WorldWideScience

Sample records for experimental nuclear el4

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

    International Nuclear Information System (INIS)

    2006-01-01

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

  2. Study of the origin of elements of the uranium-235 family observed in excess in the vicinity of the experimental nuclear EL4 reactor under dismantling. Lessons got at this day and conclusions

    International Nuclear Information System (INIS)

    2007-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

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

  5. [Experimental study of interleukin-12 gene vaccines in the treatment of low-load malignant lymphoma (EL4)].

    Science.gov (United States)

    Jiang, Q; Da, W; Ou, Y

    2001-11-01

    Two kinds of murine interleukin-12 (mIL-12) fusion gene vaccines were used to treat the murine low-load malignant T cell lymphoma EL4 as minimal residual disease (MRD) model. C57BL/6 synergistical mice were subcutaneously inoculated with 1 x 10(6) wild-type (wt) EL4 tumor cells as low-load lymphoma model treated with two mIL-12 gene vaccines. Package cell line PA317/12 producing mIL-12 retrovirus (RV) was used as in vivo vaccine and EL4 tumor cells transferred with mIL-12 gene as ex vivo vaccine. In both mIL-12 gene vaccine-treated groups, there was no tumor growth in 50% mice 60 days after inoculation. Nine of these no tumor growth mice were re-challenged with 5 x 10(5) wt EL4 cells, and 5 of them survived without tumors in another 60 days. All control mice died with tumors within one month after inoculation. Among those developed tumors in both vaccine-treated groups, the development of tumors was delayed, the survival period prolonged (P EL4 MRD in C57BL/6 mice.

  6. Investigation of the origin of elements of the uranium-235 family noticed in excess around the EL4 experimental nuclear reactor during its dismantling. Site of the Monts d'Arree - Brennilis (29) power plant. Years 2007-2008. Report and appendices with results

    International Nuclear Information System (INIS)

    2009-02-01

    The presence of actinium-227 has been noticed in the Mont d'Arree region (Finistere district) and such a presence in the environment had never been reported before. Thus, a study has been performed to investigate the origin of this element: about 300 samples have been analysed. After an indication of the investigation chronology, the report outlines that there is no relationship between the excess of actinium-227 and land amendment or embankments, that there is no obvious relationship between this presence and radioactive liquid effluents or atmospheric effluents from the Brennilis nuclear site. It shows that there is an obvious relationship with the radiological quality. It states that this excess of actinium 227 is related to the management of rain waters about the Brennilis site. An appendix specifies the location, nature and agenda of samplings (bio-indicators, samplings in sludge, soils, food and tap water, aquatic foams and sediments, ponds, wet lands, and at the vicinity of the power plant channel), presents detailed results obtained by gamma spectrometry, and measurement equipment and methods

  7. Actions needed for RA reactor exploitation - I-IV, Part II, Design project VI-SA 1, Experimental loop for testing the EL-4 reactor fuel elements in the central vertical experimental channel of the RA reactor in Vinca

    International Nuclear Information System (INIS)

    Novakovic, M.

    1961-12-01

    The objective of installing the VISA-1 loop was testing the fuel elements of the EL-4 reactor. The fuel elements planned for testing are natural UO 2 with beryllium cladding, cooled by CO 2 under nominal pressure of 60 at and temperature 600 deg C. central vertical experimental channel of the RA reactor was chosen for installing a test loop cooled by CO 2 . This report contains the detailed design project of the testing loop with the control system and safety analysis of the planned experiment

  8. Experimental nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Dormehl, I C [Nuclear Development Corp. of South Africa (Pty.) Ltd., Pelindaba, Pretoria. Inst. of Life Sciences; Du Plessis, M; Jacobs, D J

    1983-07-01

    Exciting investigative research, widening the dimensions of conventional nuclear medicine, is being conducted in Pretoria where the development and evaluation of new radiopharmaceuticals in particular is attracting international attention. Additional to this, the development of new diagnostic techniques involving sophisticated data processing, is helping to place South Africa firmly in the front line of nuclear medical progress.

  9. Experimental nuclear physics

    Science.gov (United States)

    An earlier study of unusual electromagnetic decays in (sup 86)Zr was extended in order to make comparisons with its isotone (sup 84)Sr and with (sup 84)Zr. The K=14 (t(sub 1/2) = 70 ns) high-spin isomer in (sup 176)W was found to have a 13 percent branch directly to the K=O ground-state band, one of the strongest violations of K-selection rules known. A new program to search for a predicted region of oblate deformation involving neutron deficient isotopes in the Rn/Fr/Ra region was begun. In the area of nuclear astrophysics, as part of a study of the onset of the rp-Process, a set of measurements searching for possible new resonances for (sup 14)O+(alpha) and (sup 17)F+p reactions was completed and a coincidence experiment measuring the (sup 19)F ((sup 3)He,t) (sup 19)Ne(alpha) (sup 15)O and (sup 19)F ((sup 3)He,t) (sup 19)Ne(p) (sup 18)F reactions in order to determine the rates of the (sup 18)F(p,(alpha)) (sup 15)O and (sup 18)F(p,(gamma)) (sup 19)Ne reactions was begun. Experimental measurements of (beta)n(alpha) coincidences from the (sup 15)N(d,p) (sup 16)N((beta)- (nu)) (sup 16)O((alpha)) (sup 12)C reaction have also been completed and are currently being analyzed to determine the rate of the (sup 12)C((alpha),(gamma)) reaction. In the APEX collaboration, we have completed the assembly and testing of two position-sensitive Na barrels which surround the axial silicon detector arrays and serve as the e(sup +) triggers by detecting their back-to-back annihilation quanta were completed. The HI@AGS and RHIC collaborations, construction and implementation activities associated with the space-time-tracker detector and in the design of the central detector for the PHENIX experiment were carried out. Operation of the ESTU tandem accelerator has been reliable, delivering beam on target at terminal voltages as high as 19.3 MV and running for as long as 143 days between tank openings. Fabrication and bench testing of a new negative ion source system have been completed.

  10. [Experimental nuclear physics

    International Nuclear Information System (INIS)

    1992-01-01

    An earlier study of unusual electromagnetic decays in 86 Zr was extended in order to make comparisons with its isotone 84 Sr and with 84 Zr. The K=14 (t 1/2 = 70 ns) high-spin isomer in 176 W was found to have a 13% branch directly to the K=O ground-state band, one of the strongest violations of K-selection rules known. A new program to search for a predicted region of oblate deformation involving neutron deficient isotopes in the Rn/Fr/Ra region was begun. In the area of nuclear astrophysics, as part of a study of the onset of the rp-Process, a set of measurements searching for possible new resonances for 14 O+α and 17 F+p reactions was completed and a coincidence experiment measuring the 19 F( 3 He,t) 19 Ne(α) 15 O and 19 F( 3 He,t) 19 Ne(p) 18 F reactions in order to determine the rates of the 18 F(p,α) 15 O and 18 F(p,γ) 19 Ne reactions was begun. Experimental measurements of βnα coincidences from the 15 N(d,p) 16 N(β - ν) 16 O(α) 12 C reaction have also been completed and are currently being analyzed to determine the rate of the 12 C(α,γ) reaction. In the APEX collaboration, we have completed the assembly and testing of two position-sensitive Na barrels which surround the axial silicon detector arrays and serve as the e + triggers by detecting their back-to-back annihilation quanta were completed. The HI at sign AGS and RHIC collaborations, construction and implementation activities associated with the space-time-tracker detector and in the design of the central detector for the PHENIX experiment were carried out. Operation of the ESTU tandem accelerator has been reliable, delivering beam on target at terminal voltages as high as 19.3 MV and running for as long as 143 days between tank openings. Fabrication and bench testing of a new negative ion source system have been completed

  11. [Experimental nuclear physics

    International Nuclear Information System (INIS)

    1990-04-01

    This report contains brief discussion on the following tapes: giant resonances; nucleus-nucleus reactions; nuclear astrophysics; polarization; fundamental symmetries and interactions; accelerator mass spectrometry; instrumentation; accelerators and in sources; and computer systems

  12. Experimental Aspects of Nuclear Interaction

    Energy Technology Data Exchange (ETDEWEB)

    Slaus, I. [Institute ' ' Rudjer Boskovic' ' , Zagreb, Yugoslavia (Croatia)

    1970-07-15

    1. Introduction; 2. Basic features of nuclear interaction; 3. How accurate is our present knowledge of phase parameters? 4. Experimental problems in N-N scattering studies; 5. N-N potential models; 6. Some open problems in nuclear interaction studies. (author)

  13. Nuclear test experimental science

    International Nuclear Information System (INIS)

    Struble, G.L.; Middleton, C.; Bucciarelli, G.; Carter, J.; Cherniak, J.; Donohue, M.L.; Kirvel, R.D.; MacGregor, P.; Reid, S.

    1989-01-01

    This report discusses research being conducted at Lawrence Livermore Laboratory under the following topics: prompt diagnostics; experimental modeling, design, and analysis; detector development; streak-camera data systems; weapons supporting research

  14. Nuclear test experimental science

    Energy Technology Data Exchange (ETDEWEB)

    Struble, G.L.; Middleton, C.; Bucciarelli, G.; Carter, J.; Cherniak, J.; Donohue, M.L.; Kirvel, R.D.; MacGregor, P.; Reid, S. (eds.)

    1989-01-01

    This report discusses research being conducted at Lawrence Livermore Laboratory under the following topics: prompt diagnostics; experimental modeling, design, and analysis; detector development; streak-camera data systems; weapons supporting research.

  15. Nuclear Test-Experimental Science

    International Nuclear Information System (INIS)

    Struble, G.L.; Donohue, M.L.; Bucciarelli, G.; Hymer, J.D.; Kirvel, R.D.; Middleton, C.; Prono, J.; Reid, S.; Strack, B.

    1988-01-01

    Fiscal year 1988 has been a significant, rewarding, and exciting period for Lawrence Livermore National Laboratory's nuclear testing program. It was significant in that the Laboratory's new director chose to focus strongly on the program's activities and to commit to a revitalized emphasis on testing and the experimental science that underlies it. It was rewarding in that revolutionary new measurement techniques were fielded on recent important and highly complicated underground nuclear tests with truly incredible results. And it was exciting in that the sophisticated and fundamental problems of weapons science that are now being addressed experimentally are yielding new challenges and understanding in ways that stimulate and reward the brightest and best of scientists. During FY88 the program was reorganized to emphasize our commitment to experimental science. The name of the program was changed to reflect this commitment, becoming the Nuclear Test-Experimental Science (NTES) Program

  16. Experimental studies of nuclear astrophysics

    International Nuclear Information System (INIS)

    He Jianjun; Zhou Xiaohong; Zhang Yuhu

    2013-01-01

    Nuclear astrophysics is an interdisciplinary subject combining micro-scale nuclear physics and macro-scale astrophysics. Its main aims are to understand the origin and evolution of the elements in the universe, the time scale of stellar evolution, the stellar environment and sites, the energy generation of stars from thermonuclear processes and its impact on stellar evolution and the mechanisms driving astrophysical phenomena, and the structure and property of compact stars. This paper presents the significance and current research status of nuclear astrophysics; we introduce some fundamental concepts, the nuclear physics input parameters required by certain astrophysics models, and some widely-used experimental approaches in nuclear astrophysics research. The potential and feasibility of research in this field using China’s current and planned large-scale scientific facilities are analyzed briefly. Finally, the prospects of the establishing a deep underground science and engineering laboratory in China are envisaged. (authors)

  17. GRANULOCYTE INFILTRATION AND EXPRESSION OF THE PRO-ANGIOGENIC BV8 PROTEIN IN EXPERIMENTAL EL4 AND LEWIS LUNG CARCINOMA TUMORS.

