock solution. The higher redox potential and aqueous Pu concentrations were in general agreement with previous studies on {sup 242}PuO{sub 2}(am) precipitates, presumably due to the removal of possible organic compounds originally present in the TTA purified stock. {sup 242}PuO{sub 2}(am) suspensions prepared with both stock solutions showed almost identical solubilities in Fe(II) containing solutions even though the initial aqueous Pu concentrations before the addition of Fe(II) were orders of magnitude different. By examining the solubility of {sup 242}PuO{sub 2}(am) prepared from both stocks in this way we have essentially approached equilibrium from both the undersaturated and oversaturated conditions. The final aqueous Pu concentrations are predictable using a chemical equilibrium model which includes the

  14. Radiative neutron capture on 242Pu in the resonance region at the CERN n_TOF-EAR1 facility

    Science.gov (United States)

    Lerendegui-Marco, J.; Guerrero, C.; Mendoza, E.; Quesada, J. M.; Eberhardt, K.; Junghans, A. R.; Krtička, M.; Aberle, O.; Andrzejewski, J.; Audouin, L.; Bécares, V.; Bacak, M.; Balibrea, J.; Barbagallo, M.; Barros, S.; Bečvář, F.; Beinrucker, C.; Berthoumieux, E.; Billowes, J.; Bosnar, D.; Brugger, M.; Caamaño, M.; Calviño, F.; Calviani, M.; Cano-Ott, D.; Cardella, R.; Casanovas, A.; Castelluccio, D. M.; Cerutti, F.; Chen, Y. H.; Chiaveri, E.; Colonna, N.; Cortés, G.; Cortés-Giraldo, M. A.; Cosentino, L.; Damone, L. A.; Diakaki, M.; Dietz, M.; Domingo-Pardo, C.; Dressler, R.; Dupont, E.; Durán, I.; Fernández-Domínguez, B.; Ferrari, A.; Ferreira, P.; Finocchiaro, P.; Furman, V.; Göbel, K.; García, A. R.; Gawlik, A.; Glodariu, T.; Gonçalves, I. F.; González-Romero, E.; Goverdovski, A.; Griesmayer, E.; Gunsing, F.; Harada, H.; Heftrich, T.; Heinitz, S.; Heyse, J.; Jenkins, D. G.; Jericha, E.; Käppeler, F.; Kadi, Y.; Katabuchi, T.; Kavrigin, P.; Ketlerov, V.; Khryachkov, V.; Kimura, A.; Kivel, N.; Kokkoris, M.; Leal-Cidoncha, E.; Lederer, C.; Leeb, H.; Lo Meo, S.; Lonsdale, S. J.; Losito, R.; Macina, D.; Marganiec, J.; Martínez, T.; Massimi, C.; Mastinu, P.; Mastromarco, M.; Matteucci, F.; Maugeri, E. A.; Mengoni, A.; Milazzo, P. M.; Mingrone, F.; Mirea, M.; Montesano, S.; Musumarra, A.; Nolte, R.; Oprea, A.; Patronis, N.; Pavlik, A.; Perkowski, J.; Porras, J. I.; Praena, J.; Rajeev, K.; Rauscher, T.; Reifarth, R.; Riego-Perez, A.; Rout, P. C.; Rubbia, C.; Ryan, J. A.; Sabaté-Gilarte, M.; Saxena, A.; Schillebeeckx, P.; Schmidt, S.; Schumann, D.; Sedyshev, P.; Smith, A. G.; Stamatopoulos, A.; Tagliente, G.; Tain, J. L.; Tarifeño-Saldivia, A.; Tassan-Got, L.; Tsinganis, A.; Valenta, S.; Vannini, G.; Variale, V.; Vaz, P.; Ventura, A.; Vlachoudis, V.; Vlastou, R.; Wallner, A.; Warren, S.; Weigand, M.; Weiss, C.; Wolf, C.; Woods, P. J.; Wright, T.; Žugec, P.; n TOF Collaboration

    2018-02-01

    The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with uranium to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing to the long-term sustainability of nuclear energy. However, an extensive use of MOX fuels, in particular in fast reactors, requires more accurate capture and fission cross sections for some Pu isotopes. In the case of 242Pu there are sizable discrepancies among the existing capture cross-section measurements included in the evaluations (all from the 1970s) resulting in an uncertainty as high as 35% in the fast energy region. Moreover, postirradiation experiments evaluated with JEFF-3.1 indicate an overestimation of 14% in the capture cross section in the fast neutron energy region. In this context, the Nuclear Energy Agency (NEA) requested an accuracy of 8% in this cross section in the energy region between 500 meV and 500 keV. This paper presents a new time-of-flight capture measurement on 242Pu carried out at n_TOF-EAR1 (CERN), focusing on the analysis and statistical properties of the resonance region, below 4 keV. The 242Pu(n ,γ ) reaction on a sample containing 95(4) mg enriched to 99.959% was measured with an array of four C6D6 detectors and applying the total energy detection technique. The high neutron energy resolution of n_TOF-EAR1 and the good statistics accumulated have allowed us to extend the resonance analysis up to 4 keV, obtaining new individual and average resonance parameters from a capture cross section featuring a systematic uncertainty of 5%, fulfilling the request of the NEA.

  15. Reasons why Plutonium 242 is the best fission chamber deposit to monitor the fast component of a high neutron flux

    International Nuclear Information System (INIS)

    Filliatre, P.; Oriol, L.; Jammes, C.; Vermeeren, L.

    2008-01-01

    The FNDS project aims at developing fission chambers to measure on-line the fast component of a high neutron flux (∼10 14 ncm -2 s -1 or more) with a significant thermal component. We identify with simulations the deposits of fission chambers that are best suited to this goal. We address the question of the evolution of the deposit by radiative capture and decay. A deposit of 242 Pu appears as the best choice, with a high initial sensitivity to fast neutrons only slowly degrading under irradiation. The effect of unavoidable impurities was assessed: small concentrations of 241 Pu and 239 Pu can be tolerated

  16. Measurements of the neutron-induced fission cross sections of 240Pu and 242Pu relative to 235U

    International Nuclear Information System (INIS)

    Behrens, J.W.; Browne, J.C.; Carlson, G.W.

    1976-01-01

    A continuation is given of the fission-cross-section ratio measurements in progress at the Lawrence Livermore Laboratory. Preliminary results are provided for the 240 Pu/ 235 U and 242 Pu/ 235 U ratios from 0.02 to 30 MeV and 0.1 to 30 MeV, respectively. Using the threshold-cross-section method, the ratios were normalized to the values 1.368 +- 0.030 and 1.116 +- 0.025, respectively, from 1.75 to 4.00 MeV

  17. Neutron and gamma-ray emission in the proton induced fission of {sup 238}U and {sup 242}Pu

    Energy Technology Data Exchange (ETDEWEB)

    Kniajeva, G.N.; Krupa, L.; Bogachev, A.A.; Chubarian, G.G.; Dorvaux, O.; Itkis, I.M.; Itkis, M.G.; Kliman, J.; Khlebnikov, S.; Kondratiev, N.A.; Kozulin, E.M.; Lyapin, V.; Materna, T.; Pokrovsky, I.V.; Rubchenya, V.A.; Trzaska, W.H.; Vakhtin, D.; Voskressenski, V.M

    2004-04-05

    Average prescission M{sup pre}{sub n} and postscission M{sup post}{sub n} neutron multiplicities as well as average {gamma}-ray multiplicity , average energy emitted by {gamma}-rays as a function of mass and total kinetic energy (TKE) of fission fragments were measured in proton induced reactions p+{sup 242}Pu{yields}{sup 243}Am, p+{sup 238}U{yields}{sup 239}Np at proton energy E{sub p}=13, 20 and 55 MeV.

  18. 242Pu as tracer for simultaneous determination of 237Np and 239,240Pu in environmental samples

    DEFF Research Database (Denmark)

    Chen, Q.J.; Dahlgaard, H.; Nielsen, S.P.

    2002-01-01

    A procedure has been developed using Pu-242 as tracer for simultaneous determination of Np-237 and Pu-239,Pu-240 in environmental samples. The validity of the method has been demonstrated by ICPMS and alpha-spectroscopy for up to 10 gram soil and sediment, seawater up to 200 litres. The paper...... from Np and Pu) R-before/R-after = 1.004 +/- 3.3% (S.D n = 20) and 1 litre seawater R-before/R-after = 1.019+/-1.9% (S.D., n = 12). Results from the intercomparison samples LAEA-135, LAEA-381 and from environmental samples are presented....... describes a suitable chemical procedure for Np and Pu including a quantitative pre-concentration of neptunium and plutonium, preparation of Np4+ and Pu4+, NP(NO3)(6)(2-) and Pu(NO3)(6)(2-), The ratio of Np-237/Pu-242 (or Np-237/Pu-239) before and after the procedure has been determined using 10 g soil (free...

  19. Sequence and batch language programs and alarm-related ``C`` programs for the 242-A MCS. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Berger, J.F.

    1995-03-01

    A Distributive Process Control system was purchased by Project B-534, ``242-A Evaporator/Crystallizer Upgrades``. This control system, called the Monitor and Control System (MCS), was installed in the 242-A Evaporator located in the 200 East Area. The purpose of the MCS is to monitor and control the Evaporator and monitor a number of alarms and other signals from various Tank Farm facilities. Applications software for the MCS was developed by the Waste Treatment Systems Engineering (WTSE) group of Westinghouse. The standard displays and alarm scheme provide for control and monitoring, but do not directly indicate the signal location or depict the overall process. To do this, WTSE developed a second alarm scheme which uses special programs, annunciator keys, and process graphics. The special programs are written in two languages; Sequence and Batch Language (SABL), and ``C`` language. The WTSE-developed alarm scheme works as described below: SABL relates signals and alarms to the annunciator keys, called SKID keys. When an alarm occurs, a SABL program causes a SKID key to flash, and if the alarm is of yellow or white priority then a ``C`` program turns on an audible horn (the D/3 system uses a different audible horn for the red priority alarms). The horn and flashing key draws the attention of the operator.

  20. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 4

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    Radiation protection of personnel and the public is accomplished by establishing a well defined Radiation Protection Organization to ensure that appropriate controls on radioactive materials and radiation sources are implemented and documented. This Requirements Identification Document (RID) applies to the activities, personnel, structures, systems, components, and programs involved in executing the mission of the Tank Farms. The physical boundaries within which the requirements of this RID apply are the Single Shell Tank Farms, Double Shell Tank Farms, 242-A Evaporator-Crystallizer, 242-S, T Evaporators, Liquid Effluent Retention Facility (LERF), Purgewater Storage Facility (PWSF), and all interconnecting piping, valves, instrumentation, and controls. Also included is all piping, valves, instrumentation, and controls up to and including the most remote valve under Tank Farms control at any other Hanford Facility having an interconnection with Tank Farms. The boundary of the structures, systems, components, and programs to which this RID applies, is defined by those that are dedicated to and/or under the control of the Tank Farms Operations Department and are specifically implemented at the Tank Farms.

  1. Comparison of size modulation and conventional standard automated perimetry with the 24-2 test protocol in glaucoma patients

    Science.gov (United States)

    Hirasawa, Kazunori; Shoji, Nobuyuki; Kasahara, Masayuki; Matsumura, Kazuhiro; Shimizu, Kimiya

    2016-05-01

    This prospective randomized study compared test results of size modulation standard automated perimetry (SM-SAP) performed with the Octopus 600 and conventional SAP (C-SAP) performed with the Humphrey Field Analyzer (HFA) in glaucoma patients. Eighty-eight eyes of 88 glaucoma patients underwent SM-SAP and C-SAP tests with the Octopus 600 24-2 Dynamic and HFA 24-2 SITA-Standard, respectively. Fovea threshold, mean defect, and square loss variance of SM-SAP were significantly correlated with the corresponding C-SAP indices (P < 0.001). The false-positive rate was slightly lower, and false-negative rate slightly higher, with SM-SAP than C-SAP (P = 0.002). Point-wise threshold values obtained with SM-SAP were moderately to strongly correlated with those obtained with C-SAP (P < 0.001). The correlation coefficients of the central zone were significantly lower than those of the middle to peripheral zone (P = 0.031). The size and depth of the visual field (VF) defect were smaller (P = 0.039) and greater (P = 0.043), respectively, on SM-SAP than on C-SAP. Although small differences were observed in VF sensitivity in the central zone, the defect size and depth and the reliability indices between SM-SAP and C-SAP, global indices of the two testing modalities were well correlated.

  2. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 4

    International Nuclear Information System (INIS)

    1994-04-01

    Radiation protection of personnel and the public is accomplished by establishing a well defined Radiation Protection Organization to ensure that appropriate controls on radioactive materials and radiation sources are implemented and documented. This Requirements Identification Document (RID) applies to the activities, personnel, structures, systems, components, and programs involved in executing the mission of the Tank Farms. The physical boundaries within which the requirements of this RID apply are the Single Shell Tank Farms, Double Shell Tank Farms, 242-A Evaporator-Crystallizer, 242-S, T Evaporators, Liquid Effluent Retention Facility (LERF), Purgewater Storage Facility (PWSF), and all interconnecting piping, valves, instrumentation, and controls. Also included is all piping, valves, instrumentation, and controls up to and including the most remote valve under Tank Farms control at any other Hanford Facility having an interconnection with Tank Farms. The boundary of the structures, systems, components, and programs to which this RID applies, is defined by those that are dedicated to and/or under the control of the Tank Farms Operations Department and are specifically implemented at the Tank Farms

  3. Association between NADPH oxidase p22(phox C242T polymorphism and ischemic cerebrovascular disease: a meta-analysis.

    Directory of Open Access Journals (Sweden)

    Bing-Hu Li

    Full Text Available BACKGROUND: Epidemiological studies have evaluated the association between nicotinamide adenine dinucleotide phosphate (NADPH oxidase p22(phox C242T polymorphism and risk of ischemic cerebrovascular disease (ICVD, but the results remain inconclusive. This meta-analysis was therefore designed to clarify these controversies. METHODOLOGY/PRINCIPAL FINDINGS: Systematic searches of electronic databases Embase, PubMed and Web of Science, as well as hand searching of the references of identified articles and the meeting abstracts were performed. Statistical analyses were performed using software Review Manager (Version 5.1.7 and Stata (Version 11.0. The pooled odds ratios (ORs with 95% confidence intervals (95%CIs were performed. Fixed or random effects model was separately used depending on the heterogeneity between studies. Publication bias was tested by Begg's funnel plot and Egger's regression test. A total of 6 studies including 1,948 cases and 2,357 controls were combined showing no statistical evidence of association between NADPH oxidase p22(phox C242T polymorphism and overall ICVD (allelic model: OR = 1.08, 95%CI = 0.93-1.26; additive model: OR = 1.33, 95%CI = 0.81-2.17; dominant model: OR = 1.00, 95%CI = 0.86-1.15; recessive model: OR = 1.06, 95%CI = 0.77-1.45. Significant association was found in large-artery atherosclerotic stroke subgroup (allelic model: OR = 1.12, 95%CI = 0.88-1.41; additive model: OR = 1.36, 95%CI = 0.60-3.09; dominant model: OR = 1.25, 95%CI = 0.74-2.11; recessive model: OR = 2.17, 95%CI = 1.11-4.23. No statistical evidence of significant association was observed for small-vessel occlusive stroke, as well as Asian subgroup and Caucasian subgroup. Statistical powers on the combined sample size (total and subgroup were all lower than 80%. CONCLUSIONS/SIGNIFICANCE: This meta-analysis indicates that NADPH oxidase p22(phox C242T polymorphism is more associated

  4. Relationship between peripheral and mesenteric serum levels of CEA and CA 242 with staging and histopathological variables in colorectal adenocarcinoma Níveis séricos periféricos e mesentéricos de CEA e CA 242, estadiamento e variáveis histopatológicas no adenocarcinoma colorretal

    Directory of Open Access Journals (Sweden)

    Mauro Lamelas Cardoso

    2009-10-01

    Full Text Available PURPOSE: To compare histopathological variables and staging in colorectal adenocarcinoma cases with CEA and CA 242 in peripheral and mesenteric blood. METHODS: In 169 individuals underwent surgery for colorectal cancer, CEA and CA 242 were analyzed and compared to mesenteric and peripheral blood and correlated with macroscopic tumor's morphology and size, degree of cell differentiation, venous, neural and lymphatic involvement and TNM classification. RESULTS: There was a difference between the mesenteric (M and peripheral (P serum levels of CEA (p=0.020. Higher levels of markers were correlated with venous invasion CEA (P p=0.013, CEA (M p=0.05, CA 242 (M p=0.005 and CA 242 (P p=0.038; with advanced staging CEA (P OBJETIVO: Comparar variáveis histopatológicas e graus de estadiamento do adenocarcinoma colorretal com níveis sanguíneos periféricos e mesentéricos de CEA e CA-242. MÉTODOS: Em 169 doentes submetidos ao tratamento cirúrgico por adenocarcinoma colorretal, CEA e CA-242 foram analisados e comparados quanto aos níveis sanguíneos periféricos e mesentéricos e correlacionados com o tamanho e a morfologia macroscópica do tumor, grau de diferenciação celular, invasões venosa, linfática, neural e a classificação TNM. RESULTADOS: Verificou-se diferença significante entre o nível sérico mesentérico e periférico de CEA (p= 0,02. Níveis séricos mais elevados dos marcadores foram observados e correlacionados com invasão venosa, CEA (P p=0,013, CEA(M, p=0,05, CA-242 (M p=0,005 e CA-242 (P p=0,038. Grau de estadiamento TNM avançado foi associado com CEA(P < CEA(M p<0,05, CA-242(P < CA-242(M p<0,05. Nas maiores dimensões tumorais constatou-se CEA(P < CEA(M p=0,001 e CA 242 (P < CA 242 (M (p < 0.001. O CA 242 periférico e mesentérico aumentados associaram-se com a invasão neural, p=0.014 e p=0.003, respectivamente. CONCLUSÕES: O nível sérico mesentérico de CEA é superior ao nível sérico periférico. Os níveis s

  5. Applicative Value of Serum CA19-9, CEA, CA125 and CA242 in Diagnosis and Prognosis for Patients with Pancreatic Cancer Treated by Concurrent Chemoradiotherapy.

    Science.gov (United States)

    Gu, Yu-Lei; Lan, Chao; Pei, Hui; Yang, Shuang-Ning; Liu, Yan-Fen; Xiao, Li-Li

    2015-01-01

    To evaluate the application value of serum CA19-9, CEA, CA125 and CA242 in diagnosis and prognosis of pancreatic cancer cases treated with concurrent chemotherapy. 52 patients with pancreatic cancer, 40 with benign pancreatic diseases and 40 healthy people were selected. The electrochemiluminescence immunoassay method was used for detecting levels of CA19-9, CEA and CA125, and a CanAg CA242 enzyme linked immunoassay kit for assessing the level of CA242. The Kaplan-Meier method was used for analyzing the prognostic factors of patients with pancreatic cancer. The Cox proportional hazard model was applied for analyzing the hazard ratio (HR) and 95% confidential interval (CI) for survival time of patients with pancreatic cancer. The levels of serum CA19-9, CEA, CA125 and CA242 in patients with pancreatic cancer were significantly higher than those in patients with benign pancreatic diseases and healthy people (PCEA. The specificity of CA242 is the highest, followed by CA125, CEA and CA19-9. The sensitivity and specificity of joint detection of serum CA19-9, CEA, CA125and CA242 were 90.4% and 93.8%, obviously higher than single detection of those markers in diagnosis of pancreatic cancer. The median survival time of 52 patients with pancreatic cancer was 10 months (95% CI7.389~12.611).. Patients with the increasing level of serum CA19-9, CEA, CA125, CA242 had shorter survival times (P=0.047. 0.043, 0.0041, 0.029). COX regression analysis showed that CA19-9 was an independent prognostic factor for patients with pancreatic cancer (P=0.001, 95%CI 2.591~38.243). The detection of serum tumor markers (CA19.9, CEA, CA125 and CA242) is conducive to the early diagnosis of pancreatic cancer and joint detection of tumor markers helps improve the diagnostic efficiency. Moreover, CA19-9 is an independent prognostic factor for patients with pancreatic cancer.

  6. Measurement of the fission cross-section of $^{240}$Pu and $^{242}$Pu at CERN's n_TOF Facility

    CERN Multimedia

    Pavlik, A F; Gonzalez romero, E M

    The n_TOF Collaboration proposes to continue the fission program, already started in 2002-2004, taking advantage of the newly constructed Work Sector Type A, with the measurement of the two isotopes : $^{240}$ Pu and $^{242}$ Pu. They are both of major importance for reactor physics applications and are included in the Nuclear Energy Agency (NEA) High Priority List [1], in the NEA WPEC Subgroup 26 Report on the accuracy of nuclear data for advanced reactor designe [2] and in the EU 6$^{th}$ Framework Programme IP-EUROTRANS/NUDATRA reports [3]. Based on those requests, the measurement of the fission cross-section of the two Pu isotopes is one of the objectives of the project ANDES of the FP7 EURATOM program [4].

  7. Reasons why Plutonium 242 is the best fission chamber deposit to monitor the fast component of a high neutron flux

    Energy Technology Data Exchange (ETDEWEB)

    Filliatre, P. [CEA, DEN, SPEx/LDCI, F-13108 Saint-Paul-lez-Durance (France); Laboratoire Commun d' Instrumentation CEA-SCK-CEN (France)], E-mail: philippe.filliatre@cea.fr; Oriol, L.; Jammes, C. [CEA, DEN, SPEx/LDCI, F-13108 Saint-Paul-lez-Durance (France); Laboratoire Commun d' Instrumentation CEA-SCK-CEN (France); Vermeeren, L. [SCK-CEN, Boeretang 200, B-2400 Mol (Belgium); Laboratoire Commun d' Instrumentation CEA-SCK-CEN (France)

    2008-08-11

    The FNDS project aims at developing fission chambers to measure on-line the fast component of a high neutron flux ({approx}10{sup 14}ncm{sup -2}s{sup -1} or more) with a significant thermal component. We identify with simulations the deposits of fission chambers that are best suited to this goal. We address the question of the evolution of the deposit by radiative capture and decay. A deposit of {sup 242}Pu appears as the best choice, with a high initial sensitivity to fast neutrons only slowly degrading under irradiation. The effect of unavoidable impurities was assessed: small concentrations of {sup 241}Pu and {sup 239}Pu can be tolerated.

  8. The emission of heavy clusters described in the mean-field HFB theory: the case of 242Cm

    International Nuclear Information System (INIS)

    Robledo, L.M.; Warda, M.

    2008-01-01

    The emission of a nucleus of 34 Si by the parent 96 242 Cm is a process in the diffuse borderline between cluster emission and standard mass asymmetric fission. In this paper we analyze in a microscopic framework such process using the standard mean field techniques used to describe cluster emission. They include Hartree-Fock-Bogoliubov constrained calculations with the Gogny D1S interaction and the octupole moment operator as the collective coordinate to describe the process. Collective masses and all kind of zero point energy corrections are considered which allows for a parameter free estimation of the process' half-life. The agreement with experiment is quite satisfactory. (author)

  9. Method for Determination of Neptunium in Large-Sized Urine Samples Using Manganese Dioxide Coprecipitation and 242Pu as Yield Tracer

    DEFF Research Database (Denmark)

    Qiao, Jixin; Hou, Xiaolin; Roos, Per

    2013-01-01

    A novel method for bioassay of large volumes of human urine samples using manganese dioxide coprecipitation for preconcentration was developed for rapid determination of 237Np. 242Pu was utilized as a nonisotopic tracer to monitor the chemical yield of 237Np. A sequential injection extraction chr...... and rapid analysis of neptunium contamination level for emergency preparedness....

  10. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 7. Revision 1

    International Nuclear Information System (INIS)

    Burt, D.L.

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 7) presents the standards and requirements for the following sections: Occupational Safety and Health, and Environmental Protection

  11. The value of combined tumor markers of CEA, CA19-9 and CA242 for diagnosis of patients with colorectal cancer

    International Nuclear Information System (INIS)

    Hu Hongyong; Tang Jianlin; Li Yuying; Gao Liuyan; Tang Xiuping

    2010-01-01

    Objective: To explore the clinical value of serum tumor markers carcinoembryonic antigen (CEA), carbohydrate antigen 19-9 (CA19-9) and carbohydrate antigen 242 (CA242) levels in patients with colorectal cancer using single item and multi-items determination. Methods: Serum levels of CEA, CA19-9 and CA242 were measured with chemiuminescent immunoassay (CLIA) and radioimmunoassay (RIA) in 89 cases of colorectal cancer patients and 50 cases of normal people. Results: The serum levels of this three tumor markers were significantly higher than those in the control group (t=3.97, 3.55 and 7.44, P 2 =30.552, 32.076, 18.365, 7.130 and 8.862, P<0.01). Combined determination of those three could enhance the sensitivity (85.39%) and accuracy (90.60%), but the specificity was decreased (88.00%). Conclusion: Determination of serum CEA, CA19-9 and CA242 levels are valuable for the diagnosis and evaluation of patients with colorectal cancer, and the diagnosis sensitivity can be enhanced with combined determinations. (authors)

  12. Application value of combined measurement of serum sTn, CA242, CA19-9 and CEA in the diagnosis of gastroenterological neoplasm

    International Nuclear Information System (INIS)

    Zhang Wanzhong; Chen Zhizhou; Fan Zhenfu

    2007-01-01

    To determine the application value of four serum tumor markers sTn, CA242, CA 19-9 and CEA in the diagnosis of gastroenterological neoplasm, the serum sTn, CA242, CA19-9 and CEA in 30 normal adult controls and 60 patients with gastroenterological neoplasm were measured by IRMA. The results showed that the serum sTn, CA242, CA19-9 and CEA levels in patients with gastric carcinoma or colorectal carcinoma were much higher than those in control group (P<0.01). The serum CEA, CA19-9 and CA242 levels in patients with colorectal carcinoma were significantly higher than those in patients with gastric carcinoma (P<0.01), but the serum sTn level in the former was markedly lower (P<0.01) than that in the latter. The sensitivity of tumor marker increased with the progress of clinical stages, with a considerably higher sensitivity for stage IV compared with stage I-II (P<0.01). The combined test of four tumor markers could be more sensitive than single test in detecting gastric carcinoma and colorectal carcinoma (P<0.05). Four tumor markers are useful for diagnosing gastroenterological neoplasm, and the combined measurement of 4 tumor markers could increase the sensitivity of detecting gastric carcinoma. (authors)

  13. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 7. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Burt, D.L.

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 7) presents the standards and requirements for the following sections: Occupational Safety and Health, and Environmental Protection.

  14. C242T Polymorphism in CYBA Gene (p22phox and Risk of Coronary Artery Disease in a Population of Caucasian Italians

    Directory of Open Access Journals (Sweden)

    Sabina Nasti

    2006-01-01

    Full Text Available Background: specific polymorphisms of genes regulating intracellular redox balance and oxidative stress are related to atherogenesis. Some studies have identified a relationship between progression of atherosclerosis and C242T mutation in CYBA gene coding for p22phox, a subunit of the NADH/NADPH oxidase system.

  15. Configuration management plan for waste tank farms and the 242-A evaporator of tank waste remediation system

    International Nuclear Information System (INIS)

    Laney, T.

    1994-01-01

    The configuration management architecture presented in this Configuration Management Plan is based on the functional model established by DOE-STD-1073-93, ''Guide for Operational Configuration Management Program.'' The DOE Standard defines the configuration management program by the five basic program elements of ''program management,'' ''design requirements,'' ''document control,'' ''change control,'' and ''assessments,'' and the two adjunct recovery programs of ''design reconstitution,'' and ''material condition and aging management.'' The CM model of five elements and two adjunct programs strengthen the necessary technical and administrative control to establish and maintain a consistent technical relationship among the requirements, physical configuration, and documentation. Although the DOE Standard was originally developed for the operational phase of nuclear facilities, this plan has the flexibility to be adapted and applied to all life-cycle phases of both nuclear and non-nuclear facilities. The configuration management criteria presented in this plan endorses the DOE Standard and has been tailored specifically to address the technical relationship of requirements, physical configuration, and documentation during the full life cycle of the Waste Tank Farms and 242-A Evaporator of Tank Waste Remediation System

  16. The Impact of Forced Migration on Mortality: A Cohort Study of 242,075 Finns from 1939-2010.

    Science.gov (United States)

    Haukka, Jari; Suvisaari, Jaana; Sarvimäki, Matti; Martikainen, Pekka

    2017-07-01

    The stresses and life changes associated with migration may have harmful long-term health effects, especially for mental health. These effects are exceedingly difficult to establish, because migrants are typically a highly selected group. We examined the impact of migration on health using "naturally occurring" historical events. In this article, we use the forced migration of 11% of the Finnish population after WWII as such a natural experiment. We observed the date and cause of death starting from 1 January 1971 and ending in 31 December 2010 for the cohort of 242,075 people. Data were obtained by linking individual-level data from the 1950 and 1970 population censuses and the register of death certificates from 1971 to 2010 (10% random sample). All-cause and cause-specific mortalities were modeled using Poisson regression. Models with full adjustment for background variables showed that both all-cause mortality (RR 1.03, 95% CI 1.01, 1.05), and ischemic heart disease mortality (RR 1.11, 95% CI 1.08, 1.15) were higher in the displaced population than in the nondisplaced population. Suicide mortality was lower (RR 0.77, 95% CI 0.64, 0.92) in displaced than in the general population. In our long-term follow-up study, forced migration was associated with increased risk of death due to ischemic heart diseases. In contrast, lower suicide mortality was observed in association with forced migration 25 years or more.

  17. Evaluation of 242Pu data for the incident neutron energy range 0.1 - 6 MeV

    International Nuclear Information System (INIS)

    Vladuca, G.; Sin, M.; Tudora, A.

    1996-11-01

    This report presents the models and the procedures used for the calculation of the quantities required by Files 3, 4 and 5 of ENDF-6 for 242 Pu. These quantities are the integrated cross sections for the total, fission, scattering and gamma-capture reactions and the angular and energy distributions of the scattered neutrons for the incident neutron energies 0.01/6 MeV. The direct mechanism was treated with the coupled-channel method using a deformed optical potential defined by a set of actinide region parameters established by the authors. For the compound nucleus calculations, a new HRTW version of the statistical model extended to describe the fission at subbarrier energies was used. To describe the continuous part of the transition states spectrum, analytical expressions have been established. The energy distributions of the scattered neutrons have been calculated with an author's version of the Los Alamos model. The agreement of the calculations with the existing experimental data is good. (author)

  18. Prenatal Diagnosis of a 2.5 Mb De Novo 17q24.1q24.2 Deletion Encompassing KPNA2 and PSMD12 Genes in a Fetus with Craniofacial Dysmorphism, Equinovarus Feet, and Syndactyly

    Directory of Open Access Journals (Sweden)

    Marie-Emmanuelle Naud

    2017-01-01

    Full Text Available Interstitial 17q24.1 or 17q24.2 deletions were reported after conventional cytogenetic analysis or chromosomal microarray analysis in patients presenting intellectual disability, facial dysmorphism, and/or malformations. We report on a fetus with craniofacial dysmorphism, talipes equinovarus, and syndactyly associated with a de novo 2.5 Mb 17q24.1q24.2 deletion. Among the deleted genes, KPNA2 and PSMD12 are discussed for the correlation with the fetal phenotype. This is the first case of prenatal diagnosis of 17q24.1q24.2 deletion.

  19. miR-24-2 controls H2AFX expression regardless of gene copy number alteration and induces apoptosis by targeting antiapoptotic gene BCL-2: a potential for therapeutic intervention.

    Science.gov (United States)

    Srivastava, Niloo; Manvati, Siddharth; Srivastava, Archita; Pal, Ranjana; Kalaiarasan, Ponnusamy; Chattopadhyay, Shilpi; Gochhait, Sailesh; Dua, Raina; Bamezai, Rameshwar N K

    2011-04-04

    New levels of gene regulation with microRNA (miR) and gene copy number alterations (CNAs) have been identified as playing a role in various cancers. We have previously reported that sporadic breast cancer tissues exhibit significant alteration in H2AX gene copy number. However, how CNA affects gene expression and what is the role of miR, miR-24-2, known to regulate H2AX expression, in the background of the change in copy number, are not known. Further, many miRs, including miR-24-2, are implicated as playing a role in cell proliferation and apoptosis, but their specific target genes and the pathways contributing to them remain unexplored. Changes in gene copy number and mRNA/miR expression were estimated using real-time polymerase chain reaction assays in two mammalian cell lines, MCF-7 and HeLa, and in a set of sporadic breast cancer tissues. In silico analysis was performed to find the putative target for miR-24-2. MCF-7 cells were transfected with precursor miR-24-2 oligonucleotides, and the gene expression levels of BRCA1, BRCA2, ATM, MDM2, TP53, CHEK2, CYT-C, BCL-2, H2AFX and P21 were examined using TaqMan gene expression assays. Apoptosis was measured by flow cytometric detection using annexin V dye. A luciferase assay was performed to confirm BCL-2 as a valid cellular target of miR-24-2. It was observed that H2AX gene expression was negatively correlated with miR-24-2 expression and not in accordance with the gene copy number status, both in cell lines and in sporadic breast tumor tissues. Further, the cells overexpressing miR-24-2 were observed to be hypersensitive to DNA damaging drugs, undergoing apoptotic cell death, suggesting the potentiating effect of mir-24-2-mediated apoptotic induction in human cancer cell lines treated with anticancer drugs. BCL-2 was identified as a novel cellular target of miR-24-2. mir-24-2 is capable of inducing apoptosis by modulating different apoptotic pathways and targeting BCL-2, an antiapoptotic gene. The study suggests

  20. Fission cross sections of plutonium-239 and plutonium-242 relative to uranium-285 from 0. 1 to 10 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Meadows, J.W.

    1978-12-01

    Measurement of the ratio of the fission cross sections of /sup 239/Pu and /sup 242/Pu to that of /sup 235/U is reported. The sources of neutrons were the /sup 7/Li(p,n)/sup 7/Be and D(d,n)/sup 3/He reactions. The ratio of the masses of the samples was determined by low geometry alpha counting and from relative thermal fission rates. The results are compared with other measurements. 19 references.

  1. A 233U/236U/242Pu/244Pu spike for isotopic and isotope dilution analysis by mass spectrometry with internal calibration

    International Nuclear Information System (INIS)

    Stepanov, A.; Belyaev, B.; Buljanitsa, L.

    1989-11-01

    The Khlopin Radium Institute prepared on behalf of the IAEA a synthetic mixture of 233 U, 236 U, 242 Pu and 244 Pu isotopes. The isotopic composition and elemental concentration of uranium and plutonium were certified on the basis of analyses done by four laboratories of the IAEA Network, using mass spectrometry with internal standardization. The certified values for 233 U/ 236 U ratio and the 236 U chemical concentration have a coefficient of variation of 0.05%. The latter is fixed by the uncertainty in the 235 U/ 238 U ratio of NBS500 used as internal standard. The coefficients of variation of the 244 Pu/ 242 Pu ratio and the 242 Pu chemical concentration are respectively 0.10% and 0.16% and limited by the uncertainty in the 240 Pu/ 239 Pu ratio of NBS947. This four isotope mixture was used as an internal standard as well as a spike, to analyze 30 batches of LWR spent fuel solutions. The repeatability of the mass spectrometric measurements have a coefficient of variation of 0.025% for the uranium concentration, and of 0.039% for the plutonium concentration. The spiking and treatment errors had a coefficient of variation of 0.048%. (author). Refs, figs and tabs

  2. Pages 242 - 248.pmd

    African Journals Online (AJOL)

    Administrator

    Department of Paediatrics and Child Health Makerere University, Kampala, Uganda. 2. Department of ... several times each day, often during meals, and in ..... Figure 2: The smaller patient has Nodding syndrome and is the same age as the taller adolescent who is of the ... Onchocerca volvulus in the CSF confirms our lack.

  3. Unraveling the reaction mechanism on nitrile hydration catalyzed by [Pd(OH2)4]2+: insights from theory.

    Science.gov (United States)

    Tílvez, Elkin; Menéndez, María I; López, Ramón

    2013-07-01

    Density functional theory methodologies combined with continuum and discrete-continuum descriptions of solvent effects were used to investigate the [Pd(OH2)4](2+)-catalyzed acrylonitrile hydration to yield acrylamide. According to our results, the intramolecular hydroxide attack mechanism and the external addition mechanism of a water molecule with rate-determining Gibbs energy barriers in water solution of 27.6 and 28.3 kcal/mol, respectively, are the most favored. The experimental kinetic constants of the hydration started by hydroxide, k(OH), and water, k(H2O), attacks for the cis-[Pd(en)(OH2)2](2+)-catalyzed dichloroacetonitrile hydration rendered Gibbs energy barriers whose energy difference, 0.7 kcal/mol, is the same as that obtained in the present study. Our investigation reveals the nonexistence of the internal attack of a water ligand for Pd-catalyzed nitrile hydration. At the low pHs used experimentally, the equilibrium between [Pd(OH2)3(nitrile)](2+) and [Pd(OH2)2(OH)(nitrile)](+) is completely displaced to [Pd(OH2)3(nitrile)](2+). Experimental studies in these conditions stated that water acts as a nucleophile, but they could not distinguish whether it was a water ligand, an external water molecule, or a combination of both possibilities. Our theoretical explorations clearly indicate that the external water mechanism becomes the only operative one at low pHs. On the basis of this mechanistic proposal it is also possible to ascribe an (1)H NMR signal experimentally detected to the presence of a unidentate iminol intermediate and to explain the influence of nitrile concentration reported experimentally for nitriles other than acrylonitrile in the presence of aqua-Pd(II) complexes. Therefore, our theoretical point of view on the mechanism of nitrile hydration catalyzed by aqua-Pd(II) complexes can shed light on these relevant processes at a molecular level as well as afford valuable information that can help in designing new catalysts in milder and more

  4. The C242T polymorphism of the p22-phox gene (CYBA is associated with higher left ventricular mass in Brazilian hypertensive patients

    Directory of Open Access Journals (Sweden)

    Krieger José E

    2011-08-01

    Full Text Available Abstract Background Reactive oxygen species have been implicated in the physiopathogenesis of hypertensive end-organ damage. This study investigated the impact of the C242T polymorphism of the p22-phox gene (CYBA on left ventricular structure in Brazilian hypertensive subjects. Methods We cross-sectionally evaluated 561 patients from 2 independent centers [Campinas (n = 441 and Vitória (n = 120] by clinical history, physical examination, anthropometry, analysis of metabolic and echocardiography parameters as well as p22-phox C242T polymorphism genotyping. In addition, NADPH-oxidase activity was quantified in peripheral mononuclear cells from a subgroup of Campinas sample. Results Genotype frequencies in both samples were consistent with the Hardy- Weinberg equilibrium. Subjects with the T allele presented higher left ventricular mass/height2.7 than those carrying the CC genotype in Campinas (76.8 ± 1.6 vs 70.9 ± 1.4 g/m2.7; p = 0.009, and in Vitória (45.6 ± 1.9 vs 39.9 ± 1.4 g/m2.7; p = 0.023 samples. These results were confirmed by stepwise regression analyses adjusted for age, gender, blood pressure, metabolic variables and use of anti-hypertensive medications. In addition, increased NADPH-oxidase activity was detected in peripheral mononuclear cells from T allele carriers compared with CC genotype carriers (p = 0.03. Conclusions The T allele of the p22-phox C242T polymorphism is associated with higher left ventricular mass/height2.7 and increased NADPH-oxidase activity in Brazilian hypertensive patients. These data suggest that genetic variation within NADPH-oxidase components may modulate left ventricular remodeling in subjects with systemic hypertension.

  5. Thermal neutron capture cross-section measurements of 243Am and 242Pu using the new mini-INCA α- and γ-spectroscopy station

    International Nuclear Information System (INIS)

    Marie, F.; Letourneau, A.; Fioni, G.; Deruelle, O.; Veyssiere, Ch.; Faust, H.; Mutti, P.; AlMahamid, I.; Muhammad, B.

    2006-01-01

    In the framework of the Mini-INCA project, dedicated to the study of Minor Actinide transmutation process in high neutron fluxes, an α- and γ-spectroscopy station has been developed and installed at the High Flux Reactor of the Laue-Langevin Institut. This set-up allows short irradiations as well as long irradiations in a high quasi-thermal neutron flux and post-irradiation spectroscopy analysis. It is well suited to measure precisely, in reference to 59 Co cross-section, neutron capture cross-sections, for all the actinides, in the thermal energy region. The first measurements using this set-up were done on 243 Am and 242 Pu isotopes. Cross-section values, at E n =0.025eV, were found to be (81.8+/-3.6)b for 243 Am and (22.5+/-1.1)b for 242 Pu. These values differ from evaluated data libraries by a factor of 9% and 17%, respectively, but are compatible with the most recent measurements, validating by the way the experimental apparatus

  6. De novo 14q24.2q24.3 microdeletion including IFT43 is associated with intellectual disability, skeletal anomalies, cardiac anomalies, and myopia.

    Science.gov (United States)

    Stokman, Marijn F; Oud, Machteld M; van Binsbergen, Ellen; Slaats, Gisela G; Nicolaou, Nayia; Renkema, Kirsten Y; Nijman, Isaac J; Roepman, Ronald; Giles, Rachel H; Arts, Heleen H; Knoers, Nine V A M; van Haelst, Mieke M

    2016-06-01

    We report an 11-year-old girl with mild intellectual disability, skeletal anomalies, congenital heart defect, myopia, and facial dysmorphisms including an extra incisor, cup-shaped ears, and a preauricular skin tag. Array comparative genomic hybridization analysis identified a de novo 4.5-Mb microdeletion on chromosome 14q24.2q24.3. The deleted region and phenotype partially overlap with previously reported patients. Here, we provide an overview of the literature on 14q24 microdeletions and further delineate the associated phenotype. We performed exome sequencing to examine other causes for the phenotype and queried genes present in the 14q24.2q24.3 microdeletion that are associated with recessive disease for variants in the non-deleted allele. The deleted region contains 65 protein-coding genes, including the ciliary gene IFT43. Although Sanger and exome sequencing did not identify variants in the second IFT43 allele or in other IFT complex A-protein-encoding genes, immunocytochemistry showed increased accumulation of IFT-B proteins at the ciliary tip in patient-derived fibroblasts compared to control cells, demonstrating defective retrograde ciliary transport. This could suggest a ciliary defect in the pathogenesis of this disorder. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

  7. Multi-isotopic determination of plutonium (239Pu, 240Pu, 241Pu and 242Pu) in marine sediments using sector-field inductively coupled plasma mass spectrometry.

    Science.gov (United States)

    Donard, O F X; Bruneau, F; Moldovan, M; Garraud, H; Epov, V N; Boust, D

    2007-03-28

    Among the transuranic elements present in the environment, plutonium isotopes are mainly attached to particles, and therefore they present a great interest for the study and modelling of particle transport in the marine environment. Except in the close vicinity of industrial sources, plutonium concentration in marine sediments is very low (from 10(-4) ng kg(-1) for (241)Pu to 10 ng kg(-1) for (239)Pu), and therefore the measurement of (238)Pu, (239)Pu, (240)Pu, (241)Pu and (242)Pu in sediments at such concentration level requires the use of very sensitive techniques. Moreover, sediment matrix contains huge amounts of mineral species, uranium and organic substances that must be removed before the determination of plutonium isotopes. Hence, an efficient sample preparation step is necessary prior to analysis. Within this work, a chemical procedure for the extraction, purification and pre-concentration of plutonium from marine sediments prior to sector-field inductively coupled plasma mass spectrometry (SF-ICP-MS) analysis has been optimized. The analytical method developed yields a pre-concentrated solution of plutonium from which (238)U and (241)Am have been removed, and which is suitable for the direct and simultaneous measurement of (239)Pu, (240)Pu, (241)Pu and (242)Pu by SF-ICP-MS.

  8. Extractability of plutonium-238 and curium-242 from a contaminated soil as a function of pH and certain soil components. CH3COOH-NH4OH system

    International Nuclear Information System (INIS)

    Nishita, H.

    1978-01-01

    Extractability of 238 Pu and 242 Cm from an artificially contaminated soil as a function of pH and certain soil components was examined with an equilibrium batch technique by the use of a CH 3 COOH--NH 4 OH extracting system. The influence of various soil components on 238 Pu and 242 Cm extractability was determined indirectly by selective removal of the components from the soil. The soil organic matter appeared to have a major influence on the extractability of these radionuclides. Though to a lesser extent, free iron oxides exerted an influence also. Before removal of soil organic matter, the extractability curves for these radionuclides were qualitatively similar in general form. The nature of this form is discussed. Within the contaminated, untreated soil, the 238 Pu and 242 Cm extractability ranged from 0.60 to 30.8% and 0.11 to 14.83% of dose, respectively, depending on the pH of the extracting solution. The liquid-to soild-phase ratio (K'/sub d/) values ranged from 3.5 x 10 -4 to 2.7 x 10 -2 for 238 Pu and 0.9 x 10 -4 to 1.4 x 10 -2 for 242 Cm. Very low extractability occurred in the pH range from approx. 8.6 to approx. 9.7 for 238 Pu and from 7.6 to approx. 9.7 for 242 Cm

  9. TAK-242, a small-molecule inhibitor of Toll-like receptor 4 signalling, unveils similarities and differences in lipopolysaccharide- and lipid-induced inflammation and insulin resistance in muscle cells.

    Science.gov (United States)

    Hussey, Sophie E; Liang, Hanyu; Costford, Sheila R; Klip, Amira; DeFronzo, Ralph A; Sanchez-Avila, Alicia; Ely, Brian; Musi, Nicolas

    2012-11-30

    Emerging evidence suggests that TLR (Toll-like receptor) 4 and downstream pathways [MAPKs (mitogen-activated protein kinases) and NF-κB (nuclear factor κB)] play an important role in the pathogenesis of insulin resistance. LPS (lipopolysaccharide) and saturated NEFA (non-esterified fatty acids) activate TLR4, and plasma concentrations of these TLR4 ligands are elevated in obesity and Type 2 diabetes. Our goals were to define the role of TLR4 on the insulin resistance caused by LPS and saturated NEFA, and to dissect the independent contribution of LPS and NEFA to the activation of TLR4-driven pathways by employing TAK-242, a specific inhibitor of TLR4. LPS caused robust activation of the MAPK and NF-κB pathways in L6 myotubes, along with impaired insulin signalling and glucose transport. TAK-242 completely prevented the inflammatory response (MAPK and NF-κB activation) caused by LPS, and, in turn, improved LPS-induced insulin resistance. Similar to LPS, stearate strongly activated MAPKs, although stimulation of the NF-κB axis was modest. As seen with LPS, the inflammatory response caused by stearate was accompanied by impaired insulin action. TAK-242 also blunted stearate-induced inflammation; yet, the protective effect conferred by TAK-242 was partial and observed only on MAPKs. Consequently, the insulin resistance caused by stearate was only partially improved by TAK-242. In summary, TAK-242 provides complete and partial protection against LPS- and NEFA-induced inflammation and insulin resistance, respectively. Thus, LPS-induced insulin resistance depends entirely on TLR4, whereas NEFA works through TLR4-dependent and -independent mechanisms to impair insulin action.

  10. TAK-242, a small-molecule inhibitor of Toll-like receptor 4 signalling, unveils similarities and differences in lipopolysaccharide- and lipidinduced inflammation and insulin resistance in muscle cells

    Science.gov (United States)

    Hussey, Sophie E.; Liang, Hanyu; Costford, Sheila R.; Klip, Amira; DeFronzo, Ralph A.; Sanchez-Avila, Alicia; Ely, Brian; Musi, Nicolas

    2012-01-01

    Emerging evidence suggests that TLR (Toll-like receptor) 4 and downstream pathways [MAPKs (mitogen-activated protein kinases) and NF-κB (nuclear factor κB)] play an important role in the pathogenesis of insulin resistance. LPS (lipopolysaccharide) and saturated NEFA (non-esterified fatty acids) activate TLR4, and plasma concentrations of these TLR4 ligands are elevated in obesity and Type 2 diabetes. Our goals were to define the role of TLR4 on the insulin resistance caused by LPS and saturated NEFA, and to dissect the independent contribution of LPS and NEFA to the activation of TLR4-driven pathways by employing TAK-242, a specific inhibitor of TLR4. LPS caused robust activation of the MAPK and NF-κB pathways in L6 myotubes, along with impaired insulin signalling and glucose transport. TAK-242 completely prevented the inflammatory response (MAPK and NF-κB activation) caused by LPS, and, in turn, improved LPS-induced insulin resistance. Similar to LPS, stearate strongly activated MAPKs, although stimulation of the NF-κB axis was modest. As seen with LPS, the inflammatory response caused by stearate was accompanied by impaired insulin action. TAK-242 also blunted stearate-induced inflammation; yet, the protective effect conferred by TAK-242 was partial and observed only on MAPKs. Consequently, the insulin resistance caused by stearate was only partially improved by TAK-242. In summary, TAK-242 provides complete and partial protection against LPS- and NEFA-induced inflammation and insulin resistance, respectively. Thus, LPS-induced insulin resistance depends entirely on TLR4, whereas NEFA works through TLR4-dependent and -independent mechanisms to impair insulin action. PMID:23050932

  11. The synthesis and complex anion-vacancy ordered structure of La0.33Sr0.67MnO2.42

    International Nuclear Information System (INIS)

    Dixon, Edward; Hadermann, Joke; Hayward, Michael A.

    2011-01-01

    The low-temperature topotactic reduction of La 0.33 Sr 0.67 MnO 3 with NaH results in the formation of La 0.33 Sr 0.67 MnO 2.42 . A combination of neutron powder and electron diffraction data show that La 0.33 Sr 0.67 MnO 2.42 adopts a novel anion-vacancy ordered structure with a 6-layer OOTOOT' stacking sequence of the 'octahedral' and tetrahedral layers (Pcmb, a=5.5804(1) A, b=23.4104(7) A, c=11.2441(3) A). A significant concentration of anion vacancies at the anion site, which links neighbouring 'octahedral' layers means that only 25% of the 'octahedral' manganese coordination sites actually have 6-fold MnO 6 coordination, the remainder being MnO 5 square-based pyramidal sites. The chains of cooperatively twisted apex-linked MnO 4 tetrahedra adopt an ordered -L-R-L-R- arrangement within each tetrahedral layer. This is the first published example of a fully refined structure of this type which exhibits such intralayer ordering of the twisted tetrahedral chains. The rationale behind the contrasting structures of La 0.33 Sr 0.67 MnO 2.42 and other previously reported reduced La 1-x Sr x MnO 3-y phases is discussed. - Graphical Abstract: The topotactic reduction of the perovskite phase La 0.33 Sr 0.67 MnO 3 with NaH yields La 0.33 Sr 0.67 MnO 2.42(3) , which adopts a novel anion vacancy ordered structure with a 6-layer OOTOOT' stacking sequence of the 'octahedral' and tetrahedral layers. The anion site that links the neighbouring octahedral layers is partially occupied so only 25% of the 'octahedral' manganese sites actually have 6-fold MnO 6 coordination. Highlights: → Topotactic reduction with NaH to form a mixed valent Mn 2+ /Mn 3+ phase. → Novel layered anion-vacancy ordered structure. → Comparison to related brownmillerite structure types.

  12. Savannah River Plant californium-252 Shuffler electronics manual

    International Nuclear Information System (INIS)

    Bourret, S.C.; Crane, T.W.; Eccleston, G.W.; Gallegos, E.A.; Garcia, D.L.

    1980-03-01

    Detailed information is presented in this report, an electronics manual for the Savannah River Plant Shuffler, about the electronics associated with the various control and data acquisition functions of the Shuffler subsystems. Circuit diagrams, interconnection information, and details about computer control and programming are included

  13. Survey of potential markets for devices using Californium-252

    International Nuclear Information System (INIS)

    Permar, P.H.

    1975-01-01

    Potential applications for devices or systems containing 252 Cf in the years from 1975 to 1980 are estimated. The estimated number of devices and associated business value were derived from a survey of 46 industrial, educational and governmental organizations conducted from Jan. to May, 1975. Applications for devices and systems based on 252 Cf are expected to increase by a factor of 7 in the 6-y period from 1975 to 1980. The annual business value of 252 Cf devices should increase from 1.5 million dollars in 1975 to 10.8 million dollars in 1980. The potential European market should be several times as large as the US market, based on actual sales of 252 Cf, which have been two to four times greater in Europe than in the US

  14. The protective cell petrus for the production of californium 252

    International Nuclear Information System (INIS)

    Sontag, R.; Berger, R.

    1967-01-01

    The alpha, beta, gamma, neutron cell which is described in the present paper is devoted to the transplutonium element production and study. It is located at the CEN in Fontenay-aux-Roses (France). The 4 feet ordinary concrete shielding made of stacked blocs allows the manipulation of radioactive sources as high as 1000 curies of 1 MeV gamma rays and with a fast neutrons flux of 10 9 n.cm -2 .s -1 . The airtight alpha containment box is equipped with two transfer systems, one consists of a parallelepiped shaped airtight box located in a turntable, the other uses standard cylindrical containers made of polyethylene. The general equipment and the main setting up are also described. (authors) [fr

  15. Automated absolute activation analysis with californium-252 sources

    International Nuclear Information System (INIS)

    MacMurdo, K.W.; Bowman, W.W.

    1978-09-01

    A 100-mg 252 Cf neutron activation analysis facility is used routinely at the Savannah River Laboratory for multielement analysis of many solid and liquid samples. An absolute analysis technique converts counting data directly to elemental concentration without the use of classical comparative standards and flux monitors. With the totally automated pneumatic sample transfer system, cyclic irradiation-decay-count regimes can be pre-selected for up to 40 samples, and samples can be analyzed with the facility unattended. An automatic data control system starts and stops a high-resolution gamma-ray spectrometer and/or a delayed-neutron detector; the system also stores data and controls output modes. Gamma ray data are reduced by three main programs in the IBM 360/195 computer: the 4096-channel spectrum and pertinent experimental timing, counting, and sample data are stored on magnetic tape; the spectrum is then reduced to a list of significant photopeak energies, integrated areas, and their associated statistical errors; and the third program assigns gamma ray photopeaks to the appropriate neutron activation product(s) by comparing photopeak energies to tabulated gamma ray energies. Photopeak areas are then converted to elemental concentration by using experimental timing and sample data, calculated elemental neutron capture rates, absolute detector efficiencies, and absolute spectroscopic decay data. Calculational procedures have been developed so that fissile material can be analyzed by cyclic neutron activation and delayed-neutron counting procedures. These calculations are based on a 6 half-life group model of delayed neutron emission; calculations include corrections for delayed neutron interference from 17 O. Detection sensitivities of 239 Pu were demonstrated with 15-g samples at a throughput of up to 140 per day. Over 40 elements can be detected at the sub-ppM level

  16. Savannah River Plant Californium-252 Shuffler software manual

    International Nuclear Information System (INIS)

    Johnson, S.S.; Crane, T.W.; Eccleston, G.W.

    1979-03-01

    A software manual for operating the Savannah River Plant Shuffler nondestructive assay instrument is presented. The procedures for starting up the instrument, making assays, calibrating, and checking the performance of the hardware units are described. A list of the error messages with an explanation of the circumstances prompting the message and possible corrective measures is given. A summary of the software package is included showing the names and contents of the files and subroutines. The procedure for modifying the software package is outlined

  17. Californium-252 interstitial implants in carcinoma of the tongue

    International Nuclear Information System (INIS)

    Vtyurin, B.M.; Ivanov, V.N.; Medvedev, V.S.; Galantseva, G.F.; Abdulkadyrov, S.A.; Ivanova, L.F.; Petrovskaya, G.A.; Plichko, V.I.