    Science.gov (United States)

    Jiang, Kan; Kwak, Hyeongil; Tosato, Giovanna

    2013-01-18

    Although Vascular Endothelial Growth Factor (VEGF)-targeted therapies have shown efficacy in the treatment of certain advanced cancers, benefits to patients have been modest, which is attributed to tumor resistance to VEGF neutralization. Recent efforts to identify new targets to inhibit tumor angiogenesis have identified Bv8 (prokineticin 2), a myeloid cell-derived protein that promotes endothelial cell growth and tumor angiogenesis, but many mechanistic aspects of the pro-tumorigenic function of Bv8 are unclear. Here we demonstrate that CD11b+, Ly6C+, Ly6G+ granulocytes are the predominant cell source of Bv8 expression in bone marrow, spleen and in tumor tissues. Using granulocyte-deficient Growth factor independence-1 (Gfi1)-null mutant mice and normal littermates, we found that EL4 lymphoma tumors grow significantly larger in the granulocyte and Bv8-deficient mutant mice in comparison to the normal mice that display abundant tumor-associated granulocytes and Bv8 expression. Conversely, Lewis lung carcinoma (LLC-1) tumors grew to a significantly greater size in the normal mice in comparison to the Gfi1-null mice, but normal granulocyte tumor infiltration was modest. Quantitative analysis of tissue vascularization showed that EL4 and LLC-1 tumors from normal and Gfi1-mutant mice are similarly vascularized. These results confirm the critical contribution of the tumor microenvironment in determining the rate of tumor progression independently of tumor angiogenesis, and reveal some of the complexities of granulocyte and Bv8 functions in modulating tumor growth.

  18. Experimental nuclear explosions and the arms race

    International Nuclear Information System (INIS)

    Lenci, F.

    1989-01-01

    This paper discusses how experimental nuclear explosions have basically three aims: a study of the effects of nuclear weapons; the development of new nuclear weapons; and control of the efficiency and security of nuclear weapons

  19. Role of nuclear factor of activated T-cells and activator protein-1 in the inhibition of interleukin-2 gene transcription by cannabinol in EL4 T-cells.

    Science.gov (United States)

    Yea, S S; Yang, K H; Kaminski, N E

    2000-02-01

    We previously reported that immunosuppressive cannabinoids inhibited interleukin (IL)-2 steady-state mRNA expression and secretion by phorbol-12-myristate-13-acetate plus ionomycin-activated mouse splenocytes and EL4 murine T-cells. Here we show that inhibition of IL-2 production by cannabinol, a modest central nervous system-active cannabinoid, is mediated through the inhibition of IL-2 gene transcription. Moreover, electrophoretic mobility shift assays demonstrated that cannabinol markedly inhibited the DNA binding activity of nuclear factor of activated T-cells (NF-AT) and activator protein-1 (AP-1) in a time- and concentration-dependent manner in activated EL4 cells. The inhibitory effects produced by cannabinol on AP-1 DNA binding were quite transient, showing partial recovery by 240 min after cell activation and no effect on the activity of a reporter gene under the control of AP-1. Conversely, cannabinol-mediated inhibition of NF-AT was robust and sustained as demonstrated by an NF-AT-regulated reporter gene. Collectively, these results suggest that decreased IL-2 production by cannabinol in EL4 cells is due to the inhibition of transcriptional activation of the IL-2 gene and is mediated, at least in part, through a transient inhibition of AP-1 and a sustained inhibition of NF-AT.

  20. Experimental qualification of nuclear components

    Energy Technology Data Exchange (ETDEWEB)

    Alliot, P; Fronte, T; Genty, F [FRAMATOME - Cedex 16, Paris la Defense (France)

    1988-07-01

    In the process of showing the adequacy of the seismic design of French PWR reactor, Fermat has repeatedly used dynamic testing on actual nuclear reactor components both on site and in manufacturing shops. The objective and results of a few representative examples of this on-site experimental verification are presented in this paper: the experimental dynamic analysis of a manipulator crane; the investigation of the seismic behaviour of fuel storage racks equipped with aseismic bearing devices. Difficulties to select satisfactory testing methods are also discussed for the particular case of the electrical cabinets. (author)

  1. Experimental qualification of nuclear components

    International Nuclear Information System (INIS)

    Alliot, P.; Fronte, T.; Genty, F.

    1988-01-01

    In the process of showing the adequacy of the seismic design of French PWR reactor, Fermat has repeatedly used dynamic testing on actual nuclear reactor components both on site and in manufacturing shops. The objective and results of a few representative examples of this on-site experimental verification are presented in this paper: the experimental dynamic analysis of a manipulator crane; the investigation of the seismic behaviour of fuel storage racks equipped with aseismic bearing devices. Difficulties to select satisfactory testing methods are also discussed for the particular case of the electrical cabinets. (author)

  2. Actions needed for RA reactor exploitation - I-IV, Part II, Design project VI-SA 1, Experimental loop for testing the EL-4 reactor fuel elements in the central vertical experimental channel of the RA reactor in Vinca; Radovi za potrebe eksploatacije reaktora RA - I-IV, II Deo, Predprojekat VI-SA 1, Petlja za ispitivanje gorivnih elemenata reaktora EL-4 u centralnom vertikalnom eksperimentalnom kanalu reaktora RA u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Novakovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    The objective of installing the VISA-1 loop was testing the fuel elements of the EL-4 reactor. The fuel elements planned for testing are natural UO{sub 2} with beryllium cladding, cooled by CO{sub 2} under nominal pressure of 60 at and temperature 600 deg C. central vertical experimental channel of the RA reactor was chosen for installing a test loop cooled by CO{sub 2}. This report contains the detailed design project of the testing loop with the control system and safety analysis of the planned experiment.

  3. Experimental nuclear physics in Vietnam - recent status

    International Nuclear Information System (INIS)

    Tran Thanh Minh

    1995-01-01

    Status of research works on experimental nuclear physics in Vietnam is reviewed. Vietnam institutions and main instruments for nuclear research are listed. The results on physics and technology of nuclear reactor, neutron physics, nuclear reactions, radiological safety are mentioned. (N.H.A). 6 tabs, 4 figs

  4. Experimental nuclear physics research in Hungary

    International Nuclear Information System (INIS)

    Koltay, Ede.

    1984-01-01

    The status and recent results of experimental nuclear physics in Hungary is reviewed. The basic nuclear sciences, instrumental background and international cooperation are discussed. Personal problems and the effects of the international scientific deconjuncture are described. The applied nuclear and interdisciplinary researches play an important role in Hungarian nuclear physics. Some problems of cooperation of Hungarian nuclear and other research institutes applying or producing nuclear analytical technology are reviewed. The new instrument, the Debrecen cyclotron under construction gives new possibilities to basic and applied researches. A new field of Hungarian nuclear physics is the fusion and plasma research using tokamak equipment, the main topics of which are plasma diagnostics and fusion control systems. Some practical applications of Hungarian nuclear physical results, e.g. establishment of new analytical techniques like PIXE, RBS, PIGE, ESCA, etc. are summarized. (D.Gy.)

  5. [Experimental nuclear physics]. Final report

    International Nuclear Information System (INIS)

    1991-04-01

    This is the final report of the Nuclear Physics Laboratory of the University of Washington on work supported in part by US Department of Energy contract DE-AC06-81ER40048. It contains chapters on giant dipole resonances in excited nuclei, nucleus-nucleus reactions, astrophysics, polarization in nuclear reactions, fundamental symmetries and interactions, accelerator mass spectrometry (AMS), ultra-relativistic heavy ions, medium energy reactions, work by external users, instrumentation, accelerators and ion sources, and computer systems. An appendix lists Laboratory personnel, a Ph. D. degree granted in the 1990-1991 academic year, and publications. Refs., 41 figs., 7 tabs

  6. [Experimental nuclear physics]. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-04-01

    This is the final report of the Nuclear Physics Laboratory of the University of Washington on work supported in part by US Department of Energy contract DE-AC06-81ER40048. It contains chapters on giant dipole resonances in excited nuclei, nucleus-nucleus reactions, astrophysics, polarization in nuclear reactions, fundamental symmetries and interactions, accelerator mass spectrometry (AMS), ultra-relativistic heavy ions, medium energy reactions, work by external users, instrumentation, accelerators and ion sources, and computer systems. An appendix lists Laboratory personnel, a Ph. D. degree granted in the 1990-1991 academic year, and publications. Refs., 41 figs., 7 tabs.

  7. Experimental techniques in nuclear and particle physics

    International Nuclear Information System (INIS)

    Tavernier, Stefaan

    2010-01-01

    The book is based on a course in nuclear and particle physics that the author has taught over many years to physics students, students in nuclear engineering and students in biomedical engineering. It provides the basic understanding that any student or researcher using such instruments and techniques should have about the subject. After an introduction to the structure of matter at the subatomic scale, it covers the experimental aspects of nuclear and particle physics. Ideally complementing a theoretically-oriented textbook on nuclear physics and/or particle physics, it introduces the reader to the different techniques used in nuclear and particle physics to accelerate particles and to measurement techniques (detectors) in nuclear and particle physics. The main subjects treated are: interactions of subatomic particles in matter; particle accelerators; basics of different types of detectors; and nuclear electronics. The book will be of interest to undergraduates, graduates and researchers in both particle and nuclear physics. For the physicists it is a good introduction to all experimental aspects of nuclear and particle physics. Nuclear engineers will appreciate the nuclear measurement techniques, while biomedical engineers can learn about measuring ionising radiation, the use of accelerators for radiotherapy. What's more, worked examples, end-of-chapter exercises, and appendices with key constants, properties and relationships supplement the textual material. (orig.)

  8. Experimental techniques in nuclear and particle physics

    CERN Document Server

    Tavernier, Stefaan

    2009-01-01

    The book is based on a course in nuclear and particle physics that the author has taught over many years to physics students, students in nuclear engineering and students in biomedical engineering. It provides the basic understanding that any student or researcher using such instruments and techniques should have about the subject. After an introduction to the structure of matter at the subatomic scale, it covers the experimental aspects of nuclear and particle physics. Ideally complementing a theoretically-oriented textbook on nuclear physics and/or particle physics, it introduces the reader to the different techniques used in nuclear and particle physics to accelerate particles and to measurement techniques (detectors) in nuclear and particle physics. The main subjects treated are: interactions of subatomic particles in matter; particle accelerators; basics of different types of detectors; and nuclear electronics. The book will be of interest to undergraduates, graduates and researchers in both particle and...

  9. The experimental nuclear reactor: AQUILON

    International Nuclear Information System (INIS)

    Girard, Y.; Koechlin, J.C.; Moreau, J.M.

    1958-01-01

    'Aquilon' is an experimental reactor specially designed for the neutronic study of heterogeneous multiplying media with solid fuel and liquid moderator. Since this study is in general incompatible with energy production, the power of the reactor has been limited to a minimum so as to be able to obtain a simple and compact structure, easy access, good handling and great flexibility of operation and utilisation. (author) [fr

  10. Research in experimental nuclear physics

    International Nuclear Information System (INIS)

    Moore, C.F.

    1989-09-01

    Our program concentrates on pion physics experimental results obtained using the Energetic Pion Channel and Spectrometer (EPICS), Pion and Particle Physics channel (P 3 ), and the Low Energy Pion physics channel (LEP). These facilities are unique in the world in their intensity and resolution. Two classes of experiments can be done best with this equipment: scattering (elastic and inelastic) and double charge exchange (DCX). Several coincidence experiments are in progress and are discussed in this paper

  11. Experimental grounds for nuclear shape isomerism

    International Nuclear Information System (INIS)

    Makarenko, V.E.