    1985-01-01

    A clinical study using 252 Cf sources in brachytherapy of tumors began in the Research Institute of Medical Radiology of the Academy of Medical Sciences of the USSR in 1973. 252 Cf afterloading cells were utilized by the method of simple afterloading. Dosimetry and radiation protection of medical personnel were developed. To substantiate optimal therapeutic doses of 252 Cf neutrons, a correlation of dose, time, and treatment volume factors with clinical results of 252 Cf interstitial implants in carcinoma of the tongue for 47 patients with a minimum follow-up period of 1 year was studied. Forty-nine interstitial implants have been performed. Seventeen patients received 252 Cf implants alone (Group I), 17 other patients received 252 Cf implants in combination with external radiation (Group II), and 15 patients were treated with interstitial implants for recurrent or residual tumors (Groups III). Complete regression of carcinoma of the tongue was obtained in 48 patients (98%). Thirteen patients (27%) developed radiation necrosis. The therapeutic dose of neutron radiation from 252 Cf sources in interstitial radiotherapy of primary tongue carcinomas (Group I) was found to be 7 to 9 Gy. Optimal therapeutic neutron dose in combined interstitial and external radiotherapy of primary tumors (Group II) was 5 to 6 Gy with an external radiation dose of 40 Gy. For recurrent and residual tumors (Group III), favorable results were obtained with tumor doses of 6.5 to 7 Gy

  18. Undergraduate experiments using the neutron radiation from californium-252

    International Nuclear Information System (INIS)

    Rossel, J.; Golecki, I.

    1976-01-01

    Three experiments designed to demonstrate and measure several properties of the neutron radiation emitted by a 3μg 252 Cf source are described. The experiments constitute a special project carried out by a third-year undergraduate student at the Institute of Physics of the University of Neuchatel. The 252 Cf source is enclosed in a shield which allows a pencil of fast neutrons to pass through a central tube, while reducing the ambient radiation below the tolerance level. The shield consists of layers of borated paraffin wax, iron and cadmium. The first experiment uses an air-alcohol diffusion cloud chamber for the demonstration of tracks of recoil protons produced by the neutrons. Semi-quantitative measurements of track lengths give the correct order of magnitude of the proton energies. In the second experiment a liquid scintillator detector is used to scan the beam profile across the radiation shield enclosing the source. A pulse-shape-discrimination system discriminates between neutrons and gamma photons. The third experiment makes use of the nuclear emulsion technique to study the neutron energy distribution of 252 Cf. Preliminary results are compared with published values. (author)

  19. Investigation of the chemical explosion of an ion exchange resin column and resulting americium contamination of personnel in the 242-Z building, August 30, 1976

    Energy Technology Data Exchange (ETDEWEB)

    1976-10-19

    As a result of an explosion in the Waste Treatment Facility, 242-Z Building, 200 West Area of the Hanford Reservation on August 30, 1976, the Manager of the Richland Operations Office (RL), Energy Research and Development Administration (ERDA), appointed an ERDA Committee to conduct a formal investigation and to prepare a report on their findings of this occurrence. The Committee was instructed to conduct the investigation in accordance with ERDAMC 0502, insofar as circumstances would permit, to cover and explain technical elements of the casual sequence(s) of the occurrence, and to describe management systems which should have or could have prevented the occurrence. This report is the result of the investigation and presents the conclusions of the review.

  20. Performance Characterization of Loctite (Registered Trademark) 242 and 271 Liquid Locking Compounds (LLCs) as a Secondary Locking Feature for International Space Station (ISS) Fasteners

    Science.gov (United States)

    Dube, Michael J.; Gamwell, Wayne R.

    2011-01-01

    Several International Space Station (ISS) hardware components use Loctite (and other polymer based liquid locking compounds (LLCs)) as a means of meeting the secondary (redundant) locking feature requirement for fasteners. The primary locking method is the fastener preload, with the application of the Loctite compound which when cured is intended to resist preload reduction. The reliability of these compounds has been questioned due to a number of failures during ground testing. The ISS Program Manager requested the NASA Engineering and Safety Center (NESC) to characterize and quantify sensitivities of Loctite being used as a secondary locking feature. The findings and recommendations provided in this investigation apply to the anaerobic LLCs Loctite 242 and 271. No other anaerobic LLCs were evaluated for this investigation. This document contains the findings and recommendations of the NESC investigation

  1. Simultaneous measurement of 239Pu, 240Pu, 241Pu, and 242Pu by high resolution inductively coupled plasma mass spectrometer (HR ICP-MS) in marine sediments

    International Nuclear Information System (INIS)

    Bruneau, F.

    1999-01-01

    Transuranics elements are of particular interest in radioecological studies because of their radiotoxicity and their potential use to decipher source fingerprints and transport processes. The simultaneous measurement of 239 Pu, 240 Pu, 241 Pu, and 242 Pu in environmental samples requires a specific chemical procedure. This work deals with an analytical procedure which yields a very high grade of purification of Pu suitable for ultra low level detection by HR ICP-MS, from marine sediments. After the elimination of major elements (Fe, Al, Mg...) by a first chromatographic separation, a new device of purification by solvent extraction and concentration by a second chromatographic separation is used to obtain a concentrated and high purified solution of plutonium. The chemical procedure have been validated on IAEA certified sediment samples and on sediment samples collected in the roads of Cherbourg which had been previously analysed by other techniques (a spectrometry and thermo-ionisation mass spectrometer). (author)

  2. Estimation of Ni63, Pu241, Pu242 and Am243 from Co60, Pu239, and Cm244 activities in groundwater samples

    International Nuclear Information System (INIS)

    Holcomb, H.P.

    1993-01-01

    The Part B Permit for F ampersand H Seepage Basins calls for analysis of several constituents of concern in groundwater monitoring wells. Four of these analytes are the radionuclides Ni 63 , Pu 241 , Pu 242 , and Am 243 . These are currently not being analyzed due to their very difficult, tedious analytical schemes coupled with their relatively low activity values. This report demonstrates how the activity value for Ni 63 , a week beta emitter, can be estimated from that of Co 60 , an easily detectable, high-energy gamma emitter. Similarly, estimates of Pu 241 , a beta emitter, and the alpha-emitting Pu 242 can be made from the activity value of the more easily detected Pu 239 . Am 243 can be estimated from the activity of Cm 244 , which is easier to detect because of a shorter half-life (higher specific activity) and the emission of higher energy alpha particles. These correlations are made under very specific parameters in order to ensure the validity of this approach. Therefore, assumptions must be established setting ground rules for establishing these activity relationships. Bases for these assumptions are explained and/or referenced. Their degree of uncertainty limits the accuracy of the data so that the term ''estimate'' is used. Such soundly-based, conservative estimates for these four rads can provide a tool for evaluating any hazards from their presence over the next several years. Hopefully, during this time, sufficient advances will be made in their radiochemical analyses and in counting techniques so that in the future, their activities may be quantitatively determined more easily and also more cost effectively

  3. Separation and activity determination of 239+240Pu, 241Am and Curium (242and244Cm) in evaporator concentrate by Alpha Spectrometry

    International Nuclear Information System (INIS)

    Reis Junior, Aluisio S.; Temba, Eliane S.C.; Kastner, Geraldo F.; Monteiro, Roberto P.G.

    2013-01-01

    Alpha spectrometry analysis was used for activity determinations of Pu, Am and Cm isotopes in evaporator concentrate samples from nuclear power plants. Using a sequential procedure the first step was Pu isolation by an anion exchange column followed by an Am and Cm separation of U and Fe by a co-precipitation with oxalic acid. The precipitate was used for americium and curium separation of strontium by using a TRU resin extraction chromatography column. Due to their chemical similarities and energy difference it was seen that the simultaneous determination of 241 Am, 242 Cm and 24 3 ,244 Cm isotopes is possible using the 243 Am as tracer, once they have peaks in different region of interest (ROI) in the alpha spectrum. In this work it was used tracers, 238 Pu, 243 Am, 244 Cm and 232 U, for determination and quantification of theirs isotopes, respectively. The standard deviations for replicate analysis were calculated and for 241 Am it was (1,040 ± 160 mBqKg -1 ), relative standard deviation 15.38%, and for 239+240 Pu it was (551 +- 44 mBqKg -1 ), relative standard deviation 7.98%. In addition, for the 242 Cm isotope the standard deviation for determinations was(75 ± 23 mBqKg -1 ), with the relative standard deviation 30.67% higher than for 241 Am and 239+240 Pu. The radiometric yields ranged from 90% to 105% and the lower limit of detection was estimated as being 2.05 mBqKg -1 . (author)

  4. pH responsive label-assisted click chemistry triggered sensitivity amplification for ultrasensitive electrochemical detection of carbohydrate antigen 24-2.

    Science.gov (United States)

    Zheng, Yun; Zhao, Lihua; Ma, Zhanfang

    2018-05-15

    Sensitivity amplification strategy by implementing click chemistry in the construction of biosensing interface can efficiently improve the performance of immunosensor. Herein, we developed a sandwich-type amperometric immunosensor for ultrasensitive detection of carbohydrate antigen 24-2 (CA 242) based on pH responsive label-assisted click chemistry triggered sensitivity amplification strategy. The sensitivity of amperometric immunosensor relies on the current response differences (ΔI) caused by per unit concentration target analyte. The pH responsive Cu 2+ -loaded polydopamine (CuPDA) particles conjugated with detection antibodies were employed as labels, which can release Cu(II) ions by regulating pH. In the presence of ascorbic acid (reductant), Cu(II) ions were reduced to Cu(I) ions. Azide-functionalized double-stranded DNA (dsDNA) as signal enhancer was immobilized on the substrate through Cu + -catalyzed azide/alkyne cycloaddition reaction. With the help of the click reaction, the ΔI caused by target was elevated prominently, resulting in sensitivity amplification of the immunosensor. Under optimal condition, the proposed immunosensor exhibited excellent performance with linear range from 0.0001 to 100 U mL -1 and ultralow detection limit of 20.74 μU mL -1 . This work successfully combines click chemistry with pH-responsive labels in sandwich-type amperometric immunosensor, providing a promising sensitivity amplification strategy to construct immunosensing platform for analysis of other tumor marker. Copyright © 2018 Elsevier B.V. All rights reserved.

  5. A 242-year seasonal-resolved speleothem record from Hainan Island: A window into variability of the precipitation δ18O in East Asia

    Science.gov (United States)

    Cai, Y.; An, Z.; Cheng, H.; Edwards, R. L.; Fung, I. Y.; Zhang, H.; Tan, L.; Bi, H.

    2016-12-01

    Hainan Island is located at the gateway of East Asian summer monsoon to the continent. The typical tropical monsoon climate at Hainan island is characterized by wet season during the summer and autumn and dry season during the winter and spring. Here, we present a seasonal resolved speleothem record spanning 242 years ( 50-292 AD) from Xianren Cave (E109°25`, N18°34`), which is situated in the Baoting County, Hainan Province. The monitoring inside the cave shows that the relative humidity kept saturated during the observed periods (one and half years) while the temperature varied seasonally following the temperature changes outside the cave, but with much smaller amplitude. Monthly observation of drip water inside the cave indicates that the isotope composition of drip water mainly responds to the changes in the precipitation isotope composition with less than two months' resident time. The visible annual lamination and distinct fluctuations of calcite Mg, Sr and Ba concentrations corroborate that the high-frequency oscillations of calcite δ18O largely capture the seasonal variation of the isotope composition of precipitation, although the temperature effect cannot be excluded. By setting the heaviest value of annual variation of calcite δ18O as the beginning of each annual cycle, we transferred the δ18O record of 11.2 cm in depth to a δ18O record of 242-year in age. The δ18O record of stalagmite XR-3 demonstrate clearly the annual, decadal and multi-decadal variations of amplitude from 2 to 4‰, in addition to the seasonal oscillation of amplitude varied from 1.5 to 2.5‰. The ensemble empirical mode decomposition results show that the dominant variability (54.6% of the total variance) is captured by the components at the timescale of 3-7 year, while the components on timescales of 22-24 -year, 80-year and 120-year capture 35.0%, 7.0% and 3.4% of the variance, respectively. We contribute the variability of speleothem δ18O at the timescale of 3-7 -year to

  6. The production of {sup 238-242}Pu(n,γ){sup 239-243}Pu fissionable fluids in a fusion-fission hybrid reactor

    Energy Technology Data Exchange (ETDEWEB)

    Guenay, Mehtap [Inoenue Univ., Malatya (Turkey). Physics Dept.

    2014-03-15

    In this study, the effect of spent fuel grade plutonium content on {sup 239-243}Pu was investigated in a designed hybrid reactor system. In this system, the fluids were composed of a molten salt, heavy metal mixture with increased mole fractions 99-95 % Li{sub 20}Sn{sub 80}-1-5 % SFG-Pu, 99-95 % Li{sub 20}Sn{sub 80}-1-5 % SFG-PuF{sub 4}, 99-95 % Li{sub 20}Sn{sub 80}-1-5 % SFG-PuO{sub 2}. Beryllium (Be) is a neutron multiplier by (n,2n) reactions. Thence, a Be zone of 3 cm thickness was used in order to contribute to fissile fuel breeding between the liquid first wall and a 9Cr2WVTa ferritic steel blanket which is used as structural material. The production of {sup 238-242}Pu(n,γ){sup 239-243}Pu was calculated in liquid first wall, blanket and shielding zones. Three-dimensional nucleonic calculations were performed by using the most recent version MCNPX-2.7.0 Monte Carlo code and nuclear data library ENDF/B-VII.0. (orig.)

  7. Complex chromosomal rearrangement in a girl with psychomotor-retardation and a de novo inversion: inv(2)(p15;q24.2).

    Science.gov (United States)

    Granot-Hershkovitz, Einat; Raas-Rothschild, Annick; Frumkin, Ayala; Granot, David; Silverstein, Shira; Abeliovich, Dvorah

    2011-08-01

    Cytogenetic analysis of DNA from a girl with severe psychomotor retardation revealed a de novo pericentric inversion of chromosome 2: 46,XX,inv(2)(p15q24.2). In order to elucidate the possible role of the inversion in the girl's abnormal phenotype, we analyzed the inversion breakpoints. FISH analysis revealed BAC clones spanning the breakpoints at 2p and 2q of the inversion. Southern blot hybridization with DNA probes from the BAC regions was used to refine the localization of the breakpoints, followed by inverse-PCR which enabled us to sequence the inversion breakpoints. We found a complex chromosomal rearrangement, including five breakpoints, four at 2q and one at 2p joined with minor insertions/deletions of a few bases. The breakpoint at 2p was within the NRXN1 gene that has previously been associated with autism, intellectual disabilities, and psychiatric disorders. In 2q, the breakpoints disrupted two genes, TANC1 and RBMS1; the phenotypic effect of these genes is not currently known. Copyright © 2011 Wiley-Liss, Inc.

  8. Investigation of association between donors' and recipients' NADPH oxidase p22(phox) C242T polymorphism and acute rejection, delayed graft function and blood pressure in renal allograft recipients.

    Science.gov (United States)

    Mandegary, Ali; Rahmanian-Koshkaki, Sara; Mohammadifar, Mohammad-Amir; Pourgholi, Leila; Mehdipour, Mohammad; Etminan, Abbas; Ebadzadeh, Mohammad-Reza; Fazeli, Faramarz; Azmandian, Jalal

    2015-01-01

    Production of reactive oxygen species (ROS) and thereby induction of oxidative stress seem to be one of the major mediators of inflammatory adverse outcomes after renal transplantation. p22(phox) is a polymorphic subunit of NAD(P)H-oxidase that is critical for activation and stabilization of the enzyme. This enzyme is involved in the production of superoxide that triggers inflammatory injuries to the kidney. So in this study, the association between donors and recipients' C242T polymorphism of p22(phox) and acute rejection (AR), delayed graft function (DGF), creatinine clearance (CrCl), and blood pressure in renal-allograft recipients was studied. One hundred ninety six donor-recipient pairs were studied. The C242T polymorphism of p22(phox) was determined using polymerase chain reaction-restriction fragment length polymorphism (PCR-RFLP). According to p22 genotype, the subjects were divided in wild-type (CC) and T allele carriers (CT+TT). Transplantation outcomes were determined using acute rejection and delayed graft function criteria. The mean arterial pressure was also measured monthly after transplantation. There was a significant association between the recipients' p22(phox) polymorphism and DGF occurrence (OR=2.5, CI: 1.2-4.9, p=0.0009). No significant association was detected between donors' p22(phox) polymorphism and AR and DGF events. CrCl during the six months follow-up after transplantation was lower in the patients who received allograft from donors carrying 242T allele (B=-12.8, CI: -22.9-12.8 (-22.9 to -2.6)). Changes in the blood pressure were not different among the patients having different genotypes of p22(phox). These results suggest that the recipients' p22(phox) C242T polymorphism may be a major risk factor for DGF in renal transplantation. Moreover, the donors' 242T allele seems to affect the rate of CrCl in the renal allograft recipients. Copyright © 2014. Published by Elsevier B.V.

  9. Effects of a superantigen-antibody recombinant fusion protein (r-C242 Fab-SEA) on toxicological responses in the anaesthetised rabbit

    International Nuclear Information System (INIS)

    Ilbaeck, Nils-Gunnar; Gunnarsson, Kjell; Persson, Robert; Lindh, Ulf; Staaalhandske, Torbjoern

    2003-01-01

    The objective was to study toxin-induced effects on physiological parameters in the rabbit and whether these parameters show dose-response and co-variation after administration of a recombinant fusion protein between staphylococcal enterotoxin (SE) and the Fab fragment of an antibody. Rabbits are very sensitive to SE toxins and the cardiovascular and immune effects are similar to those observed in septic shock in man. The test compound, r-C242 Fab-SEA, was administered intravenously to anaesthetised New Zealand white rabbits at doses in the range of 0.00005-50 μg/kg. All rabbits were checked for titres of anti-SEA antibodies before entering the experiment, since they could neutralise the effect of the test compound. Heart rate, blood pressure and body temperature were continuously monitored before and during 6 h after dosing. Immediately before the start of administration and 3 and 6 h during the experiment, blood gases (pO 2 and pCO 2 ), pH, haematology, clinical chemistry, cytokine response (TNF-α) and trace elements (Mn, Cu, Zn, Se, Ag, Cd, Hg and Pb) were measured. No mortality occurred, but at 50 μg/kg severe adverse clinical signs developed. The decrease in blood pressure was weakly dose-related. Heart rate, ECG, body temperature, pCO 2 and pH were not affected by the treatment. pO 2 tended to increase as a function of time, but not in relation to dose. WBC and PLT decreased dose dependently. TNF-α was not affected by the treatment. The major effects on clinical chemistry were a dose-dependent increase in AST and creatinine. Potassium and urea showed dose dependent increases, mainly at higher doses, though these changes were of less value for drug selection purposes. Trace element changes were observed, including an increase in Mn and a decrease of Zn at all doses. The Cu/Zn ratio decreased below normal at low doses, whereas at high doses in which adverse effects developed, it increased above normal. Post mortem examination revealed minimal to moderate

  10. 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...

  11. A severe connatal form of Pelizaeus Merzbacher disease in a Czech boy caused by a novel mutation (725C>A, Ala242Glu) at the 'jimpy(msd) codon' in the PLP gene.

    Science.gov (United States)

    Seeman, Pavel; Paderova, Katerina; Benes, Vladimir; Sistermans, Erik A

    2002-02-01

    Pelizaeus Merzbacher disease (PMD) is an X-linked recessive disorder of the central nervous system myelination caused by mutations involving the proteolipid protein gene (PLP). Early nystagmus and developmental delay, progressive pyramidal, cerebellar and dystonic signs as well as white matter changes in brain MRI are typical for PMD. The PLP gene can be affected by two major types of mutations. A duplication of the whole PLP gene is the most common mutation and results usually in the milder classical phenotype, whereas point mutations in PLP gene often result in the rarer and more severe connatal form of PMD. The PLP protein is a higly conserved across species and is identical in human, mouse and rat. We describe a 13-year-old Czech boy with an early and severe developmental delay. His maternal uncle died at the age of one year and was also early and severely psychomotoricly retarded. The patient was the first child of healthy unrelated parents born after an uneventful pregnancy and delivery in 1988. Hyperbilirubinemia and bronchopneumonia and early stridor complicated his neonatal period. Diffuse hypotonia, nystagmus, psychomotor retardation, visual and hearing impairment have been observed in the patient since the age of 6 weeks. White matter abnormalities, cortical and periventricular atrophy were detected by MRI at the age of 6 and 11 years, respectively. Despite these signs and results an accurate clinical diagnosis was unclear until the age of 11 years. Last neurological examination in 1999 showed no nystagmus anymore, but extremely dystrophic limbs, truncal deformation, due to severe scoliosis, tetraplegia with hyperreflexia in C5C7 and areflexia L2S2 and positive pyramidal signs. The boy had no visual or speech contact. DNA tests followed the clinical suspicion for PMD. At first, duplication of PLP gene was excluded by quantitative comparative PCR. Direct sequencing of PLP gene detected a novel mutation in exon 6, a missense mutation 725C-->A (Ala242Glu

  12. The fission cross sections of 230Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu relative 235U at 14.74 MeV neutron energy

    International Nuclear Information System (INIS)

    Meadows, J.W.

    1986-12-01

    The measurement of the fission cross section ratios of nine isotopes relative to 235 U at an average neutron energy of 14.74 MeV is described with particular attention to the determination of corrections and to sources of error. The results are compared to ENDF/B-V and to other measurements of the past decade. The ratio of the neutron induced fission cross section for these isotopes to the fission cross section for 235 U are: 230 Th - 0.290 +- 1.9%; 232 Th - 0.191 +- 1.9%; 233 U - 1.132 +- 0.7%; 234 U - 0.998 +- 1.0%; 236 U - 0.791 +- 1.1%; 238 U - 0.587 +- 1.1%; 237 Np - 1.060 +- 1.4%; 239 Pu - 1.152 +- 1.1%; 242 Pu - 0.967 +- 1.0%. 40 refs., 11 tabs., 9 figs

  13. Effect of (3,5,6-trimethylpyrazin-2-yl)methyl 2-[4-(2-methylpropyl)phenyl]propanoate (ITE), a newly developed anti-inflammatory drug, on type II collagen-induced arthritis in mice.

    Science.gov (United States)

    Ma, Tao; Cao, Ying-Lin; Xu, Bei-Bei; Zhou, Xiao-Mian

    2004-06-01

    The effect of (3,5,6-trimethylpyrazin-2-yl)methyl 2-[4-(2-methylpropyl)phenyl]propanoate (ITE) on type II collagen (CII)-induced arthritis in mice was studied. Mice were immunized twice with CII, ITE being given orally once a day for 40 d after the 1st immunization. Clinical assessment showed that ITE had no effect on the day of onset of arthritis but did lowered the incidence rate of arthritis and the arthritis score. And ITE had a marked suppressive effect on the mouse hind paw edema induced by CII. ITE suppressed the delayed-type mouse ear skin reaction to CII but had no effect on the level of serum anti-CII antibodies. These results suggest that ITE inhibits the development of CII-induced arthritis in mice by suppressing delayed-type hypersensitivity to CII.

  14. P-glycoprotein binds to ezrin at amino acid residues 149-242 in the FERM domain and plays a key role in the multidrug resistance of human osteosarcoma.

    Science.gov (United States)

    Brambilla, Daria; Zamboni, Silvia; Federici, Cristina; Lugini, Luana; Lozupone, Francesco; De Milito, Angelo; Cecchetti, Serena; Cianfriglia, Maurizio; Fais, Stefano

    2012-06-15

    Overexpression of the mdr1 gene encoding P-glycoprotein (Pgp) exerts a major role in reducing the effectiveness of cytotoxic therapy in osteosarcoma. The interaction between actin and Pgp has been shown to be instrumental in the establishment of multidrug resistance (MDR) in human tumor cells. The cytoskeleton linker ezrin exerts a pivotal role in maintaining the functional connection between actin and Pgp. We investigated the role of ezrin in a human multidrug-resistant osteosarcoma cell line overexpressing Pgp and compared it to its counterpart that overexpresses an ezrin deletion mutant. The results showed that Pgp binds at amino acid residues 149-242 of the N-terminal domain of ezrin. The interaction between ezrin and Pgp occurs in the plasma membrane of MDR cells, where they also co-localize with the ganglioside G(M1) located in lipid rafts. The overexpression of the ezrin deletion mutant entirely restored drug susceptibility of osteosarcoma cells, consistent with Pgp dislocation to cytoplasmic compartments and abrogation of G(M1) /Pgp co-localization at the plasma membrane. Our study provides evidence that ezrin exerts a key role in MDR of human osteosarcoma cells through a Pgp-ezrin-actin connection that is instrumental for the permanence of Pgp into plasma membrane lipid rafts. We also show for the first time that Pgp-binding site is localized to amino acid residues 149-242 of the ezrin Band 4.1, Ezrin/Radixin/Moesin (FERM) domain, thus proposing a specific target for future molecular therapy aimed at counteracting MDR in osteosarcoma patients. Copyright © 2011 UICC.

  15. The protective cell petrus for the production of californium 252; Cellule blindee petrus pour la production et l'etude du californium 252

    Energy Technology Data Exchange (ETDEWEB)

    Sontag, R; Berger, R [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1967-07-01

    The alpha, beta, gamma, neutron cell which is described in the present paper is devoted to the transplutonium element production and study. It is located at the CEN in Fontenay-aux-Roses (France). The 4 feet ordinary concrete shielding made of stacked blocs allows the manipulation of radioactive sources as high as 1000 curies of 1 MeV gamma rays and with a fast neutrons flux of 10{sup 9} n.cm{sup -2}.s{sup -1}. The airtight alpha containment box is equipped with two transfer systems, one consists of a parallelepiped shaped airtight box located in a turntable, the other uses standard cylindrical containers made of polyethylene. The general equipment and the main setting up are also described. (authors) [French] La cellule alpha, beta, gamma, neutron, qui fait l'objet du present article, est destinee a la production et a l'etude des elements transplutoniens. Elle est construite au C.E.N. de Fontenay-aux-Roses (France). La protection biologique, calculee pour une activite de 1000 curies de rayonnement gamma d'energie 1 MeV accompagnee d'un flux de neutrons rapides de 10{sup 9}/cm{sup 2}s, est constituee par des parois en beton de 1,20 m d'epaisseur. L'enceinte alpha est une boite etanche qui comporte devx systemes de transferts: l'un consiste en une boite parallelepipedique etanche logee dans un barillet, l'autre fait appel a des recipients cylindriques standard en polyethylene. L'equipement general et les installations les plus importantes sont ensuite decrits. (auteurs)

  16. A model for the Lin-Shu type density-wave structure of our Galaxy: Line-of-sight and transverse-longitudinal velocities of 242 optically visible open clusters

    Science.gov (United States)

    Griv, E.; Jiang, I.-G.

    2015-02-01

    In this paper, the fourth in a series, we examine again one of the implications of the Lin-Shu density-wave theory, specifically, the noncircular systematic motion of the Galactic objects. Our previous investigation is extended by analyzing simultaneously both the line-of-sight and transversal velocities of a sample of open clusters for which velocities, distances and ages are available. The ordinary equations of the Oort-Lindblad theory of galactic differential rotation are used. The minor effects caused by the two-dimensional tightly-wound density waves are also taken into account. The published data of 242 currently known optically visible clusters having distances rsight and transversal along the Galactic longitude velocities are nearly equal. We argue that the resemblance of these Galactic wave structures is so remarkable that no doubt is felt as to the theory's truth with respect to these data. The results obtained allow us to conclude that several low-m trailing density-wave patterns with different number of spiral arms m (say, m=1, 2, 3, and 4), pitch angles (about 5o, 8o, 11o, and 14o, respectively) and amplitudes of the perturbed gravitational potential may coexist in the Galaxy. The latter suggests the asymmetric multiarm, not well-organized (``flocculent'') spiral structure of the system. In memory of Professors Alexei M. Fridman (1940-2010) and Chi Yuan (1937-2008)

  17. Application of fission track detectors to californium-252 neutron dosimetry in tissue near the radiation source

    International Nuclear Information System (INIS)

    Oswald, R.A.; Lanzl, L.H.; Rozenfeld, M.

    1981-01-01

    Fission track detectors were applied to a unique problem in neutron dosimetry. Measurements of neutron doses were required at locations within a tumor of 1 cm diameter implanted on the back of a mouse and surrounded by a square array of four 252 Cf medical sources. Measurements made in a tissue-equivalent mouse phantom showed that the neutron dose rate to the center of the tumor was 2.18 rads mg -1 h -1 +- 8.4%. The spatial variation of neutron dose to the tumor ranged from 1.88 to 2.55 rads mg -1 h -1 . These measurements agree with calculated values of neutron dose to those locations in the phantom. Fission track detectors have been found to be a reliable tool for neutron dosimetry for geometries in which one wishes to know neutron dose values which may vary considerably over distances of 1 cm or less

  18. Application of fission track detectors to californium-252 neutron dosimetry in tissue near the radiation source

    International Nuclear Information System (INIS)

    Oswald, R.A.; Lanzl, L.H.; Rozenfeld, M.

    1981-01-01

    Fission track detectors were applied to a unique problem in neutron dosimetry. Measurements of neutron doses were required at locations within a tumor of 1 cm diameter implanted on the back of a mouse and surrounded by a square array of four 252 Cf medical sources. Measurements made in a tissue-equivalent mouse phantom showed that the neutron dose rate to the center of the tumor was 2.18 rads micrograms-1 h-1 +/- 8.4%. The spatial variation of neutron dose to the tumor ranged from 1.88 to 2.55 rads micrograms-1 h-1. These measurements agree with calculated values of neutron dose to those locations in the phantom. Fission track detectors have been found to be a reliable tool for neutron dosimetry for geometries in which one wishes to know neutron dose values which may vary considerably over distances of 1 cm or less

  19. Neutron Protection Factor Determination and Validation for a Vehicle Surrogate Using a Californium Fission Source

    Science.gov (United States)

    2017-06-01

    study the laws governing shock wave propagation, and evaluate the suitability of military operations after being subjected to their use. During...14]. MCNP6.1 then outputs a dose spectrum, instead of the standard fluence spectrum created from the “ f4 ” tally [14]. In order to produce the dose...manually, an unmodified fluence tally ( f4 ) was exported externally to a spreadsheet. The energy bins were summed and grouped to mimic the energy bin

  20. Californium-252 neutron activation analysis of high-level processed nuclear tank waste

    International Nuclear Information System (INIS)

    Troyer, G.L.; Purcell, M.A.

    2000-01-01

    The basis for production assessment of the vitrification of Hanford nuclear fuel reprocessing wastes will be high-precision measurements of the elemental sodium content. However, the chemical analysis of both radioactive and nonradioactive components in nuclear waste can be challenged by high radiation dose rates. The dose rates compromise many analytical techniques as well as pose personnel dosimetry risks. In many cases, reduction of dose rates through dilution compromises the precision and sensitivity for certain key components. The use of neutron activation analysis (NAA) provides a method of analysis that avoids the need for dilutions or extensive sample preparation. These waste materials also contain trace quantities of fissionable isotopes, which, through neutron activation, can be estimated by delayed neutron counting of fissioned fragments

  1. Multiplicity and correlated energy of gamma rays emitted in the spontaneous fission of Californium-252

    International Nuclear Information System (INIS)

    Brunson, G.S. Jr.

    1982-06-01

    An array of eight high-speed plastic scintillation detectors has been used to infer a mathematical model for the emission multipliciy of prompt gammas in the spontaneous fission of 252 Cf. Exceptional time resolution and coincidence capability permitted the separation of gammas from fast neutrons over a flight path of approximately 10 cm. About 20 different distribution models were tested. The average energy of the prompt gammas is inversely related to the number emitted; however, this inverse relationship is not strong and the total gamma energy does increase with increasing gamma number. An extension of the experiment incorporated a lithium-drifted germanium gamma spectrometer that resolved nearly 100 discrete gammas associated with fission. Of these gammas, some were preferentially associated with fission in which few gammas were emitted. Certain others were more frequent when many gammas were emitted. Results are presented

  2. Use of californium-252 sources in Hungary for teaching and research

    International Nuclear Information System (INIS)

    Csikai, J.

    1976-01-01

    An activation facility was designed to accommodate up to 50 mg of 252 Cf; it contains at present a 500 μg source. The absolute values of thermal, epithermal and fast neutron fluxes were determined by the foil activation method using In, Dy, Au, Al and Fe detectors. Cross-sections averaged for unmoderated 252 Cf neutrons were determined for 22 different reactions for elements with atomic weights lying between A=27 and 204. The sensitivity for determination of Al, Ti, Cu, As, Sr, Mo, In, Cd, Ba, Au, Hg and Pb was calculated for NaI(Tl) and Ge(Li) detectors. Average (n,2n) cross-sections for 252 Cf spectrum were calculated for 49 nuclei lying between A=14 and 204. Angular distributions and cross-sections for the fragments from 252 Cf neutron-induced fission of 232 Th and 238 U were measured. Titanium in bauxite and manganese in aluminium alloys were determined with a 252 Cf source. The applicability of solid-state track detectors for neutron dosimetry, radiography and for the determination of fuel burn-up were investigated using 252 Cf neutron and fragment sources. Characteristics of a jumping spark counter for counting fission fragments were studied with 252 Cf sources. (author)

  3. Chromatographic cation exchange separation of decigram quantities of californium and other transplutonium elements

    Energy Technology Data Exchange (ETDEWEB)

    Benker, D.E.; Chattin, F.R.; Collins, E.D.; Knauer, J.B.; Orr, P.B.; Ross, R.G.; Wiggins, J.T.

    1980-01-01

    Decigram quantities of highly radioactive transplutonium elements are routinely partitioned at TRU by chromatographic elution from cation resin using AHIB eluent. By using two high-pressure ion exchange columns, a small one for the initial loading of the feed and a large one for the elution, batch runs containing up to 200 mg of /sup 252/Cf can be made in about 5 hours (2 hours to load the feed and 3 hours for the elution). The number of effluent product fractions and the amount of actinides that must be collected in intermediate fractions are minimized by monitoring response from a flow-through alpha-detector. This process has been reliable and relatively easy to operate, and will continue to be used for partitioning transplutonium elements at TRU.

  4. Determination of the average number of neutrons per fission event for californium-252

    International Nuclear Information System (INIS)

    Aleksandrov, B.M.; Belov, L.M.; Drapchinskij, L.V.

    1982-01-01

    By means of a separate determination of neutron yields and fission event rates, the value of #betta#-bar( 252 Cf) has been measured for a series of new high-purity sources. The improved quality of the source active layers has reduced the error in determining the fission rate to 0.35%. The value obtained for #betta#-bar( 252 Cf) is 3.747+-0.036. A description is given of the design and the parameters of a spherical manganese bath in which the work on refining the value of #betta#-bar( 252 Cf) will be continued. (author)

  5. Remarkably High Stability of Late Actinide Dioxide Cations: Extending Chemistry to Pentavalent Berkelium and Californium.

    Science.gov (United States)

    Dau, Phuong D; Vasiliu, Monica; Peterson, Kirk A; Dixon, David A; Gibson, John K

    2017-12-06

    Actinyl chemistry is extended beyond Cm to BkO 2 + and CfO 2 + through transfer of an O atom from NO 2 to BkO + or CfO + , establishing a surprisingly high lower limit of 73 kcal mol -1 for the dissociation energies, D[O-(BkO + )] and D[O-(CfO + )]. CCSD(T) computations are in accord with the observed reactions, and characterize the newly observed dioxide ions as linear pentavalent actinyls; these being the first Bk and Cf species with oxidation states above IV. Computations of actinide dioxide cations AnO 2 + for An=Pa to Lr reveal an unexpected minimum for D[O-(CmO + )]. For CmO 2 + , and AnO 2 + beyond EsO 2 + , the most stable structure has side-on bonded η 2 -(O 2 ), as An III peroxides for An=Cm and Lr, and as An II superoxides for An=Fm, Md, and No. It is predicted that the most stable structure of EsO 2 + is linear [O=Es V =O] + , einsteinyl, and that FmO 2 + and MdO 2 + , like CmO 2 + , also have actinyl(V) structures as local energy minima. The results expand actinide oxidation state chemistry, the realm of the distinctive actinyl moiety, and the non-periodic character towards the end of the periodic table. © 2017 Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

  6. Californium-252: isotope for modern radiotherapy of cervix, uterine and vaginal carcinomas

    International Nuclear Information System (INIS)

    Maruyama, J.; Beach, J.L.; Nagell, J.R. van

    1984-01-01

    Cf-252 is an isotope that can easily be afterloaded into available gynecological applicators and used for bulky cervix, uterus or vaginal cancer therapy. It is economical, time and cost effective in use, and can be applied to the therapy of many patients throughout the world. It is more effective for neutron therapy than machine fast neutron therapy and is the only form of neutron therapy producing consistent complication-free 5-year cure of advanced cancers currently available. Cf-252 is an isotope for modern gynecological tumor therapy for the future. Isodose curves for Cf-252 implants revealed dose distributions conforming well to tumor. (orig.) [de

  7. Testing of ENDF/B cross section data in the Californium-252 neutron benchmark field

    International Nuclear Information System (INIS)

    Mannhart, W.

    1979-01-01

    The fission neutron field of 252 Cf presently represents one of the most well-known neutron benchmark fields. For 13 neutron reactions which are of importance in reactor metrology, measurements of spectrum-averaged cross sections, [sigma], performed in this neutron field were compared with calculated average cross sections. This comparison allows one to draw conclusions as to the quality of different sigma(E) data taken from ENDF/B-IV, from ENDF/B-V, and from recent experiments and used in the calculation of average cross sections. The comparison includes an uncertainty analysis regarding the different uncertainty contributions of [sigma], of sigma(E), and of the spectral distribution of 252 Cf fission neutrons. Additionally, in a few examples, sensitivity studies were carried out. The sensitivity of the spectrum-averaged cross sections to individual characteristics of the sigma(E) data, such as normalization factors or shifts in the energy scale, was investigated. Similarly, the sensitivity of [sigma] to the spectral distribution of 252 Cf was determined. 4 figures, 2 tables

  8. Total neutron cross sections of berkelium-249 and californium-249 below 100 eV

    International Nuclear Information System (INIS)

    Benjamin, R.W.; Harvey, J.A.; Hill, N.W.; Pandey, M.S.; Carlton, R.F.

    1979-01-01

    The neutron total cross sections of 249 Bk and 249 Cf have been measured from 0.03 to 100 eV using the Oak Ridge Electron Linear Accelerator (ORELA) as a source of pulsed neutrons. The 1.6 mm dia. cylindrical transmission samples contained initially up to 5.3 mg of 98% 249 Bk and 2% 249 Cf: 4.5 years later, when the final measurements were made, the composition of the samples had become 2.5% 249 Bk, 96.9% 249 Cf, and 0.6% 245 Cm. Samples were cooled with liquid nitrogen to reduce Doppler broadening. Thirty-nine resonances were identified in 249 Bk and analyzed using a single-level Breit-Wigner formalism. Fifty-five resonances were identified in 249 Cf and analyzed using an R-matrix multilevel formalism. Fifty-five resonances were identified in 249 Cf and analyzed using an R-matrix multilevel formalism. The resonance parameters obtained have been used to determine the average level spacings and the s-wave neutron and fission strength functions. Where possible, bound-level parameters were derived to fit the thermal neutron total cross section data

  9. Prevalência e padrão de distribuição das doenças cerebrovasculares em 242 idosos, procedentes de um hospital geral, necropsiados em Belo Horizonte, Minas Gerais, no período de 1976 a 1997 Prevalence and types of cerebrovascular diseases in 242 hospitalized elderly patients, autopsied in Belo Horizonte, Minas Gerais, Brazil, from 1976 to 1997

    Directory of Open Access Journals (Sweden)

    José Eymard H. Pittella

    2002-03-01

    Full Text Available OBJETIVO: Descrever a prevalência e os tipos das doenças cerebrovasculares (DCVs em indivíduos idosos necropsiados. MÉTODO: Foram consultados os laudos neuropatológicos de 242 pacientes com idade igual ou superior a 61 anos, procedentes em sua maioria do Hospital das Clínicas da Universidade Federal de Minas Gerais, em Belo Horizonte, Minas Gerais, e necropsiados consecutivamente no período 1976 a 1997. RESULTADO: Os principais grupos de doenças do sistema nervoso central (SNC foram representados por DCVs (71,9%, infecções (12,4%, neoplasias (7,1%, traumatismos crânio-encefálicos (3,7%, doenças nutricionais (2,5% e doenças degenerativas (1,7%. As DCVs mais frequentes foram: aterosclerose (61,2%, doença cerebrovascular hipertensiva (25,6% e infarto cerebral (14,9%. Observou-se aumento da frequência e da gravidade da aterosclerose e da frequência da doença cerebrovascular hipertensiva com o avançar da idade. Houve associação significativa entre doença cerebrovascular hipertensiva e aterosclerose. As DCVs foram clinicamente sintomáticas e as responsáveis diretas pelo óbito em 42,7% e 17,3% dos pacientes, respectivamente. CONCLUSÃO: As DCVs constituíram o principal grupo de doenças do SNC no idoso. A aterosclerose e a doença cerebrovascular hipertensiva foram as principais doenças deste grupo, notando-se aumento de sua frequência com o avançar da idade e associação significativa entre ambas.OBJECTIVE: To describe the prevalence and the types of cerebrovascular diseases (CVDs in autopsied elderly individuals. METHOD: Consecutive clinical charts and neuropathological reports of 242 patients aged 61 years or older were reviewed. The patients died in Hospital das Clínicas, Federal University of Minas Gerais, in Belo Horizonte, Minas Gerais, Brazil, from 1976 to 1997. RESULTS: The prevalent diseases of the central nervous system (CNS found in decreasing order were: CVDs (71.9%, infections (12.4%, neoplasms (7.1%, head

  10. 48 CFR 242.002 - Interagency agreements.

    Science.gov (United States)

    2010-10-01

    ... administration services on their direct purchases from U.S. producers. Direct purchase is the purchase of defense... organizations send their requests for contract administration services to the DoD Central Control Point (CCP) at...

  11. Publications | Page 242 | IDRC - International Development ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    IDRC works with developing-country researchers and institutions to build local capacity through funding, knowledge sharing, and training. Through books, articles, research publications, and studies, we aim to widen the impact of our investment and advance development research. We share the results of our funded ...

  12. 24 CFR 242.16 - Applications.

    Science.gov (United States)

    2010-04-01

    ... evaluate any other factors, including but not limited to risk to the Insurance Fund, that should be... relationships that help optimize financial, clinical, and operational performance; (vii) Management's demonstrated ability to operate effectively and efficiently, and to develop effective strategies for addressing...

  13. Publications | Page 242 | IDRC - International Development ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Simple human vulnerability index to climate change hazards for Pakistan (open access) ... Understanding remittances in Ghana : analysing poverty reducing effect of ... Risk communication guide for climate change practitioners in Africa ...

  14. 32 CFR 242.5 - Admission procedures.

    Science.gov (United States)

    2010-07-01

    ... qualified applicants, based on aptitude, intelligence, maturity, personality, emotional stability, diligence, stamina, enthusiasm, motivation, and other relevant factors, consistent with the practices followed by...

  15. 17 CFR 242.500 - Definitions.

    Science.gov (United States)

    2010-04-01

    .... market is not the principal trading market. Public appearance means any participation by a research... activities of research analysts or the content of research reports; and (ii) If the broker or dealer... broker or dealer from influencing the activities of research analysts and the content of research reports...

  16. 24 CFR 242.54 - Nondiscrimination.

    Science.gov (United States)

    2010-04-01

    ... and sex discrimination do not affect the eligibility of hospitals for women and children. ... financed with mortgages insured under this part must be made available without discrimination as to race...

  17. Energy Magazine. V. 24(2)

    International Nuclear Information System (INIS)

    1999-01-01

    In this issue, there are two articles related to the thematic of the Conference on energy efficiency and renewable resources, Eurolac 2000. Some examples of actions for energy conservation and for improvement of the regional energetic efficiency are described

  18. 24 CFR 242.77 - Liens.

    Science.gov (United States)

    2010-04-01

    ... liens other than the insured mortgage, except that the property may be subject to a lien as provided by... superior lien on accounts receivable as approved by HUD as collateral for a line of credit or other...

  19. 24 CFR 242.1 - Definitions.

    Science.gov (United States)

    2010-04-01

    ... premiums (MIPs), taxes, ground rents, property insurance premiums, and assessments, when funds available... revenues over expenses (not-for-profit) or net income (for-profit) plus interest expense plus depreciation.... Mortgage Reserve Fund means a trust account, or an account held by the mortgagee, for and on behalf of the...

  20. 24 CFR 242.66 - Affiliate transactions.

    Science.gov (United States)

    2010-04-01

    ... URBAN DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES MORTGAGE INSURANCE FOR HOSPITALS Regulatory Agreement, Accounting and Reporting, and Financial Requirements...

  1. 32 CFR 242.3 - Definitions.

    Science.gov (United States)

    2010-07-01

    ... ADMISSION POLICIES AND PROCEDURES FOR THE SCHOOL OF MEDICINE, UNIFORMED SERVICES UNIVERSITY OF THE HEALTH... Health Service. (b) Military Personnel. For purposes of this Directive, “Military Personnel” shall... or more in any of the three Military Departments. (2) Reserve component personnel enrolled in the...

  2. 36 CFR 242.4 - Definitions.

    Science.gov (United States)

    2010-07-01

    ... Administrative Code. Barter means the exchange of fish or wildlife or their parts taken for subsistence uses; for... boundaries of any unit of the National Park System, National Wildlife Refuge System, National Wild and Scenic Rivers Systems, National Forest Monument, National Recreation Area, National Conservation Area, new...

  3. 19 CFR 10.242 - Definitions.

    Science.gov (United States)

    2010-04-01

    ... “beneficiary country” as defined in § 10.202(a) for purposes of the ATPA which the President also has... articles under 19 U.S.C. 3203(b)(3) and which has been the subject of a determination by the President or... entered into by the United States, Canada, and Mexico on December 17, 1992. Preferential treatment...

  4. 17 CFR 242.402 - General provisions.

    Science.gov (United States)

    2010-04-01

    ... conduct all financial relations with respect to such security future and related positions in accordance... customer in a futures account shall record and conduct all financial relations with respect to such... authorities of which the security futures intermediary is a member. (b) Separation and consolidation of...

  5. 48 CFR 5252.242-9000 - Refunds.

    Science.gov (United States)

    2010-10-01

    ..., accuracy and completeness of, cost or pricing data applicable to the item. (End of clause) ... on price was reached and the contract price. Refunds will not be made to recoup the amount of cost... established catalog or market price, plus the value of any unique requirements, including delivery terms...

  6. 32 CFR 242.4 - Policies.

    Science.gov (United States)

    2010-07-01

    ... section on obligated service requirements.) (b) In making admissions decisions, the School will adhere to... entrance shall be judged strictly on merit, in terms of demonstrated aptitude, motivation, and potential... the extent possible in making Service assignments. However, to insure that the makeup of each entering...

  7. 12 CFR 24.2 - Definitions.

    Science.gov (United States)

    2010-01-01

    ... targeted by a governmental entity for redevelopment, or would receive consideration as “qualified... nonbank community development corporations; (3) CDFI Fund-certified Community Development Financial... trusts; (7) Business development companies; (8) Community development closed-end mutual funds; (9) Non...

  8. 48 CFR 242.7502 - Procedures.

    Science.gov (United States)

    2010-10-01

    ... OF DEFENSE CONTRACT MANAGEMENT CONTRACT ADMINISTRATION AND AUDIT SERVICES Contractor Accounting... significant accounting system or related internal control deficiencies, the ACO will— (1) Provide a copy of... percentage of progress payments or reimbursement of costs proportionate to the estimated cost risk to the...

  9. 48 CFR 242.771-3 - Responsibilities.

    Science.gov (United States)

    2010-10-01

    ....771-3 Responsibilities. (a) The cognizant administrative contracting officer (ACO) or corporate ACO... (OUSD(AT&L)DDR&E), is responsible for establishing a regular method for communication— (1) From DoD to...

  10. 24 CFR 242.10 - Eligible mortgagors.

    Science.gov (United States)

    2010-04-01

    ... or profit-motivated mortgagors may include for-profit corporations, limited partnerships, and limited liability corporations and companies, but may not include natural persons, joint ventures, and general partnerships. Any proposed mortgagor must demonstrate that it has a continuity of organization commensurate...

  11. 17 CFR 242.401 - Definitions.

    Science.gov (United States)

    2010-04-01

    ... security other than a security future, the most recent closing sale price of the security, as shown by any regularly published reporting or quotation service. If there is no recent closing sale price, the security...: (A) If the instrument underlying such security future is a stock, theproduct of the daily settlement...

  12. 48 CFR 242.7501 - Policy.

    Science.gov (United States)

    2010-10-01

    ... DEFENSE CONTRACT MANAGEMENT CONTRACT ADMINISTRATION AND AUDIT SERVICES Contractor Accounting Systems and... provide reasonable assurance that— (a) Applicable laws and regulations are complied with; (b) The...

  13. Simultaneous measurement of {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, and {sup 242}Pu by high resolution inductively coupled plasma mass spectrometer (HR ICP-MS) in marine sediments; Mesure des isotopes du plutonium des sediments marins par spectrometrie de masse a plasma couple inductivement haute resolution (HR ICP-MS)

    Energy Technology Data Exchange (ETDEWEB)

    Bruneau, F

    1999-07-01

    Transuranics elements are of particular interest in radioecological studies because of their radiotoxicity and their potential use to decipher source fingerprints and transport processes. The simultaneous measurement of {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, and {sup 242}Pu in environmental samples requires a specific chemical procedure. This work deals with an analytical procedure which yields a very high grade of purification of Pu suitable for ultra low level detection by HR ICP-MS, from marine sediments. After the elimination of major elements (Fe, Al, Mg...) by a first chromatographic separation, a new device of purification by solvent extraction and concentration by a second chromatographic separation is used to obtain a concentrated and high purified solution of plutonium. The chemical procedure have been validated on IAEA certified sediment samples and on sediment samples collected in the roads of Cherbourg which had been previously analysed by other techniques (a spectrometry and thermo-ionisation mass spectrometer). (author)

  14. Oxidation-reduction properties of americium, curium, berkelium, californium, einsteinium and fermium, and thermodynamic consequences for the 5f series

    International Nuclear Information System (INIS)

    Samhoun, K.

    1976-01-01

    The amalgamation of 5f elements from Am to Fm has been studied by using 241 Am, 244 Cm, 249 Bk, 249 Cf, 252 Cf, 253 Es, 254 Es, 252 Fm and 255 Fm with two electrochemical methods, radiocoulometry and radiopolarography, perfectly adapted to investigate extremely diluted solutions when the concentration of electroactive species is as low as 10 -16 M. The theory of radiocoulometry has been developed in the general cases of reversible and irreversible electrode process. It has been used to interpret the experimental data on the kinetic curves of amalgamation, and to estimate the standard rate constant of the electrode process in complexing medium (citric). On the other hand the radiopolarographic method has been applied to study the mechanism of reduction at the dropping mercury electrode of cations M 3+ in aqueous medium to the metal M with formation of amalgam. The results are exploited into two directions: 1- Acquisition of some data concerning the oxidation-reduction properties of elements from Am to Fm. Therefore the standard electrode E 0 [M(III-0)] potentials for Bk, Cf and Es, and the standard electrode E 0 [M(II-0)] potential for Fm are estimated and the relative stability of each oxidation state (from II to VII) of 5f elements is discussed; 2- Acquisition of unknown thermodynamic data on transcalifornium elements. Correlations between 4f and 5f elements are precised and some divergences appear for the second half of 4f and 5f series (i.e. for 65 [fr

  15. Inverse gamma ray dose rate effect in californium-252 RBE experiment with human T-1 cells irradiated in vitro

    International Nuclear Information System (INIS)

    Todd, P.; Feola, J.M.

    1986-01-01

    Metabolically deoxygenated suspensions of human T-1 cells were used to determine the RBE in hypoxia of low dose rate (LDR) Cf-252 radiation compared to LDR gamma radiation. Based upon the initial portion of the survival curves the RBE was 5.0 ± 1.0 for all components of the Cf-252 radiation and 7.1 ± 1.7 for the neutrons alone. An inverse dose rate effect was observed for LDR gamma radiation in which greater cell sensitivity was observed at lower dose rates and longer irradiation periods. It was demonstrated that there was little or no sublethal damage repair or cell progression during LDR at 21 deg C, and the observed decrease in cell survival probability with increasing irradiation time at a given dose was attributable to reoxygenation of the cell suspensions during the course of LDR exposures. (Auth.)

  16. In situ x-ray fluorescence and californium-252 neutron activation analysis for marine and terrestrial mineral exploration

    International Nuclear Information System (INIS)

    Wogman, N.A.

    1976-12-01

    Instrumentation has been designed for in situ analysis of marine and terrestrial minerals using the techniques of x-ray fluorescence and neutron activation analysis. The energy-dispersive x-ray fluorescence analyzer allows more than 20 elements to be quantitatively measured at the 10 ppM level in water depths to 300 m. The analyzer consists of a solid cryogen-cooled Si(Li) detector, a 50 mCi 109 Cd or 57 Co excitation source, and an analyzer-computer system for data storage and manipulation. The neutron activation analysis, which is designed to measure up to 30 elements at parts per hundred to ppM levels, utilizes the man-made element 252 Cf as its neutron activation source. The resulting radioelements which emit characteristic gamma radiation are then analyzed in situ during 2- to 200-s counting intervals with Ge(Li) or NaI(T1) detector systems. An extension of this latter technique, which uses a 252 Cf- 235 U fueled subcritical multiplier, is also being studied. The subcritical facility allows the neutrons from the 252 Cf source to be multiplied, thus providing greater neutron flux. Details of these in situ analysis systems, actual in situ spectra, and recorded data are discussed with respect to the detection of minerals at their varying concentration levels. The system response of each illustrates its usefulness for various rapid environmental mineral exploration studies. These techniques can be utilized on terrestrial surfaces and marine or fresh water sediments. 5 figures, 2 tables

  17. The fission cross sections of /sup 230/Th, /sup 232/Th, /sup 233/U, /sup 234/U, /sup 236/U, /sup 238/U, /sup 237/Np, /sup 239/Pu and /sup 242/Pu relative /sup 235/U at 14. 74 MeV neutron energy

    Energy Technology Data Exchange (ETDEWEB)

    Meadows, J.W.

    1986-12-01

    The measurement of the fission cross section ratios of nine isotopes relative to /sup 235/U at an average neutron energy of 14.74 MeV is described with particular attention to the determination of corrections and to sources of error. The results are compared to ENDF/B-V and to other measurements of the past decade. The ratio of the neutron induced fission cross section for these isotopes to the fission cross section for /sup 235/U are: /sup 230/Th - 0.290 +- 1.9%; /sup 232/Th - 0.191 +- 1.9%; /sup 233/U - 1.132 +- 0.7%; /sup 234/U - 0.998 +- 1.0%; /sup 236/U - 0.791 +- 1.1%; /sup 238/U - 0.587 +- 1.1%; /sup 237/Np - 1.060 +- 1.4%; /sup 239/Pu - 1.152 +- 1.1%; /sup 242/Pu - 0.967 +- 1.0%. 40 refs., 11 tabs., 9 figs.

  18. 17 CFR 242.600 - NMS security designation and definitions.

    Science.gov (United States)

    2010-04-01

    ... quotation has been superseded or supplemented by the display of a new transaction report, last sale data, or... association. (36) Make publicly available means posting on an Internet Web site that is free and readily... contracts in an options class that have the same unit of trade, expiration date, and exercise price, and...

  19. 48 CFR 242.202 - Assignment of contract administration.

    Science.gov (United States)

    2010-10-01

    ..., charting, and geodesy services; (F) Base, post, camp, and station purchases; (G) Operation or maintenance of, or installation of equipment at, radar or communication network sites; (H) Communications..., post, camp, and station contracts on a military installation are normally the responsibility of the...

  20. 48 CFR 1552.242-72 - Financial administrative contracting officer.