    1995-11-01

    Experimental data on fission isomeric states of actinide nuclei - half lives, energies, quantum numbers, decay branches and spectroscopic properties - are discussed. Quite a few results find their explanation in the framework of nuclear shape isomerism hypothesis being the in-thing for about thirty years. Others seem to be the hints to the quasiparticle nature of fission isomers. The problem could be solved by direct measurement of nuclear spin for isomeric states. (author). 44 refs, 1 tab

  12. Experimental nuclear physics in Vietnam - recent status

    International Nuclear Information System (INIS)

    Tran Thanh Minh

    1995-01-01

    It is really difficult to determine the exact date for the starting of nuclear physics research in Vietnam. Serious research on experimental nuclear physics began only since 1972 with the installation of such nuclear instrument like microtron accelerator, neutron generator, etc. During the past 20 years, hundred of research works have been published in local and foreign scientific journals. In the 5th national conference in Physics held in Hanoi in October 1993, at the Nuclear Physics section, 62 reports were presented reflecting the situation of nuclear physics research in the recent years, especially in the past five years. This review introduces its main results and formulates some perspectives of development in the late nineties in Vietnam. (K.A.). 27 refs., 4 figs., 6 tabs

  13. Experimental Seminar on Nuclear Energy for Teachers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-02-01

    `Experimental Seminar on Nuclear Energy for Teachers` was conducted and sponsored by the Science and Technology Agency. And in order to understand nuclear energy properly through lectures and experiments with good results inclass, the seminar carried out for teachers of high schools and junior high schools by the Nuclear Technology and Education Center (NuTEC), Japan Atomic Energy Research Institute in 1990 FY to 1997 FY. In this report, details of the seminars in the above period are described and No.1 to 17 of Communication Letters of Experimental Seminar on Nuclear Energy` started at 1992 FY are described also. These letters were prepared for attendant follow-up program. And programs of recent seminars, future`s seminars, impressions and comments from attendants, reports from actual classes and others are described in these letters and they are very useful for educational classes on nuclear energy by other teachers. Therefore contents of the letters are listed and easy to refer. A part of this educational task was transferred to the Radiation Application Development Association in 1997 FY and other parts were transferred in 1998 FY. (author)

  14. Experimental energy-dependent nuclear spin distributions

    International Nuclear Information System (INIS)

    Egidy, T. von; Bucurescu, D.

    2009-01-01

    A new method is proposed to determine the energy-dependent spin distribution in experimental nuclear-level schemes. This method compares various experimental and calculated moments in the energy-spin plane to obtain the spin-cutoff parameter σ as a function of mass A and excitation energy using a total of 7202 levels with spin assignment in 227 nuclei between F and Cf. A simple formula, σ 2 =0.391 A 0.675 (E-0.5Pa ' ) 0.312 , is proposed up to about 10 MeV that is in very good agreement with experimental σ values and is applied to improve the systematics of level-density parameters.

  15. Experimental Nuclear Physics Activity in Italy

    Science.gov (United States)

    Chiavassa, E.; de Marco, N.

    2003-04-01

    The experimental Nuclear Physics activity of the Italian researchers is briefly reviewed. The experiments, that are financially supported by the INFN, are done in strict collaboration by more than 500 INFN and University researchers. The experiments cover all the most important field of the modern Nuclear Physics with probes extremely different in energy and interactions. Researches are done in all the four National Laboratories of the INFN even if there is a deeper involvement of the two national laboratories expressly dedicated to Nuclear Physics: the LNL (Laboratorio Nazionale di Legnaro) and LNS (Laboratorio Nazionale del Sud) where nuclear spectroscopy and reaction dynamics are investigated. All the activities with electromagnetic probes develops in abroad laboratories as TJNAF, DESY, MAMI, ESFR and are dedicated to the studies of the spin physics and of the nucleon resonance; hypernuclear and kaon physics is investigated at LNF. A strong community of researchers work in the relativistic and ultra-relativistic heavy ions field in particular at CERN with the SPS Pb beam and in the construction of the ALICE detector for heavy-ion physics at the LHC collider. Experiments of astrophysical interest are done with ions of very low energy; in particular the LUNA accelerator facility at LNGS (Laboratorio Nazionale del Gran Sasso) succeeded measuring cross section at solar energies, below or near the solar Gamow peak. Interdisciplinary researches on anti-hydrogen atom spectroscopy and on measurements of neutron cross sections of interest for ADS development are also supported.

  16. CD4 expression on EL4 cells as an epiphenomenon of retroviral transduction and selection.

    Science.gov (United States)

    Logan, Grant J; Spinoulas, Afroditi; Alexander, Stephen I; Smythe, Jason A; Alexander, Ian E

    2004-04-01

    The EL4 murine tumour cell line, isolated from a chemically induced lymphoma over 50 years ago, has been extensively exploited in immunological research. The conclusions drawn from many of these studies have been based on the presumption that EL4 cells maintain a stable phenotype during experimental manipulation. To the contrary, we have observed 100-fold greater expression of cell surface CD4 (CD4(high)) on a subpopulation of EL4 cells following retroviral transduction and G418 selection when compared with unmodified populations. Although the mechanism responsible for this effect remains to be elucidated, the unexpected expression of CD4, a molecule that functions as both a coreceptor with the T-cell receptor and ligand for the pro-inflammatory cytokine IL-16, has the potential to influence experimental outcomes. Upregulation of CD4 should be excluded when EL4 cells are utilized in experiments requiring a consistent immuno-phenotype.

  17. Nuclear Criticality Experimental Research Center (NCERC) Overview

    Energy Technology Data Exchange (ETDEWEB)

    Goda, Joetta Marie [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Grove, Travis Justin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hayes, David Kirk [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Myers, William L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sanchez, Rene Gerardo [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-03-03

    The mission of the National Criticality Experiments Research Center (NCERC) at the Device Assembly Facility (DAF) is to conduct experiments and training with critical assemblies and fissionable material at or near criticality in order to explore reactivity phenomena, and to operate the assemblies in the regions from subcritical through delayed critical. One critical assembly, Godiva-IV, is designed to operate above prompt critical. The Nuclear Criticality Experimental Research Center (NCERC) is our nation’s only general-purpose critical experiments facility and is only one of a few that remain operational throughout the world. This presentation discusses the history of NCERC, the general activities that makeup work at NCERC, and the various government programs and missions that NCERC supports. Recent activities at NCERC will be reviewed, with a focus on demonstrating how NCERC meets national security mission goals using engineering fundamentals. In particular, there will be a focus on engineering theory and design and applications of engineering fundamentals at NCERC. NCERC activities that relate to engineering education will also be examined.

  18. Modeling a nuclear reactor for experimental purposes

    International Nuclear Information System (INIS)

    Berta, V.T.

    1980-01-01

    The Loss-of-Fluid Test (LOFT) Facility is a scale model of a commercial PWR and is as fully functional and operational as the generic commercial counterpart. LOFT was designed and built for experimental purposes as part of the overall NRC reactor safety research program. The purpose of LOFT is to assess the capability of reactor safety systems to perform their intended functions during occurrences of off-normal conditions in a commercial nuclear reactor. Off-normal conditions arising from large and small break loss-of-coolant accidents (LOCA), operational transients, and anticipated transients without scram (ATWS) were to be investigated. This paper describes the LOFT model of the generic PWR and summarizes the experiments that have been conducted in the context of the significant findings involving the complex transient thermal-hydraulics and the consequent effects on the commercial reactor analytical licensing techniques. Through these techniques the validity of the LOFT model as a scaled counterpart of the generic PWR is shown

  19. Nuclear test-experimental science annual report, Fiscal year 1990

    International Nuclear Information System (INIS)

    Struble, G.L.; Middleton, C.; Anderson, S.E.; Cherniak, J.; Donohue, M.L.; Francke, A.; Hedman, I.; Kirvel, R.D.

    1991-01-01

    Fiscal year 1990 was another year of outstanding accomplishments for the Nuclear Test-Experimental Science (NTES) Program at Lawrence Livermore National Laboratory (LLNL). We continued to make progress to enhance the experimental science in the Weapons Program and to improve the operational efficiency and productivity of the Nuclear Test Program

  20. Experimental test of nuclear magnetization distribution and nuclear structure models

    International Nuclear Information System (INIS)

    Beirsdorfer, P; Crespo-Lopez-Urrutia, J R; Utter, S B.

    1999-01-01

    Models exist that ascribe the nuclear magnetic fields to the presence of a single nucleon whose spin is not neutralized by pairing it up with that of another nucleon; other models assume that the generation of the magnetic field is shared among some or all nucleons throughout the nucleus. All models predict the same magnetic field external to the nucleus since this is an anchor provided by experiments. The models differ, however, in their predictions of the magnetic field arrangement within the nucleus for which no data exist. The only way to distinguish which model gives the correct description of the nucleus would be to use a probe inserted into the nucleus. The goal of our project was to develop exactly such a probe and to use it to measure fundamental nuclear quantities that have eluded experimental scrutiny. The need for accurately knowing such quantities extends far beyond nuclear physics and has ramifications in parity violation experiments on atomic traps and the testing of the standard model in elementary particle physics. Unlike scattering experiments that employ streams of free particles, our technique to probe the internal magnetic field distribution of the nucleus rests on using a single bound electron. Quantum mechanics shows that an electron in the innermost orbital surrounding the nucleus constantly dives into the nucleus and thus samples the fields that exist inside. This sampling of the nucleus usually results in only minute shifts in the electron s average orbital, which would be difficult to detect. By studying two particular energy states of the electron, we can, however, dramatically enhance the effects of the distribution of the magnetic fields in the nucleus. In fact about 2% of the energy difference between the two states, dubbed the hyperfine splitting, is determined by the effects related to the distribution of magnetic fields in the nucleus, A precise measurement of this energy difference (better than 0.01%) would then allow us to place

  1. Decree no. 96-978 from October 31, 1996 giving permission to the French atomic energy Commission (CEA) to create a basic nuclear installation intended to maintain under supervision and in an intermediate dismantling state the old basic nuclear installation no. 28, named Monts d'Arree-EL 4 nuclear power plant (a decommissioned reactor), in the Monts d'Arree site of the Loqueffret town (Finistere, Brittany)

    International Nuclear Information System (INIS)

    Borotra, F.; Lepage, C.

    1996-01-01

    This decree from the French ministry of industry and postal services gives permission to the CEA to create a new basic nuclear installation, named EL 4D, which is devoted to the storage of materials from the partially dismantled Monts d'Arree EL 4 reactor. Thus, the CEA is allowed to carry out confining works on the reactor building with the closure of all apertures with the exception of the personnel entry sieve, on the circuits and equipments of the reactor vessel with the plugging of fuel channels, heavy water, helium and demineralized water pipes and of the heads of control rod drive mechanisms and other channels, and on the primary coolant circuit outside the reactor vessel and the steam generators with the installation of welded hatches. The irradiated fuels building, the solid wastes repository, the ventilation building, the heavy water and helium circuits, the fuel handling systems and the effluents treatment plant will be completely dismantled. The other buildings will be pulled down. The rest of the decree enumerates the general technical and safety prescriptions which have to be followed in order to ensure the protection of the personnel against ionizing radiations and of the environment against radioactive pollution. (J.S.)

  2. Overview on Fusion Nuclear Technology Experimental Testing

    Czech Academy of Sciences Publication Activity Database

    Entler, Slavomír; Kysela, J.

    2016-01-01

    Roč. 2, č. 2 (2016), č. článku 021018. ISSN 2332-8983 Institutional support: RVO:61389021 Keywords : fusion * corrosion * thermohydraulic * LiPb * HHF * ITER Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders

  3. [Experimental nuclear physics]. Annual report 1989

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-04-01

    This is the April 1989 annual report of the Nuclear Physics Labortaory of the University of Washington. It contains chapters on astrophysics, giant resonances, heavy ion induced reactions, fundamental symmetries, polarization in nuclear reactions, medium energy reactions, accelerator mass spectrometry (AMS), research by outside users, Van de Graaff and ion sources, computer systems, instrumentation, and the Laboratory`s booster linac work. An appendix lists Laboratory personnel, Ph.D. degrees granted in the 1988-1989 academic year, and publications. Refs., 23 figs., 3 tabs.