    Science.gov (United States)

    2010-10-01

    ... Administrative Contracting Officer (FACO) is responsible for performing certain post-award functions related to the financial aspects of this contract when the EPA is the cognizant federal agency. These functions...) Negotiate advance agreements applicable to treatment of costs and to Independent Research & Development/Bid...

  1. 17 CFR 242.611 - Order protection rule.

    Science.gov (United States)

    2010-04-01

    ... transaction that constituted the trade-through was not a “regular way” contract. (3) The transaction that... traded through had displayed, within one second prior to execution of the transaction that constituted the trade-through, a best bid or best offer, as applicable, for the NMS stock with a price that was...

  2. 48 CFR 652.242-72 - Shipping Instructions.

    Science.gov (United States)

    2010-10-01

    ...) Each packing box shall be of solid construction in accordance with best commercial practices and.../3 of the width of the piece of lumber. Box shall be constructed with three-way corners and diagonal... Contractor shall place the fourth copy of the packing list in packing case number one, which shall be marked...

  3. Dicty_cDB: AFH242 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available CA sequence update 2001. 6. 2 Translated Amino Acid sequence claywvyntvysytsl*rii...r*snsynirslnykwss*nwc*sleelktslpisnklqs Frame C: claywvyntvysytsl*riikknkkkek*vmfmill*ldqvfqv*cvvin*krmdikf*

  4. All projects related to | Page 242 | IDRC - International Development ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Topic: ENTREPRENEURSHIP, SOCIAL ASPECTS, BUSINESS SERVICES, INNOVATIONS, Capacity building, BUSINESS CREATION. Region: Middle East, North of Sahara, South of Sahara, ... Raising Tobacco Taxes in Selected Countries of Central America. Project. Expert advice and evidence-based research will guide ...

  5. 48 CFR 752.242-70 - Periodic progress reports.

    Science.gov (United States)

    2010-10-01

    ... interpreted as “task order” or “delivery order” when this clause is used in an indefinite-delivery contract... may be used by USAID personnel or their authorized representatives when evaluating the contractor's... contracting officer may withhold from payment an amount not to exceed US$25,000 (or local currency equivalent...

  6. 36 CFR 242.3 - Applicability and scope.

    Science.gov (United States)

    2010-07-01

    ... and the Yukon Territory; Canada, and extending westerly, along the line of extreme low water across... the western bank of the Colville River following the highest highwater mark westerly, extending across... together with the adjacent waters of the Bering Sea extending, for Federal Subsistence Management purposes...

  7. 36 CFR 242.26 - Subsistence taking of wildlife.

    Science.gov (United States)

    2010-07-01

    ...-driven boat when the boat's progress from the motor's power has not ceased; (5) Using a motorized vehicle... collars. If you take an animal that has been marked or tagged for scientific studies, you must, within a... Unit 1B—that portion on the Cleveland Peninsula south of the divide between Yes Bay and Santa Anna...

  8. 7 CFR 2.42 - Administrator, Farm Service Agency.

    Science.gov (United States)

    2010-01-01

    ... release of a hazardous substance, pollutant, or contaminant into the environment; (ii) Sections 104(e)-(h... Water Pollution Prevention and Control Act, as amended (33 U.S.C. 1251 et seq.); (iii) Safe Drinking... coordinate land retirement and agricultural working land conservation programs under section 2005 (16 U.S.C...

  9. 36 CFR 242.9 - Information collection requirements.

    Science.gov (United States)

    2010-07-01

    ... the Paperwork Reduction Act. The burden in this situation is negligible, and information gained from... estimate to: Information Collection Officer, U.S. Fish and Wildlife Service, 1849 C Street, N.W., MS 222...

  10. 48 CFR 242.302 - Contract administration functions.

    Science.gov (United States)

    2010-10-01

    ...) Contractor estimating systems (see FAR 15.407-5); and (B) Contractor material management and accounting... report identifying significant accounting system or related internal control deficiencies. (9) For... SYSTEM, DEPARTMENT OF DEFENSE CONTRACT MANAGEMENT CONTRACT ADMINISTRATION AND AUDIT SERVICES Contract...

  11. 48 CFR 3452.242-72 - Withholding of contract payments.

    Science.gov (United States)

    2010-10-01

    ... clause in all solicitations and contacts other than purchase orders: Withholding of Contract Payments... shall promptly notify the contractor of its intention to withhold payment of any invoice or voucher...

  12. 48 CFR 1852.242-70 - Technical direction.

    Science.gov (United States)

    2010-10-01

    ... Direction (SEP 1993) (a) Performance of the work under this contract is subject to the written technical... the Contracting Officer in writing in accordance with NASA FAR Supplement 1842.270. “Technical... in writing by the COTR. (d) The Contractor shall proceed promptly with the performance of technical...

  13. Radiative capture on $^{242}$Pu for MOX fuel reactors

    CERN Multimedia

    The use of MOX fuel (mixed-oxide fuel made of UO$_{2}$ and PuO$_{2}$) in nuclear reactors allows substituting a large fraction of the enriched Uranium by Plutonium reprocessed from spent fuel. Indeed around 66% of the plutonium from spent fuel is made of $^{239}$Pu and $^{241}$Pu, which are fissile in thermal reactors. A typical reactor of this type uses a fuel with 7% reprocessed Pu and 93% depleted U, thus profiting from both the spent fuel and the remaining $^{238}$U following the $^{235}$U enrichment. With the use of such new fuel compositions rich in Pu the better knowledge of the capture and fission cross sections of the Pu isotopes becomes very important. This is clearly stated in the recent OECD NEA’s “High Priority Request List” and in the WPEC-26 “Uncertainty and target accuracy assessment for innovative systems using recent covariance data evaluations” report. In particular, a new series of cross section evaluations have been recently carried out jointly by the European (JEFF) and United ...

  14. 24 CFR 242.63 - Additional indebtedness and leasing.

    Science.gov (United States)

    2010-04-01

    ... AUTHORITIES MORTGAGE INSURANCE FOR HOSPITALS Regulatory Agreement, Accounting and Reporting, and Financial... Development (Continued) OFFICE OF ASSISTANT SECRETARY FOR HOUSING-FEDERAL HOUSING COMMISSIONER, DEPARTMENT OF... derivative-type transactions, except in conformance with policies and procedures established by HUD. ...

  15. Facility effluent monitoring plan for 242-A evaporator facility

    International Nuclear Information System (INIS)

    Crummel, G.M.; Gustavson, R.D.

    1995-02-01

    A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, as a minimum, every three years

  16. Facility effluent monitoring plan for 242-A Evaporator facility

    International Nuclear Information System (INIS)

    Crummel, G.M.; Gustavson, R.D.

    1993-03-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility effluent Monitoring Plans, WHC-EP-0438-1**. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

  17. 24 CFR 242.65 - Distribution of assets.

    Science.gov (United States)

    2010-04-01

    ... URBAN DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES MORTGAGE INSURANCE FOR HOSPITALS Regulatory Agreement, Accounting and Reporting, and Financial Requirements...

  18. 24 CFR 242.59 - Inspection of facilities by Commissioner.

    Science.gov (United States)

    2010-04-01

    ... HOUSING AND URBAN DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES MORTGAGE INSURANCE FOR HOSPITALS Regulatory Agreement, Accounting and Reporting, and Financial...

  19. 24 CFR 242.64 - Current and future property.

    Science.gov (United States)

    2010-04-01

    ... URBAN DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES MORTGAGE INSURANCE FOR HOSPITALS Regulatory Agreement, Accounting and Reporting, and Financial Requirements...

  20. 24 CFR 242.57 - Maintenance of hospital facility.

    Science.gov (United States)

    2010-04-01

    ... HOUSING AND URBAN DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES MORTGAGE INSURANCE FOR HOSPITALS Regulatory Agreement, Accounting and Reporting, and Financial...

  1. 50 CFR 216.242 - Permissible methods of taking.

    Science.gov (United States)

    2010-10-01

    ... percent of the number of takes indicated below): (i) Mysticetes: (A) North Atlantic right whale (Eubalaena...) Sperm whales (Physeter macrocephalus)—48790 (an average of 9758 annually). (B) Pygmy or dwarf sperm...

  2. 242 The Status of Material Resources for Effective Teaching of ...

    African Journals Online (AJOL)

    User

    2011-07-21

    Jul 21, 2011 ... Stephen, Utib-Abasi Scepter - Department of Science Education, University of Uyo, Uyo, Akwa Ibom ... (primary, secondary and tertiary). At the ... effective teaching and learning of physics, in our secondary schools therefore ...

  3. 17 CFR 242.103 - Nasdaq passive market making.

    Science.gov (United States)

    2010-04-01

    ... paragraph (b)(2) of this section. (4) Limitation on displayed size. At all times, the passive market maker's... may display a bid size of 100 shares. (5) Identification of a passive market making bid. The bid... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Nasdaq passive market making...

  4. 40 CFR 180.242 - Thiabendazole; tolerances for residues.

    Science.gov (United States)

    2010-07-01

    ... Fruit, citrus, group 10, postharvest 10.0 None Fruit, pome, group 11, postharvest 5.0 None Mango 10.0... Strawberry1 5.0 None Sweet potato (postharvest to sweet potato intended only for use as seed) 0.05 None Wheat... connection with use of the pesticide under section 18 emergency exemptions granted by EPA. The tolerances are...

  5. 36 CFR 242.28 - Subsistence taking of shellfish.

    Science.gov (United States)

    2010-07-01

    ... from buying or selling subsistence-taken shellfish, their parts, or their eggs, unless otherwise... currently identified under Federal subsistence management jurisdiction. (3) Cook Inlet Area. (i) You may...

  6. 36 CFR 242.27 - Subsistence taking of fish.

    Science.gov (United States)

    2010-07-01

    ... not possess, transport, give, receive, or barter subsistence-taken fish or their parts which have been... Kitoi Creek; (F) All fresh water systems of Afognak Island. (iv) You must have a subsistence fishing...

  7. 40 CFR 61.242-2 - Standards: Pumps.

    Science.gov (United States)

    2010-07-01

    ... pressure that is at all times greater than the pump stuffing box pressure; or (ii) Equipped with a barrier... system that purges the barrier fluid into a process stream with zero VHAP emissions to atmosphere. (2...

  8. 40 CFR 61.242-3 - Standards: Compressors.

    Science.gov (United States)

    2010-07-01

    ... at a pressure that is greater than the compressor stuffing box pressure; or (2) Equipped with a...) Equipped with a system that purges the barrier fluid into a process stream with zero VHAP emissions to...

  9. 36 CFR 242.10 - Federal Subsistence Board.

    Science.gov (United States)

    2010-07-01

    ... consultants to the Board. (d) Powers and duties. (1) The Board shall meet at least twice per year and at such... for the decision, in writing, in a timely fashion. (2) The Board shall provide available and...

  10. 2.4.2. Water processing of cake

    International Nuclear Information System (INIS)

    Nazarov, Sh.B.; Safiev, Kh.S.; Mirsaidov, U.

    2008-01-01

    The cake water processing carried out with the purpose of extraction ofalkali components, in particular calcium chlorides and sodium, formed atbaking of raw materials with calcium chloride and by acid processingextracted the aluminium and iron compounds

  11. 48 CFR 1252.242-71 - Contractor testimony.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Contractor testimony. 1252... Contractor testimony. As prescribed in (TAR) 48 CFR 1242.7000(b), insert the following clause: Contractor Testimony (OCT 1994) All requests for the testimony of the Contractor or its employees, and any intention to...

  12. 47 CFR 24.2 - Other applicable rule parts.

    Science.gov (United States)

    2010-10-01

    ... procedures concerning the marketing and importation of radio frequency devices, and for obtaining equipment... conditions relating to the marketing of part 15 devices. Unlicensed PCS devices operate under subpart D of... towers. (g) Part 20 of this chapter governs commercial mobile radio services. (h) Part 21. This part...

  13. 36 CFR 242.20 - Request for reconsideration.

    Science.gov (United States)

    2010-07-01

    ... statement of the facts of the dispute, the issues raised by the request, and specific references to any law... implement a final decision on a request for reconsideration after compliance with 5 U.S.C. 551-559 (APA). (g...

  14. 48 CFR 352.242-71 - Tobacco-free facilities.

    Science.gov (United States)

    2010-10-01

    ... personal or company vehicles operated by Contractor employees while on an HHS property. This policy also... HHS policy will apply to the maximum area permitted by both law and current lease agreements. The Contractor shall ensure that each of its employees, and any subcontractor staff, is made aware of, understand...

  15. 49 CFR 24.2 - Definitions and acronyms.

    Science.gov (United States)

    2010-10-01

    ... development with normal site improvements, including customary landscaping. The site need not include special... displacing Agency shall follow the requirements for separate bedrooms for children of the opposite gender... assistance provided under the American Dream Downpayment Initiative (ADDI) authorized by section 102 of the...

  16. Dicty_cDB: VHM242 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available Homo sapiens full open reading fra... 74 3e-12 AF134593_1( AF134593 |pid:none) Homo sapiens L-pipecolic aci...( BC114006 |pid:none) Bos taurus L-pipecolic acid oxidas... 74 4e-12 protein upda

  17. 17 CFR 242.101 - Activities by distribution participants.

    Science.gov (United States)

    2010-04-01

    ... (CONTINUED) REGULATIONS M, SHO, ATS, AC, AND NMS AND CUSTOMER MARGIN REQUIREMENTS FOR SECURITY FUTURES... quotation system or electronic communications network; or (6) Basket transactions. (i) Bids or purchases, in... to such a basket in the ordinary course of business as a result of a change in the composition of a...

  18. 1935 15' Quad #242 Aerial Photo Mosaic Index

    Data.gov (United States)

    Earth Data Analysis Center, University of New Mexico — Aerial Photo Reference Mosaics contain aerial photographs that are retrievable on a frame by frame basis. The inventory contains imagery from various sources that...

  19. 17 CFR 242.100 - Preliminary note; definitions.

    Science.gov (United States)

    2010-04-01

    ... with the distribution participant, issuer, or selling security holder that direct, effect, or recommend... course of its business. Distribution means an offering of securities, whether or not subject to... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Preliminary note; definitions...

  20. 48 CFR 3452.242-70 - Litigation and claims.

    Science.gov (United States)

    2010-10-01

    ... proceed with the defense of the action in good faith. (e) To the extent not in conflict with any... compensated by insurance that was required by law, regulation, contract clause, or other written direction of... ACQUISITION REGULATION CLAUSES AND FORMS SOLICITATION PROVISIONS AND CONTRACT CLAUSES Texts of Provisions and...

  1. 24 CFR 242.45 - Early commencement of work.

    Science.gov (United States)

    2010-04-01

    ... insurance and is to be accomplished at the sole risk of the mortgagor. (b) Construction completed prior to... to the issuance of a commitment or denial by HUD, the hospital and lender may request for good cause... hospital and the lender to be approved. Such work may be eligible to be financed with insured mortgage...

  2. 36 CFR 242.24 - Customary and traditional use determinations.

    Science.gov (United States)

    2010-07-01

    ... (mileposts 25-46), Slana, Tazlina, Tok Cutoff Road (mileposts 79-110), Tonsina, and Units 11. Unit 11, north..., Mentasta Lake, Nabesna Road (mileposts 25-46), Slana, Tazlina, Tok Cutoff Road (mileposts 79-110), Tonsina... the Tok Cutoff—Milepost 79-110 (Mentasta Pass), residents along the Nabesna Road—Milepost 0-46...

  3. [An improved method of preparing protein and peptide probes in mass spectrometry with ionization of division fragments by californium-252 (TOF-PDMS)].

    Science.gov (United States)

    Chivanov, V D; Zubarev, R A; Aksenov, S A; Bordunova, O G; Eremenko, V I; Kabanets, V M; Tatarinova, V I; Mishnev, A K; Kuraev, V V; Knysh, A N; Eremenko, I A

    1996-08-01

    The addition of organic acids (picric, oxalic, citric, or tartaric) to peptide and protein samples was found to significantly increase the yield of their quasi-molecular ions (QMI) in time-of-flight 252Cf plasma desorption mass spectrometry. The yield of the ions depended on the pKa of the acid added.

  4. The development and medical applications of a simple facility for partial body in vivo neutron activation analysis using californium-252 sources

    International Nuclear Information System (INIS)

    Boddy, K.

    1978-11-01

    A simple and cheap facility for partial body neutron activation analysis has been designed, based on the use of two 100 μg 252 Cf neutron sources. The results reported show that calcium can be measured in parts of the body such as the tibia with a precision as good as +- 1.6 % for a radiation dose of 2 rem. The uniformity of the thermal neutron flux density is better than +- 3 % over 10 cm. Some applications of this irradiation facility for studies of trace elements, in particular cadmium in liver and aluminium in liver or brain, have also been explored. However, the sensitivity attainable is not yet sufficient for the study of normal levels, but could be of interest in toxicological investigations

  5. Radiological Characterization Technical Report on Californium-252 Sealed Source Transuranic Debris Waste for the Off-Site Source Recovery Project at Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Feldman, Alexander [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-04-24

    This document describes the development and approach for the radiological characterization of Cf-252 sealed sources for shipment to the Waste Isolation Pilot Plant. The report combines information on the nuclear material content of each individual source (mass or activity and date of manufacture) with information and data on the radionuclide distributions within the originating nuclear material. This approach allows for complete and accurate characterization of the waste container without the need to take additional measurements. The radionuclide uncertainties, developed from acceptable knowledge (AK) information regarding the source material, are applied to the summed activities in the drum. The AK information used in the characterization of Cf-252 sealed sources has been qualified by the peer review process, which has been reviewed and accepted by the Environmental Protection Agency.

  6. Calculation of neutron and gamma-ray energy spectra in liquid air and liquid nitrogen due to 14-MeV neutron and californium-252 sources

    International Nuclear Information System (INIS)

    Straker, E.A.; Gritzner, M.L.; Harris, L. Jr.

    1978-01-01

    Calculations of neutron and gamma-ray fluences from 14-MeV neutron and 252 Cf sources in liquid air and liquid nitrogen have been performed. These calculations were made specifically for comparison with experimental data measured at Stohl, Federal Republic of Germany. The discrete-ordinates method was utilized with neutron and gamma-ray cross sections from ENDF/B-IV. One-dimensional calculational models were developed for the sources and tank. Limited comparisons are made with experimental data

  7. Measurement and model description of differential neutron spectra of the californium 252 spontaneous fission depending on THETA, Msub(T), Esub(kin sum)

    International Nuclear Information System (INIS)

    Vasil'ev, Yu.A.; Sidorov, L.V.; Vasil'eva, N.K.; Barashkov, Yu.A.; Golovanov, O.A.; Kopalkin, N.V.; Nemudrov, N.I.; Surin, V.M.; Khachaturov, Yu.F.

    1984-01-01

    The results of the 4π-spectrometer mesurement of the neutron spectra in the 26-154 deg angle range for seven groups of fragments with different masses and total kinetic energies are given. Experimental spectra have been analyzed for consistency with the evaporation model of neutrons from moving fragments. The results of an analysis of differential neutron spectra shows that the main reason of the ''yearly'' neutron emission is a neutron evaporation from fragments with large excitation energy and from fragments with neutron number N>82 during the time as compared with the time of fragment acceleration

  8. Efficacy of brachytherapy with californium-252 neutrons versus cesium-137 photons for eradication of bulky localized cervical cancer: single-institution study

    International Nuclear Information System (INIS)

    Maruyama, Y.; van Nagell, J.R.; Yoneda, J.; Donaldson, E.; Gallion, H.; Higgins, R.; Powell, D.; Turner, C.; Kryscio, R.

    1988-01-01

    A fast-neutron-emitting radioisotope, 252 Cf, is being tested in clinical trials of neutron brachytherapy for cervical cancer. The efficacy for histological eradication of bulky stage IB cervical tumors (mean diameter, approximately 6 cm) using combined radiation and surgery was studied in 65 patients treated with 137 Cs or 252 Cf before surgery during 1983-1986. Forty-four patients were treated with 137 Cs and 21 were treated with 252 Cf at equivalent doses of radiation. Fifteen of the 44 specimens (34%) were positive after 137Cs therapy. Only one of the 21 specimens was positive after 252 Cf therapy (P = .025), and that patient was treated in a delayed schedule 21 days after the start of external-beam irradiation rather than early in the course. 252 Cf therapy required a much lower radiation dose and shorter treatment time. The study compared tumor destruction of an identically staged human cervical tumor in situ by direct histological means, using 252 Cf neutron therapy or conventional photon therapy at an identical and equivalent dose adjusted by a relative biological effectiveness of 6.0 for 252 Cf

  9. Accurate determination of Curium and Californium isotopic ratios by inductively coupled plasma quadrupole mass spectrometry (ICP-QMS) in 248Cm samples for transmutation studies

    Energy Technology Data Exchange (ETDEWEB)

    Gourgiotis, A.; Isnard, H.; Aubert, M.; Dupont, E.; AlMahamid, I.; Cassette, P.; Panebianco, S.; Letourneau, A.; Chartier, F.; Tian, G.; Rao, L.; Lukens, W.

    2011-02-01

    The French Atomic Energy Commission has carried out several experiments including the mini-INCA (INcineration of Actinides) project for the study of minor-actinide transmutation processes in high intensity thermal neutron fluxes, in view of proposing solutions to reduce the radiotoxicity of long-lived nuclear wastes. In this context, a Cm sample enriched in {sup 248}Cm ({approx}97 %) was irradiated in thermal neutron flux at the High Flux Reactor (HFR) of the Laue-Langevin Institute (ILL). This work describes a quadrupole ICP-MS (ICP-QMS) analytical procedure for precise and accurate isotopic composition determination of Cm before sample irradiation and of Cm and Cf after sample irradiation. The factors that affect the accuracy and reproducibility of isotopic ratio measurements by ICP-QMS, such as peak centre correction, detector dead time, mass bias, abundance sensitivity and hydrides formation, instrumental background, and memory blank were carefully evaluated and corrected. Uncertainties of the isotopic ratios, taking into account internal precision of isotope ratio measurements, peak tailing, and hydrides formations ranged from 0.3% to 1.3%. This uncertainties range is quite acceptable for the nuclear data to be used in transmutation studies.

  10. Crystal growth and applications of mercuric iodide. Report S-242-TP

    International Nuclear Information System (INIS)

    Schieber, M.; Roth, M.; Schnepple, W.F.

    1983-01-01

    A brief summary is given of a paper which discusses the crystal growth of mercuric iodide, a high-Z wide bandgap semiconductor suitable as a low noise, room temperature x-ray and gamma-ray detector. The paper summarized also reviews the state-of-the-art of the synthesis and purification of the starting material, mechanical properties and dislocation structure of HgI 2 , and recent success in the development of thick HgI 2 spectrometers

  11. 17 CFR 242.404 - Type, form and use of margin.

    Science.gov (United States)

    2010-04-01

    ... accordingly; (ii) The security futures intermediary (or clearing agency or derivatives clearing organization... value; (ii) Each net long or short position in a listed option on a contract for future delivery shall... (CONTINUED) REGULATIONS M, SHO, ATS, AC, AND NMS AND CUSTOMER MARGIN REQUIREMENTS FOR SECURITY FUTURES...

  12. 18 CFR 367.2420 - Account 242, Miscellaneous current and accrued liabilities.

    Science.gov (United States)

    2010-04-01

    ... HOLDING COMPANY ACT OF 2005, FEDERAL POWER ACT AND NATURAL GAS ACT UNIFORM SYSTEM OF ACCOUNTS FOR CENTRALIZED SERVICE COMPANIES SUBJECT TO THE PROVISIONS OF THE PUBLIC UTILITY HOLDING COMPANY ACT OF 2005... and supported so as to show the nature of each liability. ...

  13. 24 CFR 242.33 - Covenant for malpractice, fire, and other hazard insurance.

    Science.gov (United States)

    2010-04-01

    ... for malpractice, fire, and other hazard insurance. The mortgage shall contain a covenant binding the mortgagor to maintain adequate liability, fire, and extended coverage insurance on the property. The... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Covenant for malpractice, fire, and...

  14. High level waste storage tanks 242-A evaporator S/RID phase II assessment report

    Energy Technology Data Exchange (ETDEWEB)

    Biebesheimer, E.

    1996-09-27

    This document, the Standards/Requirements Identification Document (S/RID) Phase 2 Assessment Report for the subject facility, represents the results of a Performance Assessment to determine whether procedures containing S/RID requirements are fully implemented by field personnel in the field. It contains a summary report and three attachments; an assessment schedule, performance objectives, and assessments for selected functional areas.

  15. 17 CFR 242.104 - Stabilizing and other activities in connection with an offering.

    Science.gov (United States)

    2010-04-01

    ... the principal market if the security has traded in the principal market on the day stabilizing is... security has traded in that market on the day stabilizing is initiated or on the last preceding business... expressed in a currency other than the currency of the principal market for the security, such bid may be...

  16. Liu et al., Afr J Tradit Complement Altern Med. (2016) 13(3):230-242 ...

    African Journals Online (AJOL)

    Biosciences) and octadecylsilyl silica gel (Unicorn; 45–60 μm) were used for column ... Shandatianyuan Company, Shandong province, China, in June 2006 and ..... This work is the National High Technology Research and Development ...

  17. 36 CFR 242.16 - Customary and traditional use determination process.

    Science.gov (United States)

    2010-07-01

    ... characterized by efficiency and economy of effort and cost, conditioned by local characteristics; (4) The... generation to generation; (7) A pattern of use in which the harvest is shared or distributed within a...

  18. People and things. CERN Courier, Mar 1984, v. 24(2)

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. Some time ago, Wolfgang ('Pief') Panofsky, Director of SLAC since 1961 and one of the prime movers behind both the famous two-mile electron linac and the Laboratory itself, announced his intention to step down in 1984. Immediately a search began for a worthy successor. Carlo Rubbia, leader of the UA 1 experiment at CERN which last year discovered the W and Z particles, was named by the US science magazine 'Discover' as its 1983 'Scientist of the Year'. A CERN-ECFA Workshop to study the feasibility of hadron colliders which it might at some time in the future be possible to install in the LEP tunnel, is to be held at the University of Lausanne from 21-24 March. Fermilab will host the 1984 US Summer School on High Energy Particle Accelerators from 13-24 August - the fourth in this series of summer schools.The 1984 CERN School of Computing, the eighth in the biennial series, is being organized in collaboration with the Instituto Estudios Energeticos (Junta de Energia Nuclear, Madrid) and the Facultad de Informatica, Barcelona, and will be held from 9-22 September at Aiguablava, Spain. The 1984 Users' Meeting of the High Energy Discussion Group (HEDG) at Brookhaven on 29-31 March will include a Workshop on the possible physics from an improved Alternating Gradient Synchrotron

  19. 24 CFR 242.90 - Eligibility of mortgages covering hospitals in certain neighborhoods.

    Science.gov (United States)

    2010-04-01

    ..., except such requirements (other than those relating to labor standards and prevailing wages or... there is a need in the area for an adequate hospital to serve low and moderate income families. (3) That...

  20. Synthesis of novel 2-(4-(2-morpholinoethoxy)phenyl)-N ...

    Indian Academy of Sciences (India)

    gefitinib4 and the analgesic dextromoramide.5 Certain morpholino acetimidamide derivatives were found to suppress hepatitis C virus replication.6 Paracetamol, a simple acetamide is a widely used analgesic and antipyretic agent. Acetamide derivatives show potential biological functions. They possess excellent antimicro-.

  1. High level waste storage tanks 242-A evaporator standards/requirement identification document

    International Nuclear Information System (INIS)

    Biebesheimer, E.

    1996-01-01

    This document, the Standards/Requirements Identification Document (S/RIDS) for the subject facility, represents the necessary and sufficient requirements to provide an adequate level of protection of the worker, public health and safety, and the environment. It lists those source documents from which requirements were extracted, and those requirements documents considered, but from which no requirements where taken. Documents considered as source documents included State and Federal Regulations, DOE Orders, and DOE Standards

  2. Tris{2-[4-(2-pyridylpyrimidin-2-ylsulfanyl]ethyl}amine

    Directory of Open Access Journals (Sweden)

    Jian-Quan Wang

    2009-08-01

    Full Text Available The tripodal character of the title compound, C33H30N10S3, arises from the three thioether arms surrounding a central amine N atom. The three arms have approximately the same conformation but distinct geometries in a trans–trans–cis conformation, resulting in a short pyridine–sulfanyl N...S distance of 4.320 (7 Å. The distances of the central N atom to the N atoms of three pyridine rings in the arms are 8.305 (7, 8.032 (7 and 5.076 (9Å. In the crystal, molecules are joined into a three-dimensional supramolecular network via effective π–π stacking between adjacent heterocycles [centroid–centroid distances of 3.700 (3–4.118 (4 Å between adjacent interlayer pyrimidine rings and 3.676 (4 Å between the pyridine rings].

  3. People and things. CERN Courier, Mar 1984, v. 24(2)

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1984-03-15

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. Some time ago, Wolfgang ('Pief') Panofsky, Director of SLAC since 1961 and one of the prime movers behind both the famous two-mile electron linac and the Laboratory itself, announced his intention to step down in 1984. Immediately a search began for a worthy successor. Carlo Rubbia, leader of the UA 1 experiment at CERN which last year discovered the W and Z particles, was named by the US science magazine 'Discover' as its 1983 'Scientist of the Year'. A CERN-ECFA Workshop to study the feasibility of hadron colliders which it might at some time in the future be possible to install in the LEP tunnel, is to be held at the University of Lausanne from 21-24 March. Fermilab will host the 1984 US Summer School on High Energy Particle Accelerators from 13-24 August - the fourth in this series of summer schools.The 1984 CERN School of Computing, the eighth in the biennial series, is being organized in collaboration with the Instituto Estudios Energeticos (Junta de Energia Nuclear, Madrid) and the Facultad de Informatica, Barcelona, and will be held from 9-22 September at Aiguablava, Spain. The 1984 Users' Meeting of the High Energy Discussion Group (HEDG) at Brookhaven on 29-31 March will include a Workshop on the possible physics from an improved Alternating Gradient Synchrotron.

  4. Consistent evaluation of neutron cross sections for the 242-244Cm isotopes

    International Nuclear Information System (INIS)

    Ignatyuk, A.V.; Maslov, V.M.

    1989-01-01

    The knowledge of neutron cross-sections for Curium isotopes is necessary for solving the problems of the external fuel cycle. Experimental information on the cross-sections is very meager and does not satisfy requirements and existing evaluations in different libraries differ substantially for fission and (n,2n) reaction cross-sections. This situation requires a critical review of the entire set of evaluations of the neutron cross-sections for Curium. 17 refs, 3 figs

  5. 36 CFR 242.25 - Subsistence taking of fish, wildlife, and shellfish: general regulations.

    Science.gov (United States)

    2010-07-01

    ... the Alaska Department of Fish and Game. Airborne means transported by aircraft. Aircraft means any... grizzly bear. Big game means black bear, brown bear, bison, caribou, Sitka black-tailed deer, elk... gillnet that has not been intentionally staked, anchored, or otherwise fixed in one place. Edible meat...

  6. Evaluation of neutron cross-sections for 242Cm to obtain a complete file

    International Nuclear Information System (INIS)

    Bakhanovich, L.A.; Klepetskij, A.B.; Maslov, V.M.; Porodzinskij, Yu.V.; Sukhovitskij, E.Sh.

    1994-01-01

    Experimental fission, capture, inelastic scattering, (n2n), (n3n) and other cross-sections are scarce or unavailable. As a consequence, theoretical models and parameters systematics have been used extensively in the calculation of these data. Data obtained in this work are compared with previous evaluations. Severe discrepancies were found. (author). 10 refs, 2 figs, 2 tabs

  7. Determination of Am-241, Cm-242 and Cm-244 in environmental samples

    International Nuclear Information System (INIS)

    Afsar, M.; Schuettelkopf, H.

    1988-01-01

    An analytical procedure for the determination of Am and Cm in environmental, liquid and gaseous effluent samples was developed. It is based on extraction chromatography with subsequent anion and cation exchange to remove matrix elements and to purify Am and Cm, which are then electrode posited from an oxalate/HCl medium. The mean value of the chemical yield is about 90%. A detection limit of 7 μBq/g is achieved. The decontamination factors for important α emitters are > 10 4 . Four analyses/week can be performed by one technician. (orig./RB) [de

  8. 2-[4-(2-Chloroacetylphenyl]-2-methyl-1-(pyrrolidin-1-ylpropan-1-one

    Directory of Open Access Journals (Sweden)

    Dong-mei Ren

    2013-08-01

    Full Text Available The asymmetric unit of the title compound, C16H20ClNO2, contains two molecules in which the dihedral angles between the benzene ring and the plane of the amide unit are 77.4 (1 and 81.1 (1°. In both molecules, the five-membered ring adopts an envelope conformation with one of the β-C atoms as the flap. In the crystal, molecules are connected via C—H...O hydrogen bonds, forming chains along the b-axis direction. These chains are further linked by C—H...π interactions, forming a three-dimensional network.

  9. Sexospécificités | Page 242 | CRDI - Centre de recherches pour le ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Waterborne and helminthic diseases are rampant, as are respiratory and digestive illnesses. But the situation is improving dramatically for the city's poor, thanks to a unique collaboration between Nepalese and Canadian researchers and the work of a local nongovernmental organization. Read more about CASE STUDY: ...

  10. 32 CFR 242.9 - Academic, intellectual, and personal requirements for admission to advanced standing.

    Science.gov (United States)

    2010-07-01

    ... aptitude and motivation for a career in medicine in the Uniformed Services will be prime considerations in making admissions decisions. Only the most promising of candidates will be accepted, as judged by...

  11. 24 CFR 242.23 - Maximum mortgage amounts and cash equity requirements.

    Science.gov (United States)

    2010-04-01

    ... addition to the value of plant, property, and equipment and other values recognized as loan security in the commitment process. Exercise of this discretion shall never cause a loan to exceed 90 percent of estimated... COMMISSIONER, DEPARTMENT OF HOUSING AND URBAN DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL...

  12. Separation of Am-Cm from Al(NO3)3 waste solutions by in-canyon-tank precipitation as oxalates

    International Nuclear Information System (INIS)

    Gray, L.W.; Burney, G.A.; Wilson, T.W.; McKibben, J.M.; Bibler, N.E.; Holtzscheiter, E.W.; Campbell, T.G.

    1982-04-01

    A process for recovery of Am-Cm residues from high-activity waste concentrates has been developed specifically for application in Savannah River Plant (SRP) canyon tanks. The Am-Cm residues were collected from a campaign to produce plutonium containing high isotopic concentrations of 242 Pu. The separation of Am-Cm from the high-activity waste stream, containing about 2M Al(NO 3 ) 3 , is necessary to produce an acceptable feed solution for a later pressurized cation exchange chromatography separation and purification step. The new process includes formic acid denitration, adjustment of contaminating cations by evaporation and water dilution, and oxalate precipitation of the actinides and lanthanides. After washing, the precipitate was dissolved in 8M nitric acid and the oxalate was destroyed by nitric acid oxidation that was catalyzed by manganous ions. This new process generates about one-fourth the waste of the californium solvent extraction process, which it replaced. The new process also produces a cleaner feed solution for the pressurized cation exchange chromatography separation and purification step

  13. Freeze drying method for preparing radiation source material

    International Nuclear Information System (INIS)

    Mosley, W.C.; Smith, P.K.

    1976-01-01

    Fabrication of a neutron source is specifically claimed. A palladium/californium solution is freeze dried to form a powder which, through conventional powder metallurgy, is shaped into a source containing the californium evenly distributed through a palladium metal matrix. (E.C.B.)

  14. Project C-018H, 242-A evaporator/PUREX Plant Process Condensate Treatment Facility Instrumentation and Control (I ampersand C)

    International Nuclear Information System (INIS)

    Dupuis, A.

    1995-01-01

    This Acceptance Test Procedure (ATP) has been prepared to demonstrate that the Collection System Instrumentation ampersand Control System for Project C-018H performs according to design. Specifically, this ATP is designed to verify the following overall system requirements: The input and outputs properly connected to the LCU terminal strips. The control system software conforms to the configuration specified by the logic diagrams, piping and instrumentation diagrams (P ampersand ID), and the LERF operating philosophy. Testing will be performed using actual signals. If actual signals are not available, then simulated signals will be used to complete the tests

  15. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The purpose of this Requirements Identification Document (RID) section is to identify, in one location, all of the facility specific requirements and good industry practices which are necessary or important to establish an effective Issues Management Program for the Tank Farm Facility. The Management Systems Functional Area includes the site management commitment to environmental safety and health (ES&H) policies and controls, to compliance management, to development and management of policy and procedures, to occurrence reporting and corrective actions, resource and issue management, and to the self-assessment process.

  16. Electrical/instrumentation acceptance test report for Project C-018H, 242-A Evaporator/PUREX Plant condensate treatment facility

    International Nuclear Information System (INIS)

    Compau, R.A. Jr.

    1995-01-01

    This project is part of the 200 Area Effluent Treatment Facility. The acceptance test procedure describes test methods for leak detection units, pump flow switches, pump level control valves, room air temperature monitor, leachate pump status contacts, basin pump status contacts, catch basin leak detector, leachate level monitors, and basin level monitors. These are all components of the C-018H Collection System

  17. An ontological analysis of the electrocardiogram - DOI: 10.3395/reciis.v3i1.242en

    Directory of Open Access Journals (Sweden)

    Bernardo Gonçalves

    2009-04-01

    Full Text Available Bioinformatics has been a fertile field for the application of the discipline of formal ontology. The principled representation of biomedical entities has increasingly supported biological research, with direct benefits ranging from the reformulation of medical terminologies to the introduction of new perspectives for enhanced models of Electronic Health Records (EHR. This paper introduces an application-independent ontological analysis of the electrocardiogram (ECG grounded in the Unified Foundational Ontology. With the objective of investigating the phenomena underlying this cardiological exam, we deal with the sub-domains of human heart electrophysiology and anatomy. We then outline an ECG Ontology built upon the OBO Relation Ontology. In addition, the domain ontology sketched here takes inspiration both in the Foundational Model of Anatomy and in the Ontology of Functions proposed under the auspices of the General Formal Ontology (GFO research program.

  18. Acceptance test procedure for C-018H, 242-A evaporator/PUREX plant process condensate treatment facility

    International Nuclear Information System (INIS)

    Parrish, D.E.

    1994-01-01

    This Acceptance Test Procedure (ATP) has been prepared to demonstrate that the Electrical/Instrumentation system function as required for this facility. Each company or organization participating in this ATP will designate personnel to assume the responsibilities and duties as defined herein for their respective roles

  19. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 5

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The Fire Protection functional area for the Hanford Site Tank Farm facilities and support structures is based on the application of relevant DOE orders, regulations, and industry codes and standards. The fire protection program defined in this document may be divided into three areas: (1) organizational, (2) administrative programmatic features, and (3) technical features. The information presented in each section is in the form of program elements and orders, regulations, industry codes, and standards that serve as the attributes of a fire protection program for the Tank Farm facilities. Upon completion this document will be utilized as the basis to evaluate compliance of the fire protection program being implemented for the Tank Farm facilities with the requirements of DOE orders and industry codes and standards.

  20. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 2

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The Quality Assurance Functional Area Requirements Identification Document (RID), addresses the programmatic requirements that ensure risks and environmental impacts are minimized, ensure safety, reliability, and performance are maximized through the application of effective management systems commensurate with the risks posed by the Tank Farm Facility and its operation. This RID incorporates guidance intended to provide Tank Farms management with the necessary requirements information to develop, upgrade, or assess the effectiveness of a Quality Assurance Program in the performance of organizational and functional activities. Quality Assurance is defined as all those planned and systematic actions necessary to provide adequate confidence that a facility, structure, system, or component will perform satisfactorily and safely in service. This document will provide the specific requirements to meet DNFSB recommendations and the guidance provided in DOE Order 5700.6C, utilizing industry codes, standards, regulatory guidelines, and industry good practices that have proven to be essential elements for an effective and efficient Quality Assurance Program as the nuclear industry has matured over the last thirty years.

  1. 47 CFR 15.242 - Operation in the bands 174-216 MHz and 470-668 MHz.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 1 2010-10-01 2010-10-01 false Operation in the bands 174-216 MHz and 470-668... bands 174-216 MHz and 470-668 MHz. (a) The marketing and operation of intentional radiators under the... services, facilities, and beds for use beyond 24 hours in rendering medical treatment and institutions and...

  2. SU-E-T-242: Design of a Novel Afterloader Clearance QA Device for Biliary HDR Therapy

    Energy Technology Data Exchange (ETDEWEB)

    Mullins, JP; Deufel, CL [Mayo Clinic, Rochester, MN (United States)

    2015-06-15

    Purpose: Bile duct cancer affects 2–3 thousand people annually in the United States. Radiation therapy has been shown to double median survival, with combined external beam and intraluminal high dose-rate (HDR) brachytherapy being most effective. Endoscopic retrograde cholangiopancreatography (ERCP) biliary HDR, a less-invasive alternative to trans-hepatic brachytherapy, is delivered through a catheter that travels a tortuous path from nose to bile duct, requiring wire drive force and dexterity beyond typical afterloader performance specifications. Thus, specific afterloader quality assurance(QA) is recommended for this procedure. Our aim was to create a device and process for Varisource afterloader clearance QA with objectives that it be quantitative and can monitor afterloader performance over time, compare performance between two distinct afterloaders and potentially Result in a predictive nomogram for patient-specific clearance. Methods: Based on retrospective reconstruction of 20 ERCP patient anatomies, we designed a phantom to test afterloader ability to drive the source wire along an intended treatment path. The ability of the afterloader to fully extend the intended treatment path is a function of number and diameters of turns. We have determined experimentally that relative position of the turns does not impact performance. Results: Both patient and QA paths involve three common turns/loops: a large turn representing the stomach(10.8cm±2.0cm), an elliptical loop representing the duodenum(7.3cm±1.5cmx4.8cm±0.7cm), and a final turn at the end of the bile duct that may be tight for some patient-specific anatomies and absent in others(3.7cm±0.7cm, where present). Our phantom design uses anatomical average turn diameters for the stomach and duodenum then terminates in a turn of quantitatively selectable diameter. The smallest final turn diameter that an afterloader can pass is recorded as the QA parameter. Conclusion: With this device and QA process, we have the ability to quantitatively evaluate and track our afterloader performance for a technically challenging ERCP brachytherapy procedure.

  3. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 2

    International Nuclear Information System (INIS)

    1994-04-01

    The Quality Assurance Functional Area Requirements Identification Document (RID), addresses the programmatic requirements that ensure risks and environmental impacts are minimized, ensure safety, reliability, and performance are maximized through the application of effective management systems commensurate with the risks posed by the Tank Farm Facility and its operation. This RID incorporates guidance intended to provide Tank Farms management with the necessary requirements information to develop, upgrade, or assess the effectiveness of a Quality Assurance Program in the performance of organizational and functional activities. Quality Assurance is defined as all those planned and systematic actions necessary to provide adequate confidence that a facility, structure, system, or component will perform satisfactorily and safely in service. This document will provide the specific requirements to meet DNFSB recommendations and the guidance provided in DOE Order 5700.6C, utilizing industry codes, standards, regulatory guidelines, and industry good practices that have proven to be essential elements for an effective and efficient Quality Assurance Program as the nuclear industry has matured over the last thirty years

  4. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 7

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    This Requirements Identification Document (RID) describes an Occupational Health and Safety Program as defined through the Relevant DOE Orders, regulations, industry codes/standards, industry guidance documents and, as appropriate, good industry practice. The definition of an Occupational Health and Safety Program as specified by this document is intended to address Defense Nuclear Facilities Safety Board Recommendations 90-2 and 91-1, which call for the strengthening of DOE complex activities through the identification and application of relevant standards which supplement or exceed requirements mandated by DOE Orders. This RID applies to the activities, personnel, structures, systems, components, and programs involved in maintaining the facility and executing the mission of the High-Level Waste Storage Tank Farms.

  5. Analysis of volatile headspace gases sampled by cryogenic traps from Westinghouse Hanford Company Tank 242-C-112 March 1992

    International Nuclear Information System (INIS)

    Lucke, R.B.; Clauss, S.A.

    1993-10-01

    Results are given from gas chromatography/mass spectrometry (GC/MS) analyses of the headspace samples obtained by using cryogenic traps from Westinghouse Hanford Company (WHC) Tank 112-C during the month of March, 1992. Samples were analyzed as received with no sample preparation. Analyses included direct GC/MS for volatile/semivolatile components, and direct GC/MS for ammonia. Purge and trap GC/MS analysis was not done. In addition, aliquots were sent to Karl Pool, Pacific Northwest Laboratory, for hydrogen cyanide analysis by ion chromatography, the results are reported here. All concentrations are reported for the methanol extract solutions. To calculate concentrations in the headspace, the cryo-sampling air volume and the methanol rinse volume must be obtained from cryo-sampling personnel at WHC. Triplicate analyses were done on all samples, and average concentrations and standard deviations are reported. One significant result was that no ammonia was detected

  6. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 3

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The Safeguards and Security (S&S) Functional Area address the programmatic and technical requirements, controls, and standards which assure compliance with applicable S&S laws and regulations. Numerous S&S responsibilities are performed on behalf of the Tank Farm Facility by site level organizations. Certain other responsibilities are shared, and the remainder are the sole responsibility of the Tank Farm Facility. This Requirements Identification Document describes a complete functional Safeguards and Security Program that is presumed to be the responsibility of the Tank Farm Facility. The following list identifies the programmatic elements in the S&S Functional Area: Program Management, Protection Program Scope and Evaluation, Personnel Security, Physical Security Systems, Protection Program Operations, Material Control and Accountability, Information Security, and Key Program Interfaces.

  7. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 1

    International Nuclear Information System (INIS)

    1994-04-01

    The purpose of this Requirements Identification Document (RID) section is to identify, in one location, all of the facility specific requirements and good industry practices which are necessary or important to establish an effective Issues Management Program for the Tank Farm Facility. The Management Systems Functional Area includes the site management commitment to environmental safety and health (ES ampersand H) policies and controls, to compliance management, to development and management of policy and procedures, to occurrence reporting and corrective actions, resource and issue management, and to the self-assessment process

  8. 32 CFR 242a.4 - Grounds on which meetings may be closed, or information may be withheld.

    Science.gov (United States)

    2010-07-01

    ... and commercial or financial information obtained from a person, privileged or confidential; (e... a subpoena, or USUHS participation in a civil action or proceeding, an action in a foreign court or international tribunal, or an arbitration, or the initiation, conduct, or disposition by the USUHS of a...

  9. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 3

    International Nuclear Information System (INIS)

    1994-04-01

    The Safeguards and Security (S ampersand S) Functional Area address the programmatic and technical requirements, controls, and standards which assure compliance with applicable S ampersand S laws and regulations. Numerous S ampersand S responsibilities are performed on behalf of the Tank Farm Facility by site level organizations. Certain other responsibilities are shared, and the remainder are the sole responsibility of the Tank Farm Facility. This Requirements Identification Document describes a complete functional Safeguards and Security Program that is presumed to be the responsibility of the Tank Farm Facility. The following list identifies the programmatic elements in the S ampersand S Functional Area: Program Management, Protection Program Scope and Evaluation, Personnel Security, Physical Security Systems, Protection Program Operations, Material Control and Accountability, Information Security, and Key Program Interfaces

  10. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 6

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The scope of the Environmental Restoration and Waste Management (EM) Functional Area includes the programmatic controls associated with the management and operation of the Hanford Tank Farm Facility. The driving management organization implementing the programmatic controls is the Tank Farms Waste Management (WM)organization whose responsibilities are to ensure that performance objectives are established; and that measurable criteria for attaining objectives are defined and reflected in programs, policies and procedures. Objectives for the WM Program include waste minimization, establishment of effective waste segregation methods, waste treatment technology development, radioactive (low-level, high-level) hazardous and mixed waste transfer, treatment, and storage, applicability of a corrective action program, and management and applicability of a decontamination and decommissioning (D&D) program in future years.

  11. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 5

    International Nuclear Information System (INIS)

    1994-04-01

    The Fire Protection functional area for the Hanford Site Tank Farm facilities and support structures is based on the application of relevant DOE orders, regulations, and industry codes and standards. The fire protection program defined in this document may be divided into three areas: (1) organizational, (2) administrative programmatic features, and (3) technical features. The information presented in each section is in the form of program elements and orders, regulations, industry codes, and standards that serve as the attributes of a fire protection program for the Tank Farm facilities. Upon completion this document will be utilized as the basis to evaluate compliance of the fire protection program being implemented for the Tank Farm facilities with the requirements of DOE orders and industry codes and standards

  12. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 6

    International Nuclear Information System (INIS)

    1994-04-01

    The scope of the Environmental Restoration and Waste Management (EM) Functional Area includes the programmatic controls associated with the management and operation of the Hanford Tank Farm Facility. The driving management organization implementing the programmatic controls is the Tank Farms Waste Management (WM)organization whose responsibilities are to ensure that performance objectives are established; and that measurable criteria for attaining objectives are defined and reflected in programs, policies and procedures. Objectives for the WM Program include waste minimization, establishment of effective waste segregation methods, waste treatment technology development, radioactive (low-level, high-level) hazardous and mixed waste transfer, treatment, and storage, applicability of a corrective action program, and management and applicability of a decontamination and decommissioning (D ampersand D) program in future years

  13. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 7

    International Nuclear Information System (INIS)

    1994-04-01

    This Requirements Identification Document (RID) describes an Occupational Health and Safety Program as defined through the Relevant DOE Orders, regulations, industry codes/standards, industry guidance documents and, as appropriate, good industry practice. The definition of an Occupational Health and Safety Program as specified by this document is intended to address Defense Nuclear Facilities Safety Board Recommendations 90-2 and 91-1, which call for the strengthening of DOE complex activities through the identification and application of relevant standards which supplement or exceed requirements mandated by DOE Orders. This RID applies to the activities, personnel, structures, systems, components, and programs involved in maintaining the facility and executing the mission of the High-Level Waste Storage Tank Farms

  14. 32 CFR 242.8 - Academic, intellectual, and personal requirements for admission to the first-year class.

    Science.gov (United States)

    2010-07-01

    ... matriculation. (ii) Prerequisite course work. Area of specialization in college is not a limiting factor in... course work equates to that course work which extends over a two-semester or three-quarter period and... admission, preference generally will be shown to applicants who also have had some college course work in...

  15. Radionuclides in rodents

    International Nuclear Information System (INIS)

    Taylor, G.N.

    1985-01-01

    Studies are being conducted in mice comparing the toxicity of radium-226, plutonium-239, americium-241, californium-249 and californium-252 in C57B1/Do (albino) mice and the toxicity of americium-241, plutonium-239 and radium-226 in deer mice (Peromyscus maniculatus) and grasshopper mice (Onychomys leucogaster). These experiments will ultimately enable comparison of the toxicity of the above actinide toxicity in man to be made using radium toxicity as the baseline

  16. A root hairless barley mutant for elucidating genetic of root hairs and phosphorus uptake (Correction in v. 242, 2002, p. 299)

    DEFF Research Database (Denmark)

    Gahoonia, T.S.; Nielsen, N.E.; Priyavadan, A.J.

    2001-01-01

    This paper reports a new barley mutant missing root hairs. The mutant was spontaneously discovered among the population of wild type (Pallas, a spring barley cultivar), producing normal, 0.8 mm long root hairs. We have called the mutant bald root barley (brb). Root anatomical studies confirmed...

  17. Wide Band Gap Semiconductors Symposium Held in Boston, Massachusetts on 2-6 December 1991. Materials Research Society Symposium Proceedings. Volume 242

    Science.gov (United States)

    1992-01-01

    AND PROPERTIES OF WIDE BAND-GAP Il-VI STRAINED- LAYER SUPERLATTICE 227 Hailong Wang. Jie Cui. Aidong Shen. Liang Xu, Yunliang Chen. and Yuhua Shen IN...WANG JIE CUI AIDONG SHEN LIANG XU YUNLIANG CHEN AND YUHUA SHEN Shanghai Institute of Optics and Fine Mechanics, Academia Sinica P.O.Box 800-216 Shanghai...He Zujou, Cao Huazhe, Su Wuda, Chen Zhongcai, Zhon Feng and Wang Erguang, Thin Solid Films, 139,261(1986). 22) Xin Li and T.L.Tansley, J.AppI.Phys

  18. Earth system modelling on system-level heterogeneous architectures: EMAC (version 2.42) on the Dynamical Exascale Entry Platform (DEEP)

    Science.gov (United States)

    Christou, Michalis; Christoudias, Theodoros; Morillo, Julián; Alvarez, Damian; Merx, Hendrik

    2016-09-01

    We examine an alternative approach to heterogeneous cluster-computing in the many-core era for Earth system models, using the European Centre for Medium-Range Weather Forecasts Hamburg (ECHAM)/Modular Earth Submodel System (MESSy) Atmospheric Chemistry (EMAC) model as a pilot application on the Dynamical Exascale Entry Platform (DEEP). A set of autonomous coprocessors interconnected together, called Booster, complements a conventional HPC Cluster and increases its computing performance, offering extra flexibility to expose multiple levels of parallelism and achieve better scalability. The EMAC model atmospheric chemistry code (Module Efficiently Calculating the Chemistry of the Atmosphere (MECCA)) was taskified with an offload mechanism implemented using OmpSs directives. The model was ported to the MareNostrum 3 supercomputer to allow testing with Intel Xeon Phi accelerators on a production-size machine. The changes proposed in this paper are expected to contribute to the eventual adoption of Cluster-Booster division and Many Integrated Core (MIC) accelerated architectures in presently available implementations of Earth system models, towards exploiting the potential of a fully Exascale-capable platform.

  19. catena-Poly[[[tetraaquacobalt(II]-μ-4,4′-bipyridine-κ2N:N′] 2-[4-(2-carboxylatoethylphenoxy]acetate

    Directory of Open Access Journals (Sweden)

    Xi-Fang Wang

    2009-07-01

    Full Text Available In the title complex, {[Co(C10H8N2(H2O4](C11H10O5}n, the unique CoII ion lies on an inversion center and is coordinated by two N atoms from two 4,4′-bipyridine ligands and four O atoms from four water molecules in a slightly distorted octahedral coordination geometry. The 4,4′-bipyridine ligands bridge CoII ions into a one-dimensional chain structure. In the crystal structure, intermolecular O—H...O hydrogen bonds link cations and anions into a three-dimensional network. The dianions are completely disordered about an inversion center.

  20. Multibeam collection for TN242: Multibeam data collected aboard Thomas G. Thompson from 2009-11-02 to 2009-11-06, Seattle, WA to Seattle, WA

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set is part of a larger set of data called the Multibeam Bathymetry Database (MBBDB) where other similar data can be found at...

  1. Identification of a sudden cardiac death susceptibility locus at 2q24.2 through genome-wide association in European ancestry individuals.

    Directory of Open Access Journals (Sweden)

    Dan E Arking

    2011-06-01

    Full Text Available Sudden cardiac death (SCD continues to be one of the leading causes of mortality worldwide, with an annual incidence estimated at 250,000-300,000 in the United States and with the vast majority occurring in the setting of coronary disease. We performed a genome-wide association meta-analysis in 1,283 SCD cases and >20,000 control individuals of European ancestry from 5 studies, with follow-up genotyping in up to 3,119 SCD cases and 11,146 controls from 11 European ancestry studies, and identify the BAZ2B locus as associated with SCD (P = 1.8×10(-10. The risk allele, while ancestral, has a frequency of ~1.4%, suggesting strong negative selection and increases risk for SCD by 1.92-fold per allele (95% CI 1.57-2.34. We also tested the role of 49 SNPs previously implicated in modulating electrocardiographic traits (QRS, QT, and RR intervals. Consistent with epidemiological studies showing increased risk of SCD with prolonged QRS/QT intervals, the interval-prolonging alleles are in aggregate associated with increased risk for SCD (P = 0.006.