  4. Experimental nuclear and radiochemistry. Progress report, 1981

    International Nuclear Information System (INIS)

    Karol, P.J.

    1981-09-01

    Research progress is reported on the following topics: (1) the importance of classical nucleon-nucleon spatial correlations on nuclear interactions; (2) mathematical development of properly behaved skewed Gaussian function; (3) cluster interactions and true pion absorption; and (4) anomalous relativistic heavy-ion projectile fragments

  5. The experimental nuclear reactor: AQUILON; Le reacteur nucleaire experimental: AQUILON

    Energy Technology Data Exchange (ETDEWEB)

    Girard, Y; Koechlin, J C; Moreau, J M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    'Aquilon' is an experimental reactor specially designed for the neutronic study of heterogeneous multiplying media with solid fuel and liquid moderator. Since this study is in general incompatible with energy production, the power of the reactor has been limited to a minimum so as to be able to obtain a simple and compact structure, easy access, good handling and great flexibility of operation and utilisation. (author) [French] 'Aquilon' est un reacteur experimental specialement concu pour l'etude neutronique de milieux multiplicateurs heterogenes a combustible solide et ralentisseur liquide. Cette etude etant en general incompatible avec la production d'energie, on a limite au minimum la puissance du reacteur pour pouvoir obtenir une structure simple et peu encombrante, un acces facile, une bonne maniabilite et une grande souplesse de fonctionnement et d'utilisation. (auteur)

  6. Nuclear symmetry energy: An experimental overview

    Indian Academy of Sciences (India)

    on how reliable the model that describes the experimental observable is. ... advantage in such studies is that they provide a 'direct' means of studying the ..... FRIB, FAIR and SPIRAL II should provide increased precision in the measurement.

  7. Experimental investigations of the nuclear structure

    International Nuclear Information System (INIS)

    Gromov, K.Ya.

    1989-01-01

    The problem of experimental investigation into atomic nucleus structure is discussed. Examples of studying the properties of low-lying nucleus states using cyclotron-type accelerators for their production are presented. The consideration is conducted on the base of the Idisol experimental complex created at the Finland. Results of measuring masses of neutron-redundant rubidium nuclei are presented. Schemes of 160 Er and 108 In decay are presented. 12 refs.; 6 figs

  8. Perspectives of experimental nuclear physics research at RBI Croatia

    International Nuclear Information System (INIS)

    Soic, N.

    2009-01-01

    Experimental nuclear physics has been one of the top research activities at the Rudjer Boskovic Institute, the largest and leading Croatian research center in science and applications. The RBI nuclear physics group has strong link with the researchers at the University of Zagreb. RBI scientists perform experiments at the RBI Tandem accelerator facility and at the top European experimental facilities in collaboration with the prominent research groups in the field. Current status of the RBI experimental nuclear physics research and our recent activities aimed to strengthen our position at the RBI and to increase our international reputation and impact in collaborative projects will be presented. Part of these activities is focused on local accelerator facilities, at present mainly used for application research, and their increased usage for nuclear physics research and for development and testing of novel research equipment for large international facilities. Upgrade of the local research equipment is on the way through FP7 REGPOT project 'CLUNA: Clustering phenomena in nuclear physics: strengthening of the Zagreb-Catania-Birmingham partnership'. Recently, steps to exploit potential of the facility for nuclear astrophysics research have been initiated. Possible future actions for further strengthening of the RBI experimental nuclear physics research will be discussed.(author)

  9. Proceedings of the Jorge Andre Swieca Summer School; 4. Experimental Nuclear Physics Session

    International Nuclear Information System (INIS)

    1990-01-01

    These proceedings present works on experimental nuclear physics, activation analysis, nuclear interactions, neutron physics, nuclear moments, inelastic scattering, lattices and chemical analysis. (L.C.J.A.)

  10. Nuclear Test-Experimental Science: Annual report, fiscal year 1988

    Energy Technology Data Exchange (ETDEWEB)

    Struble, G.L.; Donohue, M.L.; Bucciarelli, G.; Hymer, J.D.; Kirvel, R.D.; Middleton, C.; Prono, J.; Reid, S.; Strack, B. (eds.)

    1988-01-01

    Fiscal year 1988 has been a significant, rewarding, and exciting period for Lawrence Livermore National Laboratory's nuclear testing program. It was significant in that the Laboratory's new director chose to focus strongly on the program's activities and to commit to a revitalized emphasis on testing and the experimental science that underlies it. It was rewarding in that revolutionary new measurement techniques were fielded on recent important and highly complicated underground nuclear tests with truly incredible results. And it was exciting in that the sophisticated and fundamental problems of weapons science that are now being addressed experimentally are yielding new challenges and understanding in ways that stimulate and reward the brightest and best of scientists. During FY88 the program was reorganized to emphasize our commitment to experimental science. The name of the program was changed to reflect this commitment, becoming the Nuclear Test-Experimental Science (NTES) Program.

  11. Revised experimental program on the nuclear ship 'Mutsu'

    International Nuclear Information System (INIS)

    Mori, Yuichi

    1985-01-01

    The experimental program on the nuclear ship ''Mutsu'' has been revised by the Government. And, the responsible organization for n. s. Mutsu was turned to Japan Atomic Energy Research Institute (JAERI) from Japan Nuclear-ship Development Agency. The revised, new experimental program is as follows. (1) Experimental navigation of n. s. Mutsu is made with the already loaded 1st reactor core for about one year. (2) The mooring port for n. s. Mutsu is in a minimum scale. (3) Upon termination of the experimental navigation, n. s. Mutsu is immediately decommissioned. (4) Power-up test and experimental navigation of n. s. Mutsu are made in fiscal 1989 to 1990. The policy of research and development with n. s. Mutsu and the works assigned to JAERI with n. s. Mutsu are described. (Mori, K.)

  12. STACY and TRACY: nuclear criticality experimental facilities under construction

    International Nuclear Information System (INIS)

    Kobayashi, I.; Takeshita, I.; Yanagisawa, H.; Tsujino, T.

    1992-01-01

    Japan Atomic Energy Research Institute is constructing a Nuclear Fuel Cycle Safety Engineering Research Facility, NUCEF, where the following research themes essential for evaluating safety problems relating to back-end technology in nuclear fuel cycle facilities will be studied: nuclear criticality safety research; research on advanced reprocessing processes and partitioning; and research on transuranic waste treatment and disposal. To perform nuclear criticality safety research related to the reprocessing of light water reactor spent fuels, two criticality experimental facilities, STACY and TRACY, are under construction. STACY (Static Criticality Facility) will be used for the study of criticality conditions of solution fuels, uranium, plutonium and their mixtures. TRACY (Transient Criticality Facility) will be used to investigate criticality accident phenomena with uranium solutions. The construction progress and experimental programmes are described in this Paper. (author)

  13. VI European Summer School on Experimental Nuclear Astrophysics

    Science.gov (United States)

    The European Summer School on Experimental Nuclear Astrophysics has reached the sixth edition, marking the tenth year's anniversary. The spirit of the school is to provide a very important occasion for a deep education of young researchers about the main topics of experimental nuclear astrophysics. Moreover, it should be regarded as a forum for the discussion of the last-decade research activity. Lectures are focused on various aspects of primordial and stellar nucleosynthesis, including novel experimental approaches and detectors, indirect methods and radioactive ion beams. Moreover, in order to give a wide educational offer, some lectures cover complementary subjects of nuclear astrophysics such as gamma ray astronomy, neutron-induced reactions, short-lived radionuclides, weak interaction and cutting-edge facilities used to investigate nuclear reactions of interest for astrophysics. Large room is also given to young researcher oral contributions. Traditionally, particular attention is devoted to the participation of students from less-favoured countries, especially from the southern coast of the Mediterranean Sea. The school is organised by the Catania Nuclear Astrophysics research group with the collaboration of Dipartimento di Fisica e Astromomia - Università di Catania and Laboratori Nazionali del Sud - Istituto Nazionale di Fisica Nucleare.

  14. Progress of experimental research on nuclear safety in NPIC

    Energy Technology Data Exchange (ETDEWEB)

    Gong, Houjun; Zan, Yuanfeng; Peng, Chuanxin; Xi, Zhao; Zhang, Zhen; Wang, Ying; He, Yanqiu; Huang, Yanping [Nuclear Power Institute of China, Chengdu (China)

    2016-05-15

    Two kinds of Generation III commercial nuclear power plants have been developed in CNNC (China National Nuclear Corporation), one is a small modular reactor ACP100 having an equivalent electric power 100 MW, and the other is HPR1000 (once named ACP1000) having an equivalent electric power 1 000 MW. Both NPPs widely adopted the design philosophy of advanced passive safety systems and considered the lessons from Fukushima Daichi nuclear accident. As the backbone of the R and D of ACP100 and HPR1000, NPIC (Nuclear power Institute of China) has finished the engineering verification test of main safety systems, including passive residual heat removal experiments, reactor cavity injection experiments, hydrogen combustion experiments, and passive autocatalytic recombiner experiments. Above experimental work conducted in NPIC and further research plan of nuclear safety are introduced in this paper.

  15. Experimental (Network) and Evaluated Nuclear Reaction Data at NDS

    International Nuclear Information System (INIS)

    Otsuka, N.; Semkova, V.; Simakov, S.P.; Zerkin, V.

    2011-01-01

    Dr Simakov of Nuclear Data Services Unit in the Nuclear Data Section (NDS) gave a brief overview of the data compilation and evaluation activities in the nuclear data community: experimental nuclear reaction data (EXFOR, http://www-nds.iaea.org/exfor/) and evaluated nuclear reaction data (ENDF, http://www-nds.iaea.org/endf). The International Network of Nuclear Reaction Data Centres (NRDC) coordinated by NDS includes 14 Centres in 8 Countries (China, Hungary, India, Japan, Korea, Russian, Ukraine, USA) and 2 International Organizations (NEA, IAEA). It had the first meeting of four core centres (Brookhaven, Saclay, Obninsk, Vienna) in 1966 and the EXFOR was adopted as an official data exchange format. In 2000, IAEA implemented the EXFOR database as a relational multiform database and the EXFOR is a trusted, increasing and living database with 19100 experimental works (as of September 2011) and 141600 data tables. The EXFOR provides a compilation control system for selection of articles and compilation of data and the NRDC home page provides manuals, documents and codes. The nuclear data can be retrieved by the web-retrieval system or distributed on a DVD on request. The EXFOR data play a critical role in the development of evaluated nuclear reaction data. There are several major general purpose libraries: ENDF (US), CENDL (China), JEFF (EU), JENDL (Japan) and RUSFOND (Russia). In addition, there are special libraries for particular applications: EAF (European Activation File), FENDL (Fusion Evaluated Nuclear Data Library for ITER neutronics), IBANDL (Ion Beam Analysis Nuclear Data Library for surface analysis of solids), IRDF, DXS (Dosimetry, radiation damage and gas production data) and Medical portal. Dr V. Zerkin of NDS demonstrated the data retrieval from the EXFOR database and the ENDF library.

  16. Experimental (Network) and Evaluated Nuclear Reaction Data at NDS

    Energy Technology Data Exchange (ETDEWEB)

    Otsuka, N; Semkova, V; Simakov, S P; Zerkin, V [Nuclear Data Services Unit, Nuclear Data Section, IAEA, Vienna (Austria)

    2011-11-15

    Dr Simakov of Nuclear Data Services Unit in the Nuclear Data Section (NDS) gave a brief overview of the data compilation and evaluation activities in the nuclear data community: experimental nuclear reaction data (EXFOR, http://www-nds.iaea.org/exfor/) and evaluated nuclear reaction data (ENDF, http://www-nds.iaea.org/endf). The International Network of Nuclear Reaction Data Centres (NRDC) coordinated by NDS includes 14 Centres in 8 Countries (China, Hungary, India, Japan, Korea, Russian, Ukraine, USA) and 2 International Organizations (NEA, IAEA). It had the first meeting of four core centres (Brookhaven, Saclay, Obninsk, Vienna) in 1966 and the EXFOR was adopted as an official data exchange format. In 2000, IAEA implemented the EXFOR database as a relational multiform database and the EXFOR is a trusted, increasing and living database with 19100 experimental works (as of September 2011) and 141600 data tables. The EXFOR provides a compilation control system for selection of articles and compilation of data and the NRDC home page provides manuals, documents and codes. The nuclear data can be retrieved by the web-retrieval system or distributed on a DVD on request. The EXFOR data play a critical role in the development of evaluated nuclear reaction data. There are several major general purpose libraries: ENDF (US), CENDL (China), JEFF (EU), JENDL (Japan) and RUSFOND (Russia). In addition, there are special libraries for particular applications: EAF (European Activation File), FENDL (Fusion Evaluated Nuclear Data Library for ITER neutronics), IBANDL (Ion Beam Analysis Nuclear Data Library for surface analysis of solids), IRDF, DXS (Dosimetry, radiation damage and gas production data) and Medical portal. Dr V. Zerkin of NDS demonstrated the data retrieval from the EXFOR database and the ENDF library.

  17. Development of the Nuclear Ship Database. 1. Outline of the Nuclear Ship Experimental Database

    Energy Technology Data Exchange (ETDEWEB)

    Kyouya, Masahiko; Ochiai, Masa-aki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Hashidate, Kouji

    1995-03-01

    We obtained the experimental data on the effects of the ship motions and the change in load and caused by the ship operations, the waves, the winds etc., to the nuclear power plant behavior, through the Power-up Tests and Experimental Voyages of the Nuclear Ship MUTSU. Moreover, we accumulated the techniques, the knowledge and others on the Nuclear Ship development at the each stage of the N.S. MUTSU Research and Development program, such as the design stage, the construction stage, the operation stage and others. These data, techniques, knowledge and others are the assembly of the experimental data and the experiences through the design, the construction and the operation of the first nuclear ship in JAPAN. It is important to keep and pigeonhole these products of the N.S. MUTSU program in order to utilize them effectively in the research and development of the advanced marine reactor, since there is no construction plan of the nuclear ship for the present in JAPAN. We have been carrying out the development of the Nuclear Ship Database System since 1991 for the purpose of effective utilization of the N.S. MUTSU products in the design study of the advanced marine reactors. The part of the Nuclear Ship Database System on the experimental data, called Nuclear Ship Experimental Database, was already accomplished and utilized since 1993. This report describes the outline and the use of the Nuclear Ship Experimental Database.The remaining part of the database system on the documentary data, called Nuclear Ship Documentary Database, are now under development. (author).

  18. Development of the Nuclear Ship Database. 1. Outline of the Nuclear Ship Experimental Database

    International Nuclear Information System (INIS)

    Kyouya, Masahiko; Ochiai, Masa-aki; Hashidate, Kouji.

    1995-03-01

    We obtained the experimental data on the effects of the ship motions and the change in load and caused by the ship operations, the waves, the winds etc., to the nuclear power plant behavior, through the Power-up Tests and Experimental Voyages of the Nuclear Ship MUTSU. Moreover, we accumulated the techniques, the knowledge and others on the Nuclear Ship development at the each stage of the N.S. MUTSU Research and Development program, such as the design stage, the construction stage, the operation stage and others. These data, techniques, knowledge and others are the assembly of the experimental data and the experiences through the design, the construction and the operation of the first nuclear ship in JAPAN. It is important to keep and pigeonhole these products of the N.S. MUTSU program in order to utilize them effectively in the research and development of the advanced marine reactor, since there is no construction plan of the nuclear ship for the present in JAPAN. We have been carrying out the development of the Nuclear Ship Database System since 1991 for the purpose of effective utilization of the N.S. MUTSU products in the design study of the advanced marine reactors. The part of the Nuclear Ship Database System on the experimental data, called Nuclear Ship Experimental Database, was already accomplished and utilized since 1993. This report describes the outline and the use of the Nuclear Ship Experimental Database.The remaining part of the database system on the documentary data, called Nuclear Ship Documentary Database, are now under development. (author)

  19. Experimental study of water flow in nuclear fuel elements

    International Nuclear Information System (INIS)

    Rodrigues, Lorena Escriche; Rezende, Hugo Cesar; Mattos, Joao Roberto Loureiro de; Barros Filho, Jose Afonso; Santos, Andre Augusto Campagnole dos

    2013-01-01

    This work aims to develop an experimental methodology for investigating the water flow through rod bundles after spacer grids of nuclear fuel elements of PWR type reactors. Speed profiles, with the device LDV (Laser Doppler Velocimetry), and the pressure drop between two sockets located before and after the spacer grid, using pressure transducers were measured

  20. Experimental nuclear physics research challenges at low energies

    Energy Technology Data Exchange (ETDEWEB)

    Chavez, E.; Morales G, L. [UNAM, Instituto de Fisica, Circuito Exterior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Murillo O, G. [ININ, Carretera Mexico-Toluca s/n, Ocoyoacac 52750, Estado de Mexico (Mexico)

    2010-02-15

    Experimental research with low energy beams of ions (a few MeV) in nuclear physics has gone through a phase transition along its evolution in fifty years because of the increasing complexity (and cost) of the equipment required to conduct meaningful investigations. Many of the small cyclotrons and Van de Graaff (single ended and tandem) accelerators have been used for the last three decades mostly in applications related to the characterization and modification of materials. Specific experimental investigations in nuclear physics with low energy accelerators are proposed in this work. Specifically we discuss the topic of nuclear radii measurements of radioactive species produced via (d,n) reactions. Some emphasis is given to the instrumentation required. (Author)

  1. Improvement of macrophage dysfunction by administration of anti-transforming growth factor-beta antibody in EL4-bearing hosts.

    Science.gov (United States)

    Maeda, H; Tsuru, S; Shiraishi, A

    1994-11-01

    An experimental therapy for improvement of macrophage dysfunction caused by transforming growth factor-beta (TGF-beta) was tried in EL4 tumor-bearing mice. TGF-beta was detected in cell-free ascitic fluid from EL4-bearers, but not in that from normal mice, by western blot analysis. The ascites also showed growth-suppressive activity against Mv1Lu cells, and the suppressive activity was potentiated by transient acidification. To investigate whether the functions of peritoneal macrophages were suppressed in EL4-bearers, the abilities to produce nitric oxide and tumor necrosis factor-alpha (TNF-alpha) upon lipopolysaccharide (LPS) stimulation were measured. Both abilities of macrophages in EL4-bearing mice were suppressed remarkably on day 9, and decreased further by day 14, compared with non-tumor-bearing controls. TGF-beta activity was abrogated by administration of anti-TGF-beta antibody to EL4-bearing mice. While a large amount of TGF-beta was detected in ascitic fluid from control EL4-bearers, little TGF-beta was detectable in ascites from EL4-bearers given anti-TGF-beta antibody. Furthermore, while control macrophages exhibited little or no production of nitric oxide and TNF-alpha on LPS stimulation in vitro, macrophages from EL4-bearers administered with anti-TGF-beta antibody showed the same ability as normal macrophages. These results clearly indicate that TGF-beta contributes to macrophage dysfunction and that the administration of specific antibody for TGF-beta reverses macrophage dysfunction in EL4-bearing hosts.

  2. Experimental study of water flow in nuclear fuel elements; Estudo experimental do escoamento de agua em elementos combustiveis nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Rodrigues, Lorena Escriche, E-mail: ler@cdtn.br [Centro Federal de Educacao Tecnologica de Minas Gerais (CEFET), Belo Horizonte, MG (Brazil); Rezende, Hugo Cesar; Mattos, Joao Roberto Loureiro de; Barros Filho, Jose Afonso; Santos, Andre Augusto Campagnole dos, E-mail: hcr@cdtn.br, E-mail: jrmattos@cdtn.br, E-mail: jabf@cdtn.br, E-mail: aacs@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2013-07-01

    This work aims to develop an experimental methodology for investigating the water flow through rod bundles after spacer grids of nuclear fuel elements of PWR type reactors. Speed profiles, with the device LDV (Laser Doppler Velocimetry), and the pressure drop between two sockets located before and after the spacer grid, using pressure transducers were measured.

  3. Research at the Section of Experimental Nuclear Physics of ATOMKI

    International Nuclear Information System (INIS)

    Krasznahorkay, A.; Fenyes, T.; Dombradi, Zs.; Nyako, B.M.; Timar, J.; Algora, A.; Csatlos, M.; Csige, L.; Gacsi, Z.; Gulyas, J.

    2011-01-01

    Introduction. Nuclear physics research was started in Debrecen by Alexander Szalay (1909-1987) back in the 30's. He had been a postdoc of the Nobel-laureate biologist Albert Szent-Gyorgyi in Szeged and of Lord Rutherford in Cambridge. ATOMKI was founded in Debrecen later, in 1954. The Institute was meant to pursue scientific research in certain areas of experimental nuclear physics and to develop research instruments In the early years the country was pretty isolated, but the institute's state of isolation was gradually easing up from the mid-sixties. During the period 1962-1975 the research work was performed in collaboration with Joint Institute for Nuclear Research (Dubna), where up-to-date high-energy accelerators were available for the production of desired isotopes. After finishing the construction of a home-made 5 MV Van de Graaff accelerator (1972) and later on the installation of a K=20 light ion cyclotron (1985) the Institute has become the main centre of accelerator-based nuclear physics in Hungary. In the period 1975-1995 our group performed extensive nuclear structure studies in Debrecen by using γ and conversion electron spectroscopy. At the same time fruitful collaborations were initiated with Jyvaskyla (Finland), with University of Kentucky and University of Zagreb. In 1993 the former Nuclear Reaction Group (NRG) merged with our group. Parallel with this structural change, the main topics of our γ-spectroscopic work has also changed, which resulted that the location of our experiments were shifted from the home institute to foreign large-scale facilities. New topics were brought partly by the emerging NRG, partly by group members returning from postdoctoral fellowships. They also brought important non γ-spectroscopic topics, which enriched our research palette. These new topics have by now become joint endeavours involving more and more group members. The Nuclear Physics European Coordination Committee (NuPECC) has recently stated that the aim of

  4. Optimizing Nuclear Reaction Analysis (NRA) using Bayesian Experimental Design

    International Nuclear Information System (INIS)

    Toussaint, Udo von; Schwarz-Selinger, Thomas; Gori, Silvio

    2008-01-01

    Nuclear Reaction Analysis with 3 He holds the promise to measure Deuterium depth profiles up to large depths. However, the extraction of the depth profile from the measured data is an ill-posed inversion problem. Here we demonstrate how Bayesian Experimental Design can be used to optimize the number of measurements as well as the measurement energies to maximize the information gain. Comparison of the inversion properties of the optimized design with standard settings reveals huge possible gains. Application of the posterior sampling method allows to optimize the experimental settings interactively during the measurement process.

  5. A novel experimental technique of nuclear lifetime measurements

    International Nuclear Information System (INIS)

    Yuminov, O.A.; D'Arrigo, A.; Giardina, G.; Taccone, A.; Vannini, G.; Moroni, A.; Ricci, R.A.; Vannucci, L.

    1995-01-01

    In the present paper a new experimental method to measure nuclear reaction time in the 10 -15 -10 -10 s region is presented. Measurements of the lifetimes of low-lying and long-lived states of 19 F and 20 Ne decaying via α-channel were carried out with the aim of checking the feasibility of the method. The results obtained in this way are compared with the lifetimes known from different techniques. ((orig.))

  6. The former experimental nuclear power station in Lucens

    International Nuclear Information System (INIS)

    Meichle, A.