  2. SU-E-T-242: Monte Carlo Simulations Used to Test the Perturbation of a Reference Ion Chamber Prototype Used for Small Fields

    Energy Technology Data Exchange (ETDEWEB)

    Vazquez Quino, L; Calvo, O; Huerta, C; DeWeese, M [Midsouth Radation Physics, Little Rock, AR (United States)

    2014-06-01

    Purpose: To study the perturbation due to the use of a novel Reference Ion Chamber designed to measure small field dosimetry (KermaX Plus C by IBA). Methods: Using the Phase-space files for TrueBeam photon beams available by Varian in IAEA-compliant format for 6 and 15 MV. Monte Carlo simulations were performed using BEAMnrc and DOSXYZnrc to investigate the perturbation introduced by a reference chamber into the PDDs and profiles measured in water tank. Field sizes ranging from 1×1, 2×2,3×3, 5×5 cm2 were simulated for both energies with and without a 0.5 mm foil of Aluminum which is equivalent to the attenuation equivalent of the reference chamber specifications in a water phantom of 30×30×30 cm3 and a pixel resolution of 2 mm. The PDDs, profiles, and gamma analysis of the simulations were performed as well as a energy spectrum analysis of the phase-space files generated during the simulation. Results: Examination of the energy spectrum analysis performed shown a very small increment of the energy spectrum at the build-up region but no difference is appreciated after dmax. The PDD, profiles and gamma analysis had shown a very good agreement among the simulations with and without the Al foil, with a gamma analysis with a criterion of 2% and 2mm resulting in 99.9% of the points passing this criterion. Conclusion: This work indicates the potential benefits of using the KermaX Plus C as reference chamber in the measurement of PDD and Profiles for small fields since the perturbation due to in the presence of the chamber the perturbation is minimal and the chamber can be considered transparent to the photon beam.

  3. Thermodynamic Assessment of Hot Corrosion Mechanisms of Superalloys Hastelloy N and Haynes 242 in Eutectic Mixture of Molten Salts KF and ZrF4

    Energy Technology Data Exchange (ETDEWEB)

    Michael V. Glazoff

    2012-02-01

    The KF - ZrF4 system was considered for the application as a heat exchange agent in molten salt nuclear reactors (MSRs) beginning with the work carried out at ORNL in early fifties. Based on a combination of excellent properties such as thermal conductivity, viscosity in the molten state, and other thermo-physical and rheological properties, it was selected as one of possible candidates for the nuclear reactor secondary heat exchanger loop.

  4. Final characterization and safety screen report of double shell tank 241-AP-104 for 242-A evaporator, campaign 96-1

    International Nuclear Information System (INIS)

    Miller, G.L.

    1996-01-01

    This data package satisfies the requirement for a format IV, final report. It is a follow-up to the 45-day safety screen report for tank AP-104. Evaporator candidate feed from tank 241-AP-104 (hereafter referred to as AP-104) was characterized for physical, inorganic, organic and radiochemical parameters by the Westinghouse Hanford Company, 222-S Laboratory, and by the Battelle Pacific Northwest National Laboratory (PNNL), Analytical Chemistry Laboratory (ACL) as directed by the Tank Sample and Analysis Plan (TSAP), References 1 through 4. Preliminary data in the form of summary analytical tables were provided to the project in advance of this final report to enable early estimation of evaporator operational parameters, using the Predict modeling program. Laboratory analyses at ACL Laboratory was performed according to the TSAP. Analyses were performed at the 222-S Laboratory as defined and specified in the TSAP and the Laboratory's Quality Assurance Plan, References 5 and 6. Any deviations from the instructions documented in the TSAP are discussed in this narrative and are supported with additional documentation. SAMPLING The TSAP, section 2, provided sampling information for waste samples collected from tank AP-104. The bottle-on-a-string method was used to collect liquid grab samples from the tank. Each glass sample bottle was amber, precleaned, and contained approximately 100 milliliters. Each bottle was closed with a teflon seal cap (or teflon septum for volatile organic analysis samples). Field blank samples were prepared by placing deionized water into sampling bottles, lowering the unclosed bottles into the riser for a period of time, retrieving them from the riser, and then closing the bottles with the same types of caps used for the tank samples. None of the samples were preserved by acidification. Upon receipt, the sample bottles destined for organic analyses were placed in a refrigerator. No attempt was made during sampling to assure the complete filling of the bottles so as to exclude all headspace. These actions were consistent with safety procedures, which attempt to limit personnel exposure to hazardous ionizing radiation

  5. Clinical performance of provisional screw-retained metal-free acrylic restorations in an immediate loading implant protocol: a 242 consecutive patients' report.

    Science.gov (United States)

    Suarez-Feito, Jose-María; Sicilia, Alberto; Angulo, Jorge; Banerji, Subir; Cuesta, Isabel; Millar, Brian

    2010-12-01

    To evaluate the clinical performance of provisional screw-retained metal-free acrylic restorations in an immediate loading implant protocol. Two hundred and forty-two consecutive patients were selected retrospectively, who received 1011 implants and 311 immediate provisional screw-retained implant restorations (2-4 h after implant surgery). The patients were monitored for a period of 2-3 months, until they were referred for a final restoration. The primary variables recorded include the survival time and the appearance of fractures in the provisional restoration, and the independent variables included age, sex, dental arch, type of restoration, type of attachment and components used, as well as cantilevers and opposing dentition. A survival analysis (Kaplan-Meier) and a Cox regression analysis were performed. Twenty-three restorations in 20 patients (8.26%, 95% CI 4.8-11.7) showed at least one fracture (7.39%). More than half of the new fractures (52%, 12 cases) occurred in the first 4 weeks. The cumulative survival probability observed was greater in mandible (P=0.05) and non-cantilever restorations (P=0.001), and in those opposed by full restorations or natural teeth (P=0.001). With an opposing implant-supported prosthesis, the risk of fracture was multiplied by 4.7, and the use of cantilevers as well as the location of the restoration in the maxilla multiply the risk by 3.4-3.5. Immediate provisional screw-retained metal-free implant-supported restorations can be considered a reliable restoration (92.6% remain intact) for the healing period of 3 months. © 2010 John Wiley & Sons A/S.

  6. Trends in radioisotope development and utilization in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Mott, W E [Energy Research and Development Administration, Washington, D.C. (USA)

    1976-06-01

    The current trends in radioisotope and radiation technology in the United States are overviewed with emphasis on the developments since the 1973 Conference. The comments focus primarily on the research and development activities receiving the most attention today from the various agencies of the Government. Among the many available radionuclides, technetium-99m has played the single most important role for making possible the developments in the field of nuclear medicine. Many other short lived medium-lived nuclides are applied in the fields of nuclear medicine, cardiac pacemaker, artificial heart, and blood irradiator. Radiation processing is now firmly established in the United States. The trends in sewage treatment, polymer-impregnated materials, bioengineering, and food irradiation are reviewed. The programs for californium-252, strontium-90, cesium-137, plutonium-238, and krypton-85 are also reviewed. The author concludes this paper with the acknowledgement that Japanese researchers have contributed to and have been closely involved in many of the programs discussed. Of particular note is the participation in the clinical phase of the californium-252 radiotherapy program. Several Japanese hospitals have been cooperating with the United States since the very beginning of the californium-252 program in determining the value of the californium-252 neutron therapy. The research being performed is unique, and will contribute greatly to the decisions on the ultimate future of californium-252 for therapeutic purposes.

  7. Quantum-chemical consideration of extermal valent forms of actinides

    International Nuclear Information System (INIS)

    Ionova, G.V.; Pershina, V.G.; Spitsyn, V.I.

    1982-01-01

    Stability of valent forms of actinides that has not yet studied experimentally, is considered within the framework of quantum-chemical considerations. Oxidizing potentials E 0 for actinide elements are determined theoretically. A dependence of the definite valent state stability on relativistic effect is shown. A conclusion is made that oxidizing potential E 0 (4-5) for americium should be higher than E 0 (4-5) for plutonium. A relatively small oxidizing potential E 0 (4-5) for curium speaks about principle possibility of production of five-valent curium in solution, though it is less stable than the six-valent one. Oxidizing potential corresponding to transition of three-valent californium into the four-valent state should be less than the value adopted in literature. A relatively small oxidizing potential of californium E 0 (4-5) speaks about possible existence of five-valent californium in solution

  8. Source storage and transfer cask: Users Guide

    International Nuclear Information System (INIS)

    Eccleston, G.W.; Speir, L.G.; Garcia, D.C.

    1985-04-01

    The storage and shield cask for the dual californium source is designed to shield and transport up to 3.7 mg (2 Ci) of 252 Cf. the cask meets Department of Transportation (DOT) license requirements for Type A materials (DOT-7A). The cask is designed to transfer sources to and from the Flourinel and Fuel Storage (FAST) facility delayed-neutron interrogator. Californium sources placed in the cask must be encapsulated in the SR-CF-100 package and attached to Teleflex cables. The cask contains two source locations. Each location contains a gear box that allows a Teleflex cable to be remotely moved by a hand crank into and out of the cask. This transfer procedure permits sources to be easily removed and inserted into the delayed-neutron interrogator and reduces personnel radiation exposure during transfer. The radiation dose rate with the maximum allowable quantity of californium (3.7 mg) in the cask is 30 mR/h at the surface and less than 2 mR/h 1 m from the cask surface. This manual contains information about the cask, californium sources, describes the method to ship the cask, and how to insert and remove sources from the cask. 28 figs

  9. Neutron spectra from radionuclide sources for cardiac pacemakers

    International Nuclear Information System (INIS)

    Kluge, H.

    1975-01-01

    Neutron spectra from Plutonium 238 radioisotope batteries powering cardiac pacemakers are measured in the energy range above 0.7 MeV. The results are used to calculate radiation doses within a cylindrical phantom. There are only minor differences between the different types of plutonium 238-batteries and californium 252-batteries

  10. Validation of the MCNP-DSP Monte Carlo code for calculating source-driven noise parameters of subcritical systems

    International Nuclear Information System (INIS)

    Valentine, T.E.; Mihalczo, J.T.

    1995-01-01

    This paper describes calculations performed to validate the modified version of the MCNP code, the MCNP-DSP, used for: the neutron and photon spectra of the spontaneous fission of californium 252; the representation of the detection processes for scattering detectors; the timing of the detection process; and the calculation of the frequency analysis parameters for the MCNP-DSP code

  11. Magnetic measurements of the transuranium elements. Progress report, January 1, 1984-December 31, 1984

    International Nuclear Information System (INIS)

    Huray, P.G.; Nave, S.E.

    1984-01-01

    Measurements of the magnetic properties of dhcp californium-249 metal indicated the presence of three regions of differing magnetic character. Additional measurements are also reported. Magnetic moments and valence states of terbium in TbF 3 , BaTbO 3 , and TbO 1 8 are discussed. Progress on high-field operation of the micro-magnetic susceptometer is reported

  12. Single-event burnout of power MOSFET devices for satellite application

    International Nuclear Information System (INIS)

    Xue Yuxiong; Tian Kai; Cao Zhou; Yang Shiyu; Liu Gang; Cai Xiaowu; Lu Jiang

    2008-01-01

    Single-event burnout (SEB) sensitivity was tested for power MOSFET devices, JTMCS081 and JTMCS062, which were made in Institute of Microelectronics, Chinese Academy of Sciences, using californium-252 simulation source. SEB voltage threshold was found for devices under test (DUT). It is helpful for engineers to choose devices used in satellites. (authors)

  13. ADS-HE: Evaluated Nuclear Data Library up to 1 GeV for 202Hg, 208Pb, 209Bi, 232Th, 235U, 238U, 237Np, 239Pu, 242Am and 245Cm

    International Nuclear Information System (INIS)

    Lopez Aldama, Daniel

    2013-12-01

    Accelerator Driven Systems (ADS) are being developed for power generation and the transmutation of actinide and fission product waste, and well-defined cross-section libraries suitable for their transport calculations are required. Transport of high energy neutrons and protons near the target assembly requires an extension of the library for incident energies up to 1 GeV. An ADS-HE library for incident neutrons on selected target elements has been developed to meet this request, and assist benchmarking studies linked to ADS experiments and design concepts. New evaluations of high-energy data from 20 MeV up to 1 GeV have been carried out by S.G. Yavshits and O.T. Grudzevich (see INDC(NDS)-0615). The ADS- HE library has been prepared from these high-energy evaluations combined with evaluations below 20 MeV selected from the ENDF/B-VII.1, the JEFF-3.1.2 and the JENDL-4u2 libraries. The ADS-HE library was processed in suitable forms for Monte Carlo transport codes used in the analysis of ADS. ADS-HE is freely available from the IAEA Nuclear Data Section, and is readily accessible on the web site: http://www-nds.iaea.org/ads/adshe.html. (author)

  14. Comment on ;Evolution of high-pressure mafic granulites and pelitic gneisses from NE Madagascar: Tectonic implications;. Tectonophysics, 662, 219-242 (2015) by Ishwar-Kumar et al.

    Science.gov (United States)

    Goncalves, Philippe; Brandt, Sönke; Nicollet, Christian; Tucker, Robert

    2017-05-01

    Determining the possible tectonic regimes active during the Neoproterozoic is crucial for the knowledge of the evolution of the super-continent Gondwana. In Madagascar, that occupies a key position in Gondwana, there is an on-going debate regarding the location of possible suture zones and the implications in terms of paleo-geography. Recognizing high-pressure to ultra-high pressure conditions in mafic rocks is commonly viewed as a strong argument for paleo-subduction zones. Ishwar-Kumar et al. (2015) report unusual high pressure conditions (24 kbar) in Neoproterozoic to Cambrian rocks from North-Central Madagascar (Andriamena Complex). They propose a geodynamic model in which exhumation of the high pressure terranes from up to 80 km to 40 km occurred via vertical extrusion during the collision of various crustal blocks after subduction and closure of an oceanic domain during the formation of Gondwana in the late Neoproterozoic to Cambrian. We question this model and in particular the (ultra-)high pressure conditions reported, because their estimation is based on a misinterpretation of the petrography and inaccurate thermodynamic modeling for the crucial metabasite sample. The authors suggest that garnet-quartz coronas around orthopyroxene and ilmenite coexist with clinopyroxene. The postulated garnet-clinopyroxene-quartz assemblage is interpreted to document an eclogite facies overprint. However, the presence of abundant plagioclase in the sample and the lack of high jadeite content in clinopyroxene clearly refute the postulated eclogite facies conditions. According to the presented photographs clinopyroxene is part of the rock matrix. We therefore suggest that the sample represents a common two-pyroxene granulite, formed at mid- to low-pressure granulite facies conditions of > 700 °C and Madagascar, this interpretation is not justified by the data presented by Ishwar-Kumar et al. (2015).

  15. In vitro biosynthesis, isolation, and identification of predominant metabolites of 2-(4-(2-hydroxyethoxy)-3,5-dimethylphenyl)-5,7-dimethoxyquinazolin-4(3H)-one (RVX-208).

    Science.gov (United States)

    Khmelnitsky, Yuri L; Mozhaev, Vadim V; Cotterill, Ian C; Michels, Peter C; Boudjabi, Sihem; Khlebnikov, Vladimir; Madhava Reddy, M; Wagner, Gregory S; Hansen, Henrik C

    2013-06-01

    The structures of the two predominant metabolites (M4 and M5) of RVX-208, observed both in in vitro human and animal liver microsomal incubations, as well as in plasma from animal in vivo studies, were determined. A panel of biocatalytic systems was tested to identify biocatalysts suitable for milligram scale production of metabolite M4 from RVX-208. Rabbit liver S9 fraction was selected as the most suitable system, primarily based on pragmatic metrics such as catalyst cost and estimated yield of M4 (∼55%). Glucuronidation of RVX-208 catalyzed by rabbit liver S9 fraction was optimized to produce M4 in amounts sufficient for structural characterization. Structural studies using LC/MS/MS analysis and (1)H NMR spectroscopy showed the formation of a glycosidic bond between the primary hydroxyl group of RVX-208 and glucuronic acid. NMR results suggested that the glycosidic bond has the β-anomeric configuration. A synthetic sample of M4 confirmed the proposed structure. Metabolite M5, hypothesized to be the carboxylate of RVX-208, was prepared using human liver microsomes, purified by HPLC, and characterized by LC/MS/MS and (1)H NMR. The structure was confirmed by comparison to a synthetic sample. Both samples confirmed M5 as a product of oxidation of primary hydroxyl group of RVX-208 to carboxylic acid. Copyright © 2013 Elsevier Masson SAS. All rights reserved.

  16. Two populations of double minute chromosomes harbor distinct amplicons, the MYC locus at 8q24.2 and a 0.43-Mb region at 14q24.1, in the SW613-S human carcinoma cell line.

    Science.gov (United States)

    Guillaud-Bataille, M; Brison, O; Danglot, G; Lavialle, C; Raynal, B; Lazar, V; Dessen, P; Bernheim, A

    2009-01-01

    High-level amplifications observed in tumor cells are usually indicative of genes involved in oncogenesis. We report here a high resolution characterization of a new amplified region in the SW613-S carcinoma cell line. This cell line contains tumorigenic cells displaying high-level MYC amplification in the form of double minutes (DM(+) cells) and non tumorigenic cells exhibiting low-level MYC amplification in the form of homogeneously staining regions (DM(-) cells). Both cell types were studied at genomic and functional levels. The DM(+) cells display a second amplification, corresponding to the 14q24.1 region, in a distinct population of DMs. The 0.43-Mb amplified and overexpressed region contains the PLEK2, PIGH, ARG2, VTI1B, RDH11, and ZFYVE26 genes. Both amplicons were stably maintained upon in vitro and in vivo propagation. However, the 14q24.1 amplicon was not found in cells with high-level MYC amplification in the form of HSRs, either obtained after spontaneous integration of endogenous DM MYC copies or after transfection of DM(-) cells with a MYC gene expression vector. These HSR-bearing cells are highly tumorigenic. The 14q24.1 amplification may not play a role in malignancy per se but might contribute to maintaining the amplification in the form of DMs. Copyright 2009 S. Karger AG, Basel.

  17. A multi-ethnic genome-wide association study identifies novel loci for non-syndromic cleft lip with or without cleft palate on 2p24.2, 17q23 and 19q13

    DEFF Research Database (Denmark)

    Leslie, Elizabeth J; Carlson, Jenna C; Shaffer, John R

    2016-01-01

    Orofacial clefts (OFCs), which include non-syndromic cleft lip with or without cleft palate (CL/P), are among the most common birth defects in humans, affecting approximately 1 in 700 newborns. CL/P is phenotypically heterogeneous and has a complex etiology caused by genetic and environmental fac...

  18. Dimension of the SLE Light Cone, the SLE Fan, and SLE_κ(ρ) for κ \\in (0,4) and ρ \\in \\big[{κ/2}-4,-2\\big

    Science.gov (United States)

    Miller, Jason

    2018-02-01

    Suppose that h is a Gaussian free field (GFF) on a planar domain. Fix {κ \\in (0,4)} . The {SLE_κ} light cone L {(θ)} of h with opening angle {θ \\in [0,π]} is the set of points reachable from a given boundary point by angle-varying flow lines of the (formal) vector field {e^{ih/χ}} , {χ = {2}/{√{κ}} - {√{κ}}/{2}} , with angles in [-{θ}/{2},{θ}/{2}]. We derive the Hausdorff dimension of L {(θ)} . If {θ =0} then L {(θ)} is an ordinary {SLE_{κ}} curve (with {κ 4} ). In these extremes, this leads to a new proof of the Hausdorff dimension formula for {SLE} . We also consider {SLE_κ(ρ)} processes, which were originally only defined for {ρ > - 2} , but which can also be defined for {ρ ≤ -2} using Lévy compensation. The range of an {SLE_κ(ρ)} is qualitatively different when {ρ ≤ -2} . In particular, these curves are self-intersecting for {κ fan is the same as that of ordinary {SLE_κ}.

  19. Comida ritual em festas de Tambor de Mina no Maranhão (Ritual food in Maranhão’s Tambor De Mina festivities - DOI: 10.5752/P.2175-5841.2011v9n21p242

    Directory of Open Access Journals (Sweden)

    Sérgio Figueiredo Ferretti

    2011-07-01

    Full Text Available Resumo Tambor de Mina é o nome da religião afro-brasileira no Maranhão e na Amazônia estabelecida a partir de São Luís desde meados do século XIX. Existem duas casas fundadas por africanos que se continuam: a Casa das Minas Jeje, de origem daomeana e a Casa de Nagô, iorubana de onde derivam a maioria dos terreiros de Mina recentes e atuantes. Trata-se de religião muito ritualizada e discreta, envolvida em segredos e mistérios cuja mitologia é pouco comentada e os rituais muito desenvolvidos. As religiões afro-brasileiras se caracterizam pela realização de festas com transe, danças e comidas que atraem muitos participantes. A comida é bastante para oferecer a todos e distribuir as sobras. A fartura nas festas maiores constitui um dos elementos de prestígio das casas. O texto baseia-se em entrevistas com líderes de um terreiro antigo e de duas casas recentes, sobre comida de santo nas festas. Na linguagem de Mauss o sacrifício constitui obrigação que estabelece uma comunicação entre o mundo sagrado e o profano. O preparo e o consumo da comida de santo permitem conhecer aspectos do sincretismo e dos simbolismos nos rituais. Palavras-chave: Religiões afro-brasileiras; comida de santo; sincretismo; festas; ritual.   Abstract Tambor de Mina is the name of the Afro-Brazilian religion in Maranhão and Amazon established in São Luís (capital of Maranhão state since the mid-nineteenth century. There are two matrix-houses founded by Africans: Casa das Minas Jeje, a Dahomean origin house and Casa de Nagô, originally Yoruba and from which most of the Tambor de Mina's houses come from. It is a very ritualized and discrete religion, involved in secrets and mysteries whose mythology is not frequently commented upon and its rituals are highly developed. Afro-Brazilian religions are characterized by the performance of parties with trance, dance and food which attract many participants.  Food is enough to be offered to everyone and have the remains distributed. The abundance of food during the bigger festivities constitutes a prestige element to the houses. According to Mauss, sacrifice is an obligation that establishes communication between sacred and profane. The preparation and consumption of holy feast food allow us to know aspects of syncretism and symbolisms in rituals Keywords: Afro Brazilian religions; holy feast food; syncretism; festivals; ritual.

  20. [Results of a regional survey on the treatment of rhizomelic pseudopolyarthritis and temporal arteritis. Apropos of 242 cases treated by various modalities with synthetic antimalarials, corticoids and non-steroidal anti-inflammatory agents].

    Science.gov (United States)

    David-Chaussé, J; Dehais, J; Leman, A

    1983-01-01

    The authors report the results of a retrospective therapeutic survey concerning 176 cases of rhizomelic pseudopolyarthritis (RPP) and 66 cases of temporal arteritis (TA). Of 128 cases of RPP treated initially by synthetic anti-malarials (SAM) and non-steroidal anti-inflammatory agents (NSAI), 66 were followed up until cure which was obtained after a mean of 23 months and 3 subsequently received brief steroid therapy. 45 cases of RPP were treated initially with corticosteroids. They were generally associated with SAM which enabled early weaning of the steroids, towards the 8 th month, or at least reducing the dose. Cure was obtained within 24 months. Three patients were treated by NSAI and gold therapy. After cure, 5 cases of recurrence and 1 case of TA were observed. 40 cases of TA were initially treated with SAM and NSAI. Twenty cures were obtained within a mean of 28 months. 4 patients later received brief corticosteroid therapy because of an extension of the signs, including two cases of ocular manifestations with a resolving course. Of 25 cases of TA initially treated with steroids, 20 received SAM in combination, or in relay which enabled either steroids, weaning towards the 14th month or a reduction in the dose of steroids. Cure was obtained in an average of 35 months. One case of impaired visual acuity occurred during corticosteroid treatment. Immunosuppressants were used in one patient. No cases of recurrence were observed. Iatrogenic complications with SAM were rare, generally benign and reversible, in contrast to those associated with corticosteroid therapy.(ABSTRACT TRUNCATED AT 250 WORDS)

  1. ORF Alignment: NC_003070 [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available LLSAKRTRRTTRTEYIISMDA 60 ... Query: 242 GSYNIAQITYELNVLGTRGPRRMHCIMNSIPISSLEPGGSVPNQ...PEKLVPAPYSLDDXXX 301 ... GSYNIAQITYELNVLGTRGPRRMHCIMNSIPISSLEPGGSVPNQPEKLVPAPYSLDD ... Sbjct: 121 GSYNIAQITYELNVLGTRGPRRMHC

  2. ORF Alignment: NC_003074 [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available : 242 FTYALLRFSTLLKESYQSDVFSIGGRSMYLQVFPNGRNLSKGKAMSLYLNINDKFKPFEM 301 ... FTYALLRFSTLLKESYQSDVFSIGGR...SMYLQVFPNGRNLSKGKAMSLYLNINDKFKPFEM Sbjct: 1 ... FTYALLRFSTLLKESYQSDVFSIGGRSMYLQVFPNGRNLSKGKAMSLYLNINDKFKPFEM

  3. Computer-assisted nuclear fuel manufacture

    International Nuclear Information System (INIS)

    Maloney, J.P.; Schaumann, S.M.; Stone, E.

    1976-01-01

    At the ERDA Savannah River Plant, a process monitor, which incorporates an online digital computer, assists in manufacturing fuel elements used to produce nuclides such as plutonium, tritium, and californium in the plant's nuclear reactors. Also, inventory functions assist in safeguarding fissile material and protecting against accidental nuclear criticality. Terminals at strategic locations throughout the process area enable production operators to send and receive instructions and information on each manufacturing step

  4. Computer-assisted nuclear fuel manufacture

    International Nuclear Information System (INIS)

    Maloney, J.P.; Schaumann, C.M.; Stone, E.

    1976-06-01

    At the ERDA Savannah River Plant, a process monitor, which incorporates an online digital computer, assists in manufacturing fuel elements used to produce nuclides such as plutonium, tritium, and californium in the plant's nuclear reactors. Also, inventory functions assist in safeguarding fissile material and protecting against accidental nuclear criticality. Terminals at strategic locations throughout the process area enable production operators to send and receive instructions and information on each manufacturing step. 11 fig

  5. Heavy ion tests on programmable VLSI

    International Nuclear Information System (INIS)

    Provost-Grellier, A.

    1989-11-01

    The radiation from space environment induces operation damages in onboard computers systems. The definition of a strategy, for the Very Large Scale Integrated Circuitry (VLSI) qualification and choice, is needed. The 'upset' phenomena is known to be the most critical integrated circuit radiation effect. The strategies for testing integrated circuits are reviewed. A method and a test device were developed and applied to space applications candidate circuits. Cyclotron, synchrotron and Californium source experiments were carried out [fr

  6. Charge breeding of radioactive isotopes at the CARIBU facility with an electron beam ion source

    Science.gov (United States)

    Vondrasek, R. C.; Dickerson, C. A.; Hendricks, M.; Ostroumov, P.; Pardo, R.; Savard, G.; Scott, R.; Zinkann, G.

    2018-05-01

    An Electron Beam Ion Source Charge Breeder (EBIS-CB) has been developed at Argonne National Laboratory as part of the californium rare ion breeder upgrade. For the past year, the EBIS-CB has been undergoing commissioning as part of the ATLAS accelerator complex. It has delivered both stable and radioactive beams with A/Q 18% into a single charge state. The operation of this device, challenges during the commissioning phase, and future improvements will be discussed.

  7. Solid-State Neutron Multiplicity Counting System Using Commercial Off-the-Shelf Semiconductor Detectors

    Energy Technology Data Exchange (ETDEWEB)

    Rozhdestvenskyy, S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-08-09

    This work iterates on the first demonstration of a solid-state neutron multiplicity counting system developed at Lawrence Livermore National Laboratory by using commercial off-the-shelf detectors. The system was demonstrated to determine the mass of a californium-252 neutron source within 20% error requiring only one-hour measurement time with 20 cm2 of active detector area.

  8. Safety analysis report for packaging: neutron shipping cask, model 0.5T

    International Nuclear Information System (INIS)

    Peterson, R.T.