    1989-01-01

    In June 1989 in the Swiss canton of Vaud, a majority vote was reached for the discharge from federal responsibility and control of the experimental reactor in Lucens, which was shut down following an accident twenty years ago. As the topic 'Lucens' will remain current interest for some time, a brief history as well as future prospects are presented. The report begins with Switzerland's immediate post-war recognition of the importance of nuclear energy. This was initially characterized by the formation of Reactor Ltd., and three commercial groups. The submission of projects by the latter to parliament in the 1950's for the construction of a test nuclear reactor with the request for federal support met with a positive echo and a subsidy of 50% of the costs. The NGA (a national society for the promotion of industrial nuclear technology) was founded with the aim to consolidate projects into a national plan. The NGA's first step was to plan and install an experimental, heavy water moderated, gas-cooled reactor in Lucens. An engineering group (AGL) was delegated by the NGA to plan, construct and commission the reactor. The construction began in July 1962. The location, type of reactor, fuel used, cooling system and the placement in 3 cavities in a hill are briefly described. In 1966 the reactor first went critical and 2 years later 30 MW thermal power was attained. The construction engineers and the operating management were completely satisfied with reactor operation prior to the accident. 1 fig

  7. Characteristics and construction problems of EL 4; Caracteristiques et problemes de construction d'EL4

    Energy Technology Data Exchange (ETDEWEB)

    Carle, R; Schulhof, P [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Sevin, Ph [Electricite de France (EDF), 75 - Paris (France); Buttin, J [Societe INDATOM (France)

    1964-07-01

    EL 4 is the prototype of a new series of reactors moderated with heavy water and cooled by carbon dioxyde. It was studied with a double purpose: - to realize a sufficiently large and complete reactor for testing the problems of construction and operation of this type of reactors; - to keep in this installation the possibility of adapting the improvements (new materials, improved fuel elements) studied in the R. and D. program. The first objective could not be considered without a considerable volume of preliminary work. This work included particularly the construction and testing from 1962 to 1964 of several prototype channels, out of pile, but under the actual temperature and pressure conditions. These tests showed the proper behaviour of the materials under the severe mechanical and chemical conditions of the reactor. These installations will, furthermore, be available for testing further modifications before adapting them to the reactor. Important tests concerning the safety of the reactor in the event of an explosion of the CO{sub 2} circuit have also been carried out. Construction itself began in July 1962 under the double direction of the Commissariat a l'Energie Atomique and Electricite de France. The civil engineering work will be finished in 1964. The airtight containment (in which it was considered preferable to house the reactor because of its prototype character) was built in pre-stressed concrete, a method which appeared to be particularly rapid and easy. The main piece of the reactor is the heavy water tank. This tank is composed of two double end plates equipped with 216 tubes and joined by a steel cylinder. Some difficult welding problems according to the specifications were solved during the construction of these bottoms. A rigorous series of controls by radiographies and ultrasonic methods was adapted to a complicated geometry. The assembly of the reactor unit, and particularly of the array of tubes supplying the 216 channels, was studied in every

  8. Proposed experimental test of Bell's inequality in nuclear beta decay

    International Nuclear Information System (INIS)

    Skalsey, M.

    1986-01-01

    A β decay experiment is proposed for testing Bell's inequality, related to hidden-variables alternatives to quantum mechanics. The experiment uses Mott scattering for spin polarization analysis of internal conversion electrons. Beta-decay electrons, in cascade with the conversion electrons, are longitudinally polarized due to parity violation in the weak interaction. So simply detecting the β electron direction effectively measures the spin. A two-particle spin-spin correlation can thus be investigated and related, within certain assumptions, to Bell's inequality. The example of 203 Hg decay is used for a calculation of expected results. Specific problems related to nuclear structure and experimental inconsistencies are also discussed

  9. Experimental nuclear physics. Progress report, August 1985-August 1986

    International Nuclear Information System (INIS)

    1986-01-01

    The research activities of the experimental nuclear structure group at Vanderbilt University are reported here. Research continues in the areas of (1) in-beam γ-ray spectroscopy; (2) studies of nuclei far from stability at UNISOR and at the recoil mass spectrometer at the University of Rochester; (3) nucleon transfer reaction and fusion-fission studies; and (4) theoretical studies. In general, abstracts of papers published or submitted for publication in this period make up this report along with brief reports of work in process and complete copies of a few conference papers

  10. Experimental physics 4. Nuclear, particle and astrophysics. 5. ed.; Experimentalphysik 4. Kern-, Teilchen- und Astrophysik

    Energy Technology Data Exchange (ETDEWEB)

    Demtroeder, Wolfgang

    2017-09-01

    The following topics are dealt with: Structure of atomic nuclei, unstable nuclei and radioactivity, experimental techniques in nuclear and high-energy physics, nuclear forces and nuclear models, nuclear reactions, physics of elementary particles, applications of nuclear and high-energy physics, foundations of experimental astronomy and astrophysics, our solar system, birth, life, and death of stars, the development and present structure of the universe. (HSI)

  11. Differential expression of FAK and Pyk2 in metastatic and non-metastatic EL4 lymphoma cell lines.

    Science.gov (United States)

    Zhang, Zhihong; Knoepp, Stewart M; Ku, Hsun; Sansbury, Heather M; Xie, Yuhuan; Chahal, Manpreet S; Tomlinson, Stephen; Meier, Kathryn E

    2011-08-01

    The murine EL4 lymphoma cell line exists in variants that are either sensitive or resistant to phorbol 12-myristate 13-acetate (PMA). In sensitive cells, PMA causes Erk MAPK activation and Erk-mediated growth arrest. In resistant cells, PMA induces a low level of Erk activation, without growth arrest. A relatively unexplored aspect of the phenotypes is that resistant cells are more adherent to culture substrate than are sensitive cells. In this study, the roles of the protein tyrosine kinases FAK and Pyk2 in EL4 phenotype were examined, with a particular emphasis on the role of these proteins in metastasis. FAK is expressed only in PMA-resistant (or intermediate phenotype) EL4 cells, correlating with enhanced cell-substrate adherence, while Pyk2 is more highly expressed in non-adherent PMA-sensitive cells. PMA treatment causes modulation of mRNA for FAK (up-regulation) and Pyk2 (down-regulation) in PMA-sensitive but not PMA-resistant EL4 cells. The increase in Pyk2 mRNA is correlated with an increase in Pyk2 protein expression. The roles of FAK in cell phenotype were further explored using transfection and knockdown experiments. The results showed that FAK does not play a major role in modulating PMA-induced Erk activation in EL4 cells. However, the knockdown studies demonstrated that FAK expression is required for proliferation and migration of PMA-resistant cells. In an experimental metastasis model using syngeneic mice, only FAK-expressing (PMA-resistant) EL4 cells form liver tumors. Taken together, these studies suggest that FAK expression promotes metastasis of EL4 lymphoma cells.

  12. Preface: Eighth European Summer School on Experimental Nuclear Astrophysics

    International Nuclear Information System (INIS)

    Claudio, Spitaleri; Livio, Lamia; Gianluca, Pizzone Rosario

    2016-01-01

    In this book a collection of the lecture notes given during the Eighth European Summer School on Experimental Nuclear Astrophysics is given. The school, whose first edition was first held in 2003, took place from 13 to 20 of September 2015 in Santa Tecla, a small village about 15 km north of Catania, characterized by its position on the volcanic shores of the Ionian Sea, surrounded by the spectacular “Timpa” area, a green protected park specific for its mediterranean vegetation. 80 young students and researchers from more than 20 countries attended the lectures and were also encouraged to present their work and results. The school, has tried once more to present to the young students the global picture of nuclear astrophysics research in the last years. Thus the scientific program of the school covered a wide range of topics dealing with various aspects of nuclear astrophysics, such as stellar evolution and nucleosynthesis, neutrino physics, the Big Bang, direct and indirect methods and radioactive ion beams. Nuclear astrophysics plays a key role in understanding energy production in stars, stellar evolution and the concurrent synthesis of the chemical elements and their isotopes. It is also a fundamental tool to explain the ashes of the early universe, to determine the age of the universe through the study of pristine stellar objects and to predict the evolution of the Sun or Stars. The “bone structure” for the above aspects is based on nuclear reactions, whose rates need to be determined in laboratories. Although impressive progress has been made over the past decades, which was rewarded by Nobel prizes, several open questions are still unsolved, which challenge the basis of the present understanding. A list of the lecture topics is given below: —Big Bang Nucleosynthesis —Stellar evolution and Nucleosynthesis —radioactive ion beams —detector and facilities for nuclear astrophysics —indirect methods in nuclear astrophysics —plasma physics An

  13. Experimental Observation of Nuclear Reactions in Palladium and Uranium

    International Nuclear Information System (INIS)

    J. Dufour; D. Murat; X. Dufour; J. Foos

    2001-01-01

    By submitting various metals (Pd, U) containing hydrogen (from 2000 to 700 000 atoms of hydrogen for 1 000 000 atoms of the host metal) to the combined action of electrical currents and magnetic fields, we have observed a sizeable exothermal effect (from 0.1 to 8 W for 500 mg of metal used). This effect is beyond experimental errors, the energy output being typically 130 to 250% of the energy input and not of chemical origin (exothermal effect in the range of 7000 MJ/mol of metal in the case of palladium and of 60 MJ/mol in the case of uranium). New chemical species also appear in the processes metals. It has been shown by a QED calculation that resonances of long lifetime (s), nuclear dimensions (fm), and low energy of formation (eV) could exist. This concept seems to look like the 'shrunken hydrogen atoms' proposed by various authors. It is indeed very different in two ways (a) being a metastable state, it needs energy to be formed (a few eV) and reverts to normal hydrogen after a few seconds, liberating back its energy of formation (it is thus not the source of the energy observed); (b) its formation can be described as the electron spin/proton nuclear spin interaction becoming first order in the lattice environment (whereas it is third order in a normal hydrogen atom). Moreover, we consider that the hydrex cannot yield a neutron because this reaction is strongly endothermic. To explain our results, we put forward the following working hypothesis: In a metal lattice and under proper conditions, the formation of such resonances (metastable state) could be favored. We propose to call them HYDREX, and we assume that they are actually formed in cold fusion (CF) and low-energy nuclear reaction (LENR) experiments. Once formed, a number of HYDREX could gather around a nucleus of the lattice to form a cluster of nuclear size and of very long life time compared to nuclear time (10 -22 s). In this cluster, nuclear rearrangements could take place, yielding mainly 4 He

  14. Experimental Nuclear Physics. Progress report, July 1981-July 1982

    International Nuclear Information System (INIS)

    1982-01-01

    The research activities of the experimental nuclear structure group at Vanderbilt for the period July 1981 to July 1982 are reported. This includes continuing cooperative research in the areas of, (a) in-beam γ-ray spectroscopy with scientists at Oak Ridge and the University of Koeln; (b) studies of nuclei far from stability at UNISOR; (c) pre-equilibrium (massive transfer) emission processes in fusion reactions at ORNL; (d) nucleon transfer reaction studies with scientists at ORNL, Los Alamos and Brookhaven; (e) delta-electron spectroscopy at the Max Planck Institute in Heidelberg; (f) theoretical studies with scientists at Lawrence Berkeley Lab., Brookhaven National Lab., University of Frankfurt, and Vanderbilt; and (g) Coulomb excitation studies at GSI, Darmstadt, Germany. In general, abstracts of papers published or submitted for publication in this period make up this report along with brief reports of work in process and complete copies of a few reviews in press

  15. Nuclear analysis of the experimental VHTR fuel lattice

    International Nuclear Information System (INIS)

    Doi, Takeshi; Shindo, Ryuiti; Hirano, Mitsumasa; Takano, Makoto

    1984-11-01

    Nuclear properties of a fuel lattice in the experimental VHTR core were analyzed with DELIGHT-6 and SRAC codes. Analytical results by both codes were compared by using various calculational model. The nuclear parameters were analyzed, such as a multiplication factor of a fuel lattice and it's variation with burnup, a temperature effect on reactivity, an effect of double-heterogeniety in a resonance absorption calculation, a resonance integral of 238 U and a reactivity worth of burnable poison. From these analyses, following results were obtained. Firstly, on calculational models, 1) Effect of double-heterogeniety in the resonance absorption calculation for Mark-III fuel element, causing a decrease of about 5.5 barns in the resonance integral and an increase of about 2.6 %ΔK in the infinite multiplication factor, 2) The heterogeneous calculation with the collision probability method resulted in about 0.6 %ΔK higher the multiplication factor of fuel lattice than that with the point model, 3) The reactivity worth of burnable poison rod by a multi-region model is about 20 % less than that by a 2-region model at an initial state of burnup and it's variation with burnup are fairly different, Secondly, on comparison between the results by DELIGHT-6 and SRAC, 4) The nuclear parameters obtained with both codes agreed well, Lastly, on the improvement in DELIGHT-6, 5) Consideration of the neutron spectrum shielding effect in the resonance effective cross section calculation caused a decrease of about 2.4 %ΔK in the multiplication factor of fuel lattice, 6) The lattice multiplication factor increased about 0.5 %ΔK by introducing lambda-parameters for the non-resonant nuclie. (J.P.N.)

  16. Experimental evaluation of an expert system for nuclear reactor operators

    International Nuclear Information System (INIS)

    Nelson, W.R.

    1984-10-01

    The United States Nuclear Regulatory Commission (USNRC) is supporting a program for the experimental evaluation of an expert system for nuclear reactor operators. A prototype expert system, called the Response Tree System, has been developed and implemented at INEL. The Response Tree System is designed to assess the status of a reactor system following an accident and recommend corrective actions to reactor operators. The system is implemented using color graphic displays and is driven by a computer simulation of the reactor system. Control of the system is accomplished using a transparent touch panel. Controlled experiments are being conducted to measure performance differences between operators using the Response Tree System and those not using it to respond to simulated accident situations. This paper summarizes the methodology and results of the evaluation of the Response Tree System, including the quantitative results obtained in the experiments thus far. Design features of the Response Tree System are discussed, and general conclusions regarding the applicability of expert systems in reactor control rooms are presented

  17. Overview of experimental research on nuclear structure in department of modern applied physics

    International Nuclear Information System (INIS)

    Zhu Shengjiang

    1999-01-01

    The experimental research on nuclear structure in Department of Modern Applied Physics, Tsinghua University has been summarized. The main research results in high spin states of nuclear structure, as well as some low spin states, have been reported

  18. Experimental study and nuclear model calculations of {sup 3}He-induced nuclear reactions on zinc

    Energy Technology Data Exchange (ETDEWEB)

    Al-Abyad, M.; Mohamed, Gehan Y. [Nuclear Research Centre, Atomic Energy Authority, Physics Department (Cyclotron Facility), Cairo (Egypt); Ditroi, F.; Takacs, S.; Tarkanyi, F. [Hungarian Academy of Sciences (ATOMKI), Institute for Nuclear Research, Debrecen (Hungary)

    2017-05-15

    Excitation functions of {sup 3}He-induced nuclear reactions on natural zinc were measured using the standard stacked-foil technique and high-resolution gamma-ray spectrometry. From their threshold energies up to 27 MeV, the cross-sections for {sup nat}Zn ({sup 3}He,xn) {sup 69}Ge, {sup nat}Zn({sup 3}He,xnp) {sup 66,67,68}Ga, and {sup nat}Zn({sup 3}He,x){sup 62,65}Zn reactions were measured. The nuclear model codes TALYS-1.6, EMPIRE-3.2 and ALICE-IPPE were used to describe the formation of these products. The present data were compared with the theoretical results and with the available experimental data. Integral yields for some important radioisotopes were determined. (orig.)

  19. Inactivation of the small GTP binding protein Rho induces multinucleate cell formation and apoptosis in murine T lymphoma EL4.

    Science.gov (United States)

    Moorman, J P; Bobak, D A; Hahn, C S

    1996-06-01

    The small G-protein Rho regulates the actin microfilament-dependent cytoskeleton. Exoenzyme C3 of Clostridium botulinum ADP-ribosylates Rho at Asn41, a modification that functionally inactivates Rho. Using a Sindbis virus-based transient gene expression system, we studied the role of Rho in murine EL4 T lymphoma cells. We generated a double subgenomic infectious Sindbis virus (dsSIN:C3) recombinant which expressed C3 in >95% of EL4 cells. This intracellular C3 resulted in modification and inactivation of virtually all endogenous Rho. dsSIN:C3 infection led to the formation of multinucleate cells, likely by inhibiting the actin microfilament-dependent step of cytokinesis. Intriguingly, in spite of the inhibition of cytokinesis, karyokinesis continued, with the result that cells containing a nuclear DNA content as high as 16N (eight nuclei) were observed. In addition, dsSIN:C3-mediated inactivation of Rho was a potent activator of apoptosis in EL4 cells. To discern whether the formation of multinucleate cells was responsible for the activation of apoptosis, 5-fluorouracil (5-FUra) was used to induce cell cycle arrest. As expected, EL4 cells treated with 5-FUra were prevented from forming multinucleate cells upon infection with dsSIN:C3. dsSIN:C3 infection, however, still caused marked apoptosis in 5-FUra-treated cells, indicating that this activation of apoptosis was independent of multinucleate cell formation.

  20. Experimental nuclear physics: Progress report, September 1986-July 1987

    International Nuclear Information System (INIS)

    Hamilton, J.H.

    1987-08-01

    The research activities of the experimental nuclear structure group at Vanderbilt University carried out under Contract AS05-76ER05034 with the Department of Energy for the period September 1986 to July 1987 are reported here. Research continues in the areas of (1) in-beam γ-ray spectroscopy including cooperations with scientists at Oak Ridge, Univ. of Rochester, Univ. of Koeln, Louisiana State Univ., Univ. of Florida, Idaho Falls, and Univ. of Notre Dame; (2) studies of nuclei far from stability at UNISOR and at the recoil mass spectrometer at the University of Rochester; (3) nucleon transfer reaction and fusion-fission studies with scientists at ORNL, Argonne National Laboratory, Univ. of Michigan, and University of Kansas; (4) theoretical studies with scientists at Univ. Frankfurt, Univ. Tuebingen, Univ. Lund, Brookhaven, Lawrence Berkeley, and ORNL; (5) other studies. In general, abstracts of papers published or submitted for publication in this period make up this report along with brief reports of work in process and complete copies of a few conference papers

  1. Nuclear Physics Division - Inst. of Experimental Physics - Warsaw University - Annual Report 1998

    Energy Technology Data Exchange (ETDEWEB)

    Kirejczyk, M.; Szeflinski, Z. [eds.

    1999-08-01

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Warsaw University Institute of Experimental Physics in year of 1998 are described. The report is divided into three parts: Reaction Mechanisms and Nuclear Structure, Experimental Methods and Instrumentation and the third one contains the lists of personnel, seminars held at the Nuclear Physics Division and list of published papers. A summary of the (NPD) activities are briefly presented in ``Preface`` written by NDP director prof. K. Siwek-Wilczynska

  2. Nuclear Physics Division, Institute of Experimental Physics, Warsaw University annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Szeflinski, Z.; Kirejczyk, M.; Popkiewicz, M. [eds.

    1998-08-01

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Institute of Experimental Physics (Warsaw University) in year 1997 are described. The report is divided into three parts: Reaction Mechanisms and Nuclear Structure, Experimental Methods and Instrumentation and the third one contain the lists of personnel, seminars held at the Nuclear Physics Division and published papers. A summary of the (NPD) activities are briefly presented in ``Preface`` written by NDP director prof. K. Siwek-Wilczynska

  3. Nuclear Physics Division - Inst. of Experimental Physics - Warsaw University - Annual Report 2003

    International Nuclear Information System (INIS)

    Kirejczyk, M.; Skwira, I.; Grodner, E.

    2004-01-01

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Warsaw University Institute of Experimental Physics in year of 2003 are described. The report is divided into three parts: Reaction Mechanisms and Nuclear Structure, Experimental Methods and Instrumentation and the third one contain the lists of personnel, seminars held at the Nuclear Physics Division and list of published papers. A summary of the (NPD) activities are briefly presented in ''Preface'' written by NPD director prof. K. Siwek-Wilczynska

  4. Nuclear Physics Division, Institute of Experimental Physics, Warsaw University Annual Report 1996

    Energy Technology Data Exchange (ETDEWEB)

    Szeflinski, Z.; Popkiewicz, M. [eds.

    1997-12-31

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Institute of Experimental Physics (Warsaw University) in year 1996 are described. The report is divided into three parts: Reaction mechanisms and nuclear structure; Experimental methods and instrumentation and the third part contains the list of personnel, seminars held at the Nuclear Physics Division and published papers. A summary of the (NPD) activities are briefly presented in ``Preface`` by NPD director prof. Ch. Droste.

  5. Nuclear Physics Division, Institute of Experimental Physics, Warsaw University annual report 1997

    International Nuclear Information System (INIS)

    Szeflinski, Z.; Kirejczyk, M.; Popkiewicz, M.

    1998-01-01

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Institute of Experimental Physics (Warsaw University) in year 1997 are described. The report is divided into three parts: Reaction Mechanisms and Nuclear Structure, Experimental Methods and Instrumentation and the third one contain the lists of personnel, seminars held at the Nuclear Physics Division and published papers. A summary of the (NPD) activities are briefly presented in ''Preface'' written by NDP director prof. K. Siwek-Wilczynska

  6. Nuclear Physics Division - Inst. of Experimental Physics - Warsaw University - Annual Report 1998

    International Nuclear Information System (INIS)

    Kirejczyk, M.; Szeflinski, Z.

    1999-01-01

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Warsaw University Institute of Experimental Physics in year of 1998 are described. The report is divided into three parts: Reaction Mechanisms and Nuclear Structure, Experimental Methods and Instrumentation and the third one contains the lists of personnel, seminars held at the Nuclear Physics Division and list of published papers. A summary of the (NPD) activities are briefly presented in ''Preface'' written by NDP director prof. K. Siwek-Wilczynska

  7. Nuclear Physics Division - Inst. of Experimental Physics - Warsaw University - Annual Report 2000

    International Nuclear Information System (INIS)

    Kirejczyk, M.

    2001-01-01

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Warsaw University Institute of Experimental Physics in year of 2000 are described. The report is divided into three parts: Reaction Mechanisms and Nuclear Structure, Experimental Methods and Instrumentation and the third one contain the lists of personnel, seminars held at the Nuclear Physics Division and list of published papers. A summary of the (NPD) activities are briefly presented in 'Preface' written by NDP director prof. K. Siwek-Wilczynska

  8. Nuclear Physics Division - Inst. of Experimental Physics - Warsaw University - Annual Report 2004

    International Nuclear Information System (INIS)

    Kirejczyk, M.K.

    2005-01-01

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Warsaw University Institute of Experimental Physics in year of 2004 are described. The report is divided into three parts: Reaction Mechanisms and Nuclear Structure, Experimental Methods and Instrumentation and the third one contains the lists of personnel, seminars held at the Nuclear Physics Division and list of published papers. A summary of the (NPD) activities are briefly presented in ''Preface'' written by NDP director prof. K. Siwek-Wilczynska

  9. Nuclear Physics Division - Inst. of Experimental Physics - Warsaw University - Annual Report 1999

    International Nuclear Information System (INIS)

    Kirejczyk, M.