    1976-01-01

    The Safety Analysis Report for Packaging demonstrates that the neutron shipping cask can safely transport, in solid or powder form, all isotopes of uranium, plutonium, americium, curium, berkelium, californium, einsteinium, and fermium. The shipping cask and its contents are described. It also evaluates transport conditions, structural parameters (e.g., load resistance, pressure and impact effects, lifting and tiedown devices), and shielding. Finally, it discusses compliance with Chapter 0529 of the Energy Research and Development Administration Manual

  9. Directed evolution of the periodic table: probing the electronic structure of late actinides.

    Science.gov (United States)

    Marsh, M L; Albrecht-Schmitt, T E

    2017-07-25

    Recent investigations of the coordination chemistry and physical properties of berkelium (Z = 97) and californium (Z = 98) have revealed fundamental differences between post-curium elements and lighter members of the actinide series. This review highlights these developments and chronicles key findings and concepts from the last half-century that have helped usher in a new understanding of the evolution of electronic structure in the periodic table.

  10. NWIS casting measurements taken during demonstrations to Russian visitors

    International Nuclear Information System (INIS)

    Mullens, J.A.; Valentine, T.E.; Mihalczo, J.T.

    1998-01-01

    This report describes a set of NWIS measurements made during demonstrations to Russian visitors on August 28, 1997. These measurements will be given to the Russian visitors from Arzamus-16 as part of their NWIS training (part of a DOE laboratory-to-laboratory exchange program). These measurements are made on standard highly enriched Uranium annular castings (as used for storage). Associated NWIS calibration runs were made in air (no casting, just the NWIS Californium source and detectors)

  11. Properties of neutron sources

    International Nuclear Information System (INIS)

    1987-03-01

    The Conference presentations were divided into sessions devoted to the following topics: white neutron sources, primarily pulsed (6 papers); fast neutron fields (5 papers); Californium-252 prompt fission neutron spectra (14 papers); monoenergetic sources and filtered beams (11 papers); 14 MeV neutron sources (10 papers); selected special application (one paper); and a general interest session (4 papers). Individual abstracts were prepared separately for the papers

  12. Health physics aspects of 252Cf

    International Nuclear Information System (INIS)

    Bhagwat, A.M.

    1974-01-01

    After briefly describing the methods of production, radioactive, chemical and biological properties of californium-252, its health physics aspects are reviewed in detail. Its external and internal radiation hazards can be minimised through control of radiation and contamination and proper shield design. Use of various shielding materials is evaluated. The following aspects are also discussed : (1) radiation detectors for neutrons and gamma radiation (2) personnel monitoring techniques (3) bioassay and (4) storage and transportation. (M.G.B.)

  13. Definitive Brachytherapy for Kaposi's Sarcoma

    International Nuclear Information System (INIS)

    Williams, A.; Ezzell, G.; Zalupski, M.; Fontanesi, J.

    1996-01-01

    Purpose: To assess the efficacy and possible complications in patients diagnosed with Kaposi's sarcoma and treated with definitive brachytherapy. Methods and Materials: Between January, 1995 and December, 1995, four patients with Kaposi's sarcoma (KS) were treated with brachytherapy. Three patients, all with positive HIV status were treated using Iridium 192 (Ir-192) sources via a high-dose rate remote afterloader. One patient with endemic KS was treated using the application of catheters loaded with Californium 252. Eight sites were treated and included scalp, feet, nose, penis, hand, neck, and back. Dose rate for Ir-192 was 330cGy/fx to a total dose of 990cGy. The Californium was delivered as 100nGy/b.i.d. to a total dose of 900nGy. Follow-up as ranged from 2-6 months. Results: All four patients remain alive. Seven of eight sites have had complete clinical response and each patient has reported durable pain relief that has not subsided through last follow-up of 1/96. Two of eight sites, both treated with surface mold technique with Californium 252 developed moist desquamation. The remaining six sites did not demonstrate significant toxicity. Conclusion: Brachytherapy can offer Kaposi's sarcoma patients results that are equivalent to external beam radiation therapy, with minimal complications, a shorter treatment time and potential cost effectiveness

  14. Dicty_cDB: [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available VF (Link to library) VFC242 (Link to dictyBase) - - - Contig-U16280-1 VFC242F (Link... to Original site) VFC242F 431 - - - - - - Show VFC242 Library VF (Link to library) Clone ID VFC242 (Link to dict...yBase) Atlas ID - NBRP ID - dictyBase ID - Link to Contig Contig-U16280-1 Original site URL http://dict...3( S18663 ) coronin - slime mold (Dictyostelium discoideum) ... 270 1e-71 AY52578...asmic 4.0 %: cytoskeletal 4.0 %: vesicles of secretory system >> prediction for VFC242 is nuc 5' end seq. ID

  15. ORF Alignment: NC_003075 [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available in [Arabidopsis thaliana] ... Length = 242 ... Query: 66 ... PCVIYCHGNSGCRADASEAAIVLLPSNITIFTLDFSGSGLSGGEHV...TLGWNEKDDLKAVV 125 ... PCVIYCHGNSGCRADASEAAIVLLPSNITIFTLDFSGSGLSGGEHVTLGWNEKDDLKAVV Sbjct: 1 ... PCVIYCHGNSGCRADA

  16. The Majority of Library Clients Still Use Person-to-Person Interaction When Asking Reference Questions. A review of: De Groote, Sandra L. “Questions Asked at the Virtual and Physical Health Sciences Reference Desk: How Do They Compare and What Do They Tell Us?” Medical Reference Services Quarterly 24.2 (Summer 2005: 11-23.

    Directory of Open Access Journals (Sweden)

    Suzanne Pamela Lewis

    2006-03-01

    Full Text Available Objective - To identify similarities and difference in the questions asked at the virtual and physical refernece desks of a helath scienmces library, in order to better undertand user needs and highlight areas for service improvement. Also to retrospectively analyze reference statistics collected over the previous six years. Design - Use study; retrospective study of reference statistics for the period July 1997 to June 2003; literature review. Setting - Large academic helath sciences library in the United States. Subjects - All questions asked at the reference and information desks, plus questions submitted to the University-wide virtual reference service and answered by a health sciences librarian, over a period of one month. The questions were asked by faculty, staff, students and members of the public. Methods - A literature review was carried out to examine the types of information/reference questions typically asked in health sciences libraries both before and after the mass introduction of remote end-user searching of online resources and the establishment of virtual reference services. Next, the reference statistics collected at the University of Illinois at Chicage (UIC Library of the Health Sciences between July 1997 and June 2003 were examined. For most of this period a digital reference service was offered using a listserv address to which patrons would submit email queries. Beginning in March 2003, a formal virtual reference service (chat and email was provided using commercial software. Finally, data was gathered on questions answered by a health sciences librarians, and clients who asked the question, at either the physical or cirtual reference desk, during the month of November 2003 at the UIC Library of the Health Sciences. Library staff completed an online survey form for each question, and if a client asked more than one question, each question was coded individually. Data included: status of client using the service (faculty/staff. undergarduate student, graduate student, non0UIC, unknown; mode of submission (email, chat, phone, in person; and type of question asked (directional, ready reference, in-depth/mediated, instructional, technical, accounts/status and other. In subsequent analysis, the original seven types of questions were further broken down into 19 categories. Main results - It was not possible to undertake a meta-analysis or systematic review of the studies identified in the literature review because of differences in time frames, settings and the categories used to code reference questions. However the following trends emerged: directional questions accounted for between 30 and 35% of questions asked at both the physical and virtual reference desks; the remainder of questions were generally about known item searched, library policies and services, research, dadabase use and quick reference. The statistics collected at UIC Library of the Health Sciences over the period July 1997 to June 2003 were analyzed. Coded reference questions fell into one of four categories; ready reference, in-depth reference, mediated searched and digital reference. There was a noticeable drop in the number of reference questions received in 1999/2000 which reflects trends reported in some of the studies identified in the literature review. The number of mediated searches decreased from 154 in 1997-98 to 4 in 2002/2003, but the number of digital reference questions increased from 0 to 508 in the same period. Statistics were collected over the month of November 2003 for 939 questions asked at the reference and information desks which included: 38 email; 48 chat; 156 phone; and 697 in person. The major findings were as follows: - appoximately 55% of questions were reference questions (33.5% ready reference, 9.7% in-depth/mediated, 9.7% instructional; 30% were directional; and 10% were technical; it is not stated what the remaining 5% of questions were; - library clients who asked the questions comprised graduate students (26%, faculty (24%, undergraduate students (24% and non-UIC patrons (22%; - all groups were most likely to ask their reference questions in person; - graduate students were the largest group of email reference (34%, undergraduates were the largest group to use chat (35% and faculty/staff were the largest group to use the telephone (39%; - 28% of the questions were answered from the library's staff's general knowledge of the library; 22% using the online catalogue or electronic journals list; 22% by referrning the patron to, or using an online database or resource; 13% by referring the patron to another department in the library (such as circulation; 7% by consulting another individual; and 5% by using print resources. Conclusion - The results of the three parts of this study - literature review, study of 1997-2003 statistics, and in-depth collection of statistics for November 2003 - are difficult to compare with each other. However, the general trend emerging from the results is that some kinds of questions asked by health sciences library clients have remained very much the same regardless of the rise of remote end-user searching and the mode of transmission of the questions. These include questions about library policies and services, journal and book holdings, database searching and instructional support. Questions about citation verification and consumer health appear to be decreasing while technical questions and questions about accessing remote databases and online journals are increasing. The majority of reference questions are still asked in person.

  17. Retraction notice to “Methylation of apoptosis related genes in the pathogenesis and prognosis of prostate cancer” [Cancer Lett. 242 (2) (2006) 222–230]. Makoto Suzuki, Hisayuki Shigematsu, Narayan Shivapurkar, Jyotsna Reddy, Kuniharu Miyajima, Takao Takahashi, Adi F. Gazdar, Eugene P. Frenke.

    Science.gov (United States)

    2015-04-28

    Available online . This article has been retracted: please see Elsevier Policy on Article Withdrawal (http://www.elsevier.com/locate/withdrawalpolicy). This article has been retracted at the request of the first author, who accepts responsibility. Following an internal review at the UT Southwestern Medical Center in Dallas, evidence has been found of improper manipulation and duplication of Figure 1 in this article.

  18. Determination of the relative power density distribution in a heterogeneous reactor from the results of measurements of the reactivity effects and the neutron importance function

    International Nuclear Information System (INIS)

    Bobrov, A. A.; Glushkov, E. S.; Zimin, A. A.; Kapitonova, A. V.; Kompaniets, G. V.; Nosov, V. I.; Petrushenko, R. P.; Smirnov, O. N.

    2012-01-01

    A method for experimental determination of the relative power density distribution in a heterogeneous reactor based on measurements of fuel reactivity effects and importance of neutrons from a californium source is proposed. The method was perfected on two critical assembly configurations at the NARCISS facility of the Kurchatov Institute, which simulated a small-size heterogeneous nuclear reactor. The neutron importance measurements were performed on subcritical and critical assemblies. It is shown that, along with traditionally used activation methods, the developed method can be applied to experimental studies of special features of the power density distribution in critical assemblies and reactors.

  19. Nuclear assay of coal. Volume 1. Coal composition by prompt neutron activation analysis: basic experiments. Final report

    International Nuclear Information System (INIS)

    Reynolds, G.; Bozorganesh, H.; Elias, E.; Gozani, T.; Maung, T.; Orphan, V.

    1979-01-01

    Using californium-252 as a source of exciting neutrons, prompt gamma photons emitted by elemental nuclei in the coal have been measured using several detectors, including sodium--iodide and germanium--lithium. Several coal types, including bituminous, subbituminous lignite and anthracite were crushed to various top sizes and analyzed carefully be traditional ASTM wet chemistry techniques at two or three different laboratories. The elements (sulfur, hydrogen, carbon, aluminum, silicon, iron, calcium, sodium, nitrogen, and chlorine) were determined by prompt neutron activations and the quantities compared with those of the wet chemical analyses

  20. PROCEEDINGS OF THE SYMPOSIUM COMMEMORATING THE 25th ANNIVERSARY OF ELEMENTS 97 and 98 HELD ON JAN. 20, 1975

    Energy Technology Data Exchange (ETDEWEB)

    Seaborg, Glenn T.; Street Jr., Kenneth; Thompson, Stanley G.; Ghiorso, Albert

    1976-07-01

    This volume includes the talks given on January 20, 1975, at a symposium in Berkeley on the occasion of the celebration of the 25th anniversary of the discovery of berkelium and californium. Talks were given at this symposium by the four people involved in the discovery of these elements and by a number of people who have made significant contributions in the intervening years to the investigation of their nuclear and chemical properties. The papers are being published here, without editing, in the form in which they were submitted by the authors in the months following the anniversary symposium, and they reflect rather faithfully the remarks made on that occasion.

  1. Radiological safety considerations in the design and operation of the ORNL Transuranium Research Laboratory (TRL)

    International Nuclear Information System (INIS)

    Haynes, C.E.

    1976-01-01

    The Transuranium Research Laboratory (TRL) is the central facility at Oak Ridge National Laboratory (ORNL) for chemical and physical research involving transuranium elements. Transuranium Research Laboratory investigations are about equally divided between studies of inorganic and structural chemistry of the heavy elements and nuclear structure and properties of their isotopes. Elements studied include neptunium, plutonium, americium, curium, berkelium, californium, and einsteinium, each in microgram-to-gram quantities depending upon availability and experimental requirements. This paper describes an eight-step safety procedure followed in planning and approving individual research projects. This procedure should provide an optimum margin of safety and should permit the accomplishment of successful research

  2. Neutron crosstalk between liquid scintillators

    Energy Technology Data Exchange (ETDEWEB)

    Verbeke, J.M., E-mail: verbeke2@llnl.gov; Prasad, M.K., E-mail: prasad1@llnl.gov; Snyderman, N.J., E-mail: snyderman1@llnl.gov

    2015-09-11

    A method is proposed to quantify the fractions of neutrons scattering between liquid scintillators. Using a spontaneous fission source, this method can be utilized to quickly characterize an array of liquid scintillators in terms of crosstalk. The point model theory due to Feynman is corrected to account for these multiple scatterings. Using spectral information measured by the liquid scintillators, fractions of multiple scattering can be estimated, and mass reconstruction of fissile materials under investigation can be improved. Monte Carlo simulations of mono-energetic neutron sources were performed to estimate neutron crosstalk. A californium source in an array of liquid scintillators was modeled to illustrate the improvement of the mass reconstruction.

  3. Method for measuring multiple scattering corrections between liquid scintillators

    Energy Technology Data Exchange (ETDEWEB)

    Verbeke, J.M., E-mail: verbeke2@llnl.gov; Glenn, A.M., E-mail: glenn22@llnl.gov; Keefer, G.J., E-mail: keefer1@llnl.gov; Wurtz, R.E., E-mail: wurtz1@llnl.gov

    2016-07-21

    A time-of-flight method is proposed to experimentally quantify the fractions of neutrons scattering between scintillators. An array of scintillators is characterized in terms of crosstalk with this method by measuring a californium source, for different neutron energy thresholds. The spectral information recorded by the scintillators can be used to estimate the fractions of neutrons multiple scattering. With the help of a correction to Feynman's point model theory to account for multiple scattering, these fractions can in turn improve the mass reconstruction of fissile materials under investigation.

  4. Neutron crosstalk between liquid scintillators

    International Nuclear Information System (INIS)

    Verbeke, J.M.; Prasad, M.K.; Snyderman, N.J.

    2015-01-01

    A method is proposed to quantify the fractions of neutrons scattering between liquid scintillators. Using a spontaneous fission source, this method can be utilized to quickly characterize an array of liquid scintillators in terms of crosstalk. The point model theory due to Feynman is corrected to account for these multiple scatterings. Using spectral information measured by the liquid scintillators, fractions of multiple scattering can be estimated, and mass reconstruction of fissile materials under investigation can be improved. Monte Carlo simulations of mono-energetic neutron sources were performed to estimate neutron crosstalk. A californium source in an array of liquid scintillators was modeled to illustrate the improvement of the mass reconstruction

  5. Beam test of a grid-less multi-harmonic buncher

    International Nuclear Information System (INIS)

    Ostroumov, P.N.; Aseev, V.N.; Barcikowski, A.; Clifft, B.; Pardo, R.; Sharamentov, S.I.; Sengupta, M.

    2008-01-01

    The Argonne Tandem Linear Accelerator System (ATLAS) is the first superconducting heavy-ion linac in the world. Currently ATLAS is being upgraded with the Californium Rare Ion Breeder Upgrade (CARIBU). The latter is a funded project to expand the range of shortlived, neutron-rich rare isotope beams available for nuclear physics research at ATLAS. To avoid beam losses associated with the existing gridded multi-harmonic buncher (MHB), we have developed and built a grid-less four-harmonic buncher with fundamental frequency of 12.125 MHz. In this paper, we report the results of the MHB commissioning and ATLAS beam performance with the new buncher.

  6. Radiation protection data sheet. Radiation protection data sheets for the use of radionuclides in unsealed sources

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    These radiation protection data sheet are devoted to responsible persons and employees of various laboratories or medical, pharmaceutical, university and industrial departments where radionuclides are handled as well as all the persons who attend to satisfy in this field. They contain the essential radiation protection data for the use of unsealed sources: physical characteristics, risk assessment, administrative procedures, recommendations, regulations and bibliography. This new series includes the following radionuclides: californium 252, curium 244, gallium 67, indium 113m, plutonium 238, plutonium 239, polonium 210, potassium 42, radium 226, thorium 232, uranium 238 and zinc 65. (O.M.)

  7. Development of a transportable neutron radiography system for non-destructive tests application

    International Nuclear Information System (INIS)

    Silva, Ademir X. da; Crispim, Verginia R.

    1999-01-01

    This paper presents a study of a transportable neutron radiography system utilizing californium-252. Studies about moderation, collimation and shielding are showed. A Monte Carlo Code, MCNP3b, has been used to obtain a maximum and more homogeneous thermal neutron flux in the collimator outlet next to the image plain, and an adequate radiation shielding to attend radiological protection rules. With the presented collimator, it was possible to obtain for the thermal neutron flux, at the collimator outlet and next to the image plain, a L/D ratio 7,5, for neutron flux up to 6 X 10 -6 cm -2 .s -1 per neutron source. (author)

  8. Composition containing transuranic elements for use in the homeopathic treatment of aids

    International Nuclear Information System (INIS)

    Lustig, D.

    1996-01-01

    A homeopathic remedy consisting of a composition containing one or more transuranic elements, particularly plutonium, for preventing and treating acquired immunodeficiency syndrome (AIDS) in humans, as well as seropositivity for human immunodeficiency virus (HIV). Said composition is characterized in that it uses any chemical or isotopic form of one or more transuranic elements (neptunium, plutonium, americium, curium, berkelium, californium or einsteinium), particularly plutonium, said form being diluted and dynamized according to conventional homeopathic methods, particularly the so-called Hahnemann and Korsakov methods, and provided preferably but not exclusively in the form of lactose and/or saccharose globules or granules impregnated with the active principle of said composition. (author)

  9. Determination of alpha activity and fissile mass content in solid waste by systems using neutron interrogation

    International Nuclear Information System (INIS)

    Romeyer Dherbey, J.; Lacruche, G.; Berne, R.; Auge, J.; Martin Deidier, L.; Butez, M.

    1990-01-01

    The Quantitative control (determination of heavy nuclides and alpha activity) of alpha radioactive wastes is necessary, particularly to determine if the waste is in accordance with the surface storage limits. In order to reduce the uncertainty on the alpha activity resulting from unknown isotopic composition, inhomogeneity of heavy nuclides in the matrix, combination of several methods is necessary. In the paper we present the Cadarache development work in the NDA of solid waste using the Californium shuffler, 14 Mev neutron generator, and also passive techniques such as neutron emission measurement and gamma spectrometry. Experimental systems combining active and passive methods are presented (COSAC, BANCO, DANAIDE, PROMETHEE)

  10. Actinides

    International Nuclear Information System (INIS)

    Martinot, L.; Fuger, J.

    1985-01-01

    The oxidation behavior of the actinides is explained on the basis of their electronic structure. The actinide elements, actinium, thorium, protactinium, uranium, neptunium, plutonium, americium, curium, berkelium, californium, einsteinium, fermium, mendelevium, nobelium, and laurencium are included. For all except the last three elements, the points of discussion are oxidation states, Gibbs energies and potentials, and potential diagram for the element in acid solution; and thermodynamic properties of these same elements are tabulated. References are cited following discussion of each element with a total of 97 references being cited. 13 tables

  11. Safety analysis report for packaging: neutron shipping cask, model 4T

    International Nuclear Information System (INIS)

    Peterson, R.T.

    1977-01-01

    This Safety Analysis Report for Packaging demonstrates that the neutron shipping cask can safely transport, in solid or powder form, all isotopes of uranium, plutonium, americium, curium, berkelium, californium, einsteinium, and fermium. The cask and its contents are described. It also evaluates transport conditions, structural parameters (e.g., load resistance, pressure and impact effects, lifting and tiedown devices), and shielding. Finally, it discusses compliance with Chapter 0529 of the Energy Research and Development Administration Manual, Safety Standards for the Packaging of Fissile and Other Radioactive Materials

  12. TOWARD AN IMPROVED UNDERSTANDING OF STRUCTURE AND MAGNETISM IN NEPTUNIUM AND PLUTONIUM PHOSPHONATES AND SULFONATES

    Energy Technology Data Exchange (ETDEWEB)

    Albrecht-Schmitt, Thomas

    2012-03-01

    This grant supported the exploratory synthesis of new actinide materials with all of the actinides from thorium to californium with the exceptions of protactinium and berkelium. We developed detailed structure-property relationships that allowed for the identification of novel materials with selective ion-exchange, selective oxidation, and long-range magnetic ordering. We found novel bonding motifs and identified periodic trends across the actinide series. We identified structural building units that would lead to desired structural features and novel topologies. We also characterized many different spectroscopic trends across the actinide series. The grant support the preparation of approximately 1200 new compounds all of which were structurally characterized.

  13. Citric complexes of trivalent cerium and berkelium

    International Nuclear Information System (INIS)

    Boulhassa, S.

    1977-01-01

    The extraction by thenoyltrifluoroacetone (TTA) in benzene of trivalent cerium, berkelium and californium, at the indicator scale, hydrolysis and complexation by citric acid of these cations are studied. The radionuclides used were 144 Ce, 249 Bk and 249 Cf respectively γ, β and α emitters. The solvent extraction technique of the elements by TTA in benzene from a perchloric medium at the ionic stength 0.1 was employed. The distribution coefficients D were measured by the γ, β or α radiometry. Cerium and berkelium, which have a comparable redox behavior, show in solution a relatively stable valency IV. Therefore the study by solvent extraction of their trivalent form required the standing up of complete reducing conditions of these elements and their stabilization in solution at the valency III. The thermodynamic data obtained for berkelium and californium contribute to understand the chemistry of these elements and permit to complete the third 'tetrad branch' of 5f elements from Cm 3+ to Es 3+ . This tetrad effect is a manifestation of thermodynamic consequence of the 'nephelauxetic effect'. As for Ce(III), the data confirm the pronounced acid property and may be show no neglected ligand effect for f 1 configuration [fr

  14. Radioactive materials production

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The Radiochemical Processing Plant (RPP) at ORNL has served as the national repository and distribution center for 233 U for > 20 years. Several hundred kilograms of uranium, containing approximately 90 to 98% 233 U, are stored there in the form of metal, oxides, and nitrate solutions. All of these uranium materials contain small, but significant, concentrations of 232 U, ranging from 2 to 225 ppm. Most of the radioactivity associated with the 233 U comes from the decay daughters of 232 U (74-year half-life). The 252 Cf Industrial Sales/Loan Program involves loans of 252 Cf neutron sources to agencies of the US Government and sales of 252 Cf as the bulk oxide and as palladium-californium alloy pellets and wires. The program has been operated since 1968 in temporary facilities at the Savannah River Laboratory (SRL). The obsolete hot-cell facilities at SRL are now being decommissioned, and the program activities are being transferred to ORNL's Californium Facility in Bldg. 7930, which is managed by the staff of the Transuranium Processing Plant

  15. Radiochemical determination of the neutron capture cross sections of {sup 241}Am irradiated in the JMTR reactor

    Energy Technology Data Exchange (ETDEWEB)

    Shinohara, N.; Hatsukawa, Y.; Hata, K.; Kohno, N. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-03-01

    The thermal neutron capture cross section {sigma}{sub 0} and Resonance integral I{sub 0} of {sup 241}Am leading to the production of {sup 242m}Am and {sup 242g}Am were measured by radiochemical method. The cross sections obtained in this study are {sigma}{sub 0}=60.9 {+-} 2.6 barn, I{sub 0}=213 {+-} 13 barn for {sup 241}Am(n,{gamma}){sup 242m}Am and {sigma}{sub 0}=736 {+-} 31 barn, I{sub 0}=1684 {+-} 92 barn for {sup 241}Am(n,{gamma}){sup 242g}Am. (author)

  16. ORF Alignment: NC_003295 [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available RLPSPTVMRILFFSSHRYDEDAFRAAQARGGHGFELVFQRAHLDVHTAPLAAGFEVV 60 ... Query: 122 AVGMILTLNRRLHRACNRTREXXXXXXXXXXXXXXXKXXXXXXXXXXXXXFARIMA...GFGC 181 ... AVGMILTLNRRLHRACNRTRE ... K ... FARIMA...GFGC Sbjct: 121 AVGMILTLNRRLHRACNRTREGDFSLDGLLGFDLAGKTVGVVGTGQIGQVFARIMAGFGC 180 ... Query: 242

  17. ORF Alignment: NC_003106 [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available PAENLHDCASFIKDYLSSQGFSSQVIEFEKGWPVVISENGNKN 60 ... Query: 122 VNYNLIFTAVPDEESGGDKGSKYLADRYKPDLVLISEPSGSDSINIGEK...GLLQVKLIAKG 181 ... VNYNLIFTAVPDEESGGDKGSKYLADRYKPDLVLISEPSGSDSINIGEKGLLQV...KLIAKG Sbjct: 121 VNYNLIFTAVPDEESGGDKGSKYLADRYKPDLVLISEPSGSDSINIGEKGLLQVKLIAKG 180 ... Query: 242 FXXXXXXXXXXXX

  18. ORF Alignment: NC_006368 [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available LRERTGAGMMECKKFLIATNGDIEQAIIEMRKAGQAKADKKADRVAAEGI 60 ... Query: 122 TTVEQARQELVAKIGENIKLRRLERMHCDGVIGYYLHGSRIG...VMVALKNGSEALAKDIAM 181 ... TTVEQARQELVAKIGENIKLRRLERMHCDGVIGYYLHGSRIGVMVAL...KNGSEALAKDIAM Sbjct: 121 TTVEQARQELVAKIGENIKLRRLERMHCDGVIGYYLHGSRIGVMVALKNGSEALAKDIAM 180 ... Query: 242 QPYVKD

  19. ORF Alignment: ch_oct10_gene_aa_db [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available 122 GLKIVLCIGESLSERETGKTNDVIQKQLTEALKDVSDLSNLVIAYEPIWAIGTGVVATPE 181 ... GLKIVLCIGESLSERETGKTNDVIQKQ...LTEALKDVSDLSNLVIAYEPIWAIGTGVVATPE Sbjct: 121 GLKIVLCIGESLSERETGKTNDVIQKQLTEALKDVSDLSNLVIAYEPIWAIGTGVVATPE 180 ... Query: 242 FAKIIESAQ 250 ... FAKIIESAQ Sbjct: 241 FAKIIESAQ 249

  20. ORF Alignment: Ca19AnnotatedDec2004aaSeq [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available 9.2041 [Candida ... albicans SC5314] ... Length = 135 ... Query: 183 GSLVKVRKEEPLITFGRLAEFCINILNDVI...NHKFPNQGVLSGPFLEEVDTEVYTDYLDYV 242 ... GSLVKVRKEEPLITFGRLAEFCINILNDVINHK...FPNQGVLSGPFLEEVDTEVYTDYLDYV Sbjct: 1 ... GSLVKVRKEEPLITFGRLAEFCINILNDVINHKFPNQGVLSGPFLEEVDTEVYTDYLDYV 60 ... Quer