    2000-01-01

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Warsaw University Institute of Experimental Physics in year of 1999 are described. The report is divided into three parts: Reaction Mechanisms and Nuclear Structure, Experimental Methods and Instrumentation and the third one contain the lists of personnel, seminars held at the Nuclear Physics Division and list of published papers. A summary of the (NPD) activities are briefly presented in ''Preface'' written by NDP director prof. K. Siwek-Wilczynska

  10. Nuclear Physics Division, Institute of Experimental Physics, Warsaw University Annual Report 1996

    International Nuclear Information System (INIS)

    Szeflinski, Z.; Popkiewicz, M.

    1997-01-01

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Institute of Experimental Physics (Warsaw University) in year 1996 are described. The report is divided into three parts: Reaction mechanisms and nuclear structure; Experimental methods and instrumentation and the third part contains the list of personnel, seminars held at the Nuclear Physics Division and published papers. A summary of the (NPD) activities are briefly presented in ''Preface'' by NPD director prof. Ch. Droste

  11. Opioid binding site in EL-4 thymoma cell line

    International Nuclear Information System (INIS)

    Fiorica, E.; Spector, S.

    1988-01-01

    Using EL-4 thymoma cell-line we found a binding site similar to the k opioid receptor of the nervous system. The Scatchard analysis of the binding of [ 3 H] bremazocine indicated a single site with a K/sub D/ = 60 +/- 17 nM and Bmax = 2.7 +/- 0.8 pmols/10 6 cells. To characterize this binding site, competition studies were performed using selective compounds for the various opioid receptors. The k agonist U-50,488H was the most potent displacer of [ 3 H] bremazocine with an IC 50 value = 0.57μM. The two steroisomers levorphanol and dextrorphan showed the same affinity for this site. While morphine, [D-Pen 2 , D-Pen 5 ] enkephalin and β-endorphin failed to displace, except at very high concentrations, codeine demonstrated a IC 50 = 60μM, that was similar to naloxone. 32 references, 3 figures, 2 tables

  12. [Experimental and theoretical nuclear physics]: 1988 Annual report

    International Nuclear Information System (INIS)

    1988-05-01

    This paper describes the highlights of the past year of the Nuclear Physics Laboratory at the University of Washington. Particular topics discussed are: astrophysics, giant resonance, heavy ion induced reactions, fundamental symmetries, nuclear reactions, medium energy reactions, accelerator mass spectrometry, Van de Graaf and ion sources, the booster linac project, instrumentation and computer systems

  13. Identifying Understudied Nuclear Reactions by Text-mining the EXFOR Experimental Nuclear Reaction Library

    Energy Technology Data Exchange (ETDEWEB)

    Hirdt, J.A. [Department of Mathematics and Computer Science, St. Joseph' s College, Patchogue, NY 11772 (United States); Brown, D.A., E-mail: dbrown@bnl.gov [National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000 (United States)

    2016-01-15

    The EXFOR library contains the largest collection of experimental nuclear reaction data available as well as the data's bibliographic information and experimental details. We text-mined the REACTION and MONITOR fields of the ENTRYs in the EXFOR library in order to identify understudied reactions and quantities. Using the results of the text-mining, we created an undirected graph from the EXFOR datasets with each graph node representing a single reaction and quantity and graph links representing the various types of connections between these reactions and quantities. This graph is an abstract representation of the connections in EXFOR, similar to graphs of social networks, authorship networks, etc. We use various graph theoretical tools to identify important yet understudied reactions and quantities in EXFOR. Although we identified a few cross sections relevant for shielding applications and isotope production, mostly we identified charged particle fluence monitor cross sections. As a side effect of this work, we learn that our abstract graph is typical of other real-world graphs.

  14. Identifying Understudied Nuclear Reactions by Text-mining the EXFOR Experimental Nuclear Reaction Library

    International Nuclear Information System (INIS)

    Hirdt, J.A.; Brown, D.A.

    2016-01-01

    The EXFOR library contains the largest collection of experimental nuclear reaction data available as well as the data's bibliographic information and experimental details. We text-mined the REACTION and MONITOR fields of the ENTRYs in the EXFOR library in order to identify understudied reactions and quantities. Using the results of the text-mining, we created an undirected graph from the EXFOR datasets with each graph node representing a single reaction and quantity and graph links representing the various types of connections between these reactions and quantities. This graph is an abstract representation of the connections in EXFOR, similar to graphs of social networks, authorship networks, etc. We use various graph theoretical tools to identify important yet understudied reactions and quantities in EXFOR. Although we identified a few cross sections relevant for shielding applications and isotope production, mostly we identified charged particle fluence monitor cross sections. As a side effect of this work, we learn that our abstract graph is typical of other real-world graphs.

  15. Examination of Experimental Data for Irradiation - Creep in Nuclear Graphite

    Science.gov (United States)

    Mobasheran, Amir Sassan

    The objective of this dissertation was to establish credibility and confidence levels of the observed behavior of nuclear graphite in neutron irradiation environment. Available experimental data associated with the OC-series irradiation -induced creep experiments performed at the Oak Ridge National Laboratory (ORNL) were examined. Pre- and postirradiation measurement data were studied considering "linear" and "nonlinear" creep models. The nonlinear creep model considers the creep coefficient to vary with neutron fluence due to the densification of graphite with neutron irradiation. Within the range of neutron fluence involved (up to 0.53 times 10^{26} neutrons/m ^2, E > 50 KeV), both models were capable of explaining about 96% and 80% of the variation of the irradiation-induced creep strain with neutron fluence at temperatures of 600^circC and 900^circC, respectively. Temperature and reactor power data were analyzed to determine the best estimates for the actual irradiation temperatures. It was determined according to thermocouple readouts that the best estimate values for the irradiation temperatures were well within +/-10 ^circC of the design temperatures of 600^circC and 900 ^circC. The dependence of the secondary creep coefficients (for both linear and nonlinear models) on irradiation temperature was determined assuming that the variation of creep coefficient with temperature, in the temperature range studied, is reasonably linear. It was concluded that the variability in estimate of the creep coefficients is definitely not the results of temperature fluctuations in the experiment. The coefficients for the constitutive equation describing the overall growth of grade H-451 graphite were also studied. It was revealed that the modulus of elasticity and the shear modulus are not affected by creep and that the electrical resistivity is slightly (less than 5%) changed by creep. However, the coefficient of thermal expansion does change with creep. The consistency of

  16. Sophisticated visualization algorithms for analysis of multidimensional experimental nuclear spectra

    International Nuclear Information System (INIS)

    Morhac, M.; Kliman, J.; Matousek, V.; Turzo, I.

    2004-01-01

    This paper describes graphical models of visualization of 2-, 3-, 4-dimensional scalar data used in nuclear data acquisition, processing and visualization system developed at the Institute of Physics, Slovak Academy of Sciences. It focuses on presentation of nuclear spectra (histograms). However it can be successfully applied for visualization of arrays of other data types. In the paper we present conventional as well as new developed surface and volume rendering visualization techniques used (Authors)

  17. Opioid binding site in EL-4 thymoma cell line

    Energy Technology Data Exchange (ETDEWEB)

    Fiorica, E.; Spector, S.

    1988-01-01

    Using EL-4 thymoma cell-line we found a binding site similar to the k opioid receptor of the nervous system. The Scatchard analysis of the binding of (/sup 3/H) bremazocine indicated a single site with a K/sub D/ = 60 +/- 17 nM and Bmax = 2.7 +/- 0.8 pmols/10/sup 6/ cells. To characterize this binding site, competition studies were performed using selective compounds for the various opioid receptors. The k agonist U-50,488H was the most potent displacer of (/sup 3/H) bremazocine with an IC/sub 50/ value = 0.57..mu..M. The two steroisomers levorphanol and dextrorphan showed the same affinity for this site. While morphine, (D-Pen/sup 2/, D-Pen/sup 5/) enkephalin and ..beta..-endorphin failed to displace, except at very high concentrations, codeine demonstrated a IC/sub 50/ = 60..mu..M, that was similar to naloxone. 32 references, 3 figures, 2 tables.

  18. Study of pressure losses in the EL 4 cluster

    International Nuclear Information System (INIS)

    Berriaud, Ch.

    1964-01-01

    The evolution of research on the EL-4 cluster is examined here from the pressure losses point of view. These may be split up into separate pressure losses along the rode and in pressure losses corresponding to various particularities of the cluster. Tests have been carried out on series of three or four clusters placed in a channel. Water was first used, and then carbon dioxide at 60 bars. In all cases the following two parameters were varied: the Reynolds' number, and the rotation of a cluster around its axis with respect to the surrounding clusters. The influence of the gap between to successive clusters has also been studied. The first tests were carried out on clusters without jackets, the subsequent ones on clusters fitted with jackets. It was thus possible to study various types of element assemblies. The results are given in the form of curves representing: the evolution of the independent pressure loss coefficients as a function of the Reynolds number. (author) [fr

  19. Limits on the experimental simulation of nuclear fuel rod response

    International Nuclear Information System (INIS)

    Hagar, R.C.

    1980-01-01

    The steady-state and transient effects of intrinxic geometric and material property differences between typical nuclear fuel pins and electric fuel pin simulators (FPSs) are identified. The effectiveness of varying the transient power supplied to the FPS in reducing the differences between the transient responses of nuclear fuel pins and FPSs is investigated. This effectiveness is shown to be limited by the heat capacity of the FPS, the allowed range of the power program, and different FPS power requirements at different positions on a full-length FPS

  20. Review of nuclear data improvement needs for nuclear radiation measurement techniques used at the CEA experimental reactor facilities

    Directory of Open Access Journals (Sweden)

    Destouches Christophe

    2016-01-01

    Full Text Available The constant improvement of the neutron and gamma calculation codes used in experimental nuclear reactors goes hand in hand with that of the associated nuclear data libraries. The validation of these calculation schemes always requires the confrontation with integral experiments performed in experimental reactors to be completed. Nuclear data of interest, straight as cross sections, or elaborated ones such as reactivity, are always derived from a reaction rate measurement which is the only measurable parameter in a nuclear sensor. So, in order to derive physical parameters from the electric signal of the sensor, one needs specific nuclear data libraries. This paper presents successively the main features of the measurement techniques used in the CEA experimental reactor facilities for the on-line and offline neutron/gamma flux characterizations: reactor dosimetry, neutron flux measurements with miniature fission chambers and Self Power Neutron Detector (SPND and gamma flux measurements with chamber ionization and TLD. For each technique, the nuclear data necessary for their interpretation will be presented, the main identified needs for improvement identified and an analysis of their impact on the quality of the measurement. Finally, a synthesis of the study will be done.

  1. Nuclear magnetic resonance. Present results and its application to renal pathology. Experimental study of hydronephrosis

    International Nuclear Information System (INIS)

    Bertrand, P.

    1987-01-01

    Results of proton nuclear magnetic resonance imaging and relaxation time measurement of experimental hydronephrosis in mice are presented. The study is preceded by a description of the physical principles underlying the phenomenon of nuclear magnetic resonance and of its biomedical applications and with a review of the clinical use of NMR imaging in renal pathology [fr

  2. Nuclear fusion experimental study on 16 O + 60 Ni system

    International Nuclear Information System (INIS)

    Silva, C.P. da.

    1990-01-01

    Nuclear fusion cross section measurements were performed in the energy range near The Coulomb Barrier (E Lab -> 40-72 MeV), for the system 16 O + 60 Ni, aiming the study of Fusion Process involving heavy ions. (L.C.J.A.)

  3. Experimental examination of ternary fission in nuclear track emulsion

    Czech Academy of Sciences Publication Activity Database

    Mamatkulov, K. Z.; Ambrožová, Iva; Artemenkov, D. A.; Bradnova, V.; Firu, E.; Haiduc, M.; Kákona, Martin; Kattabekov, R. R.; Marey, A.; Neagu, A.; Ploc, Ondřej; Rusakova, V. V.; Stanoeva, R.; Turek, Karel; Zaitsev, A. A.; Zarubin, P. I.; Zarubina, I. G.

    2017-01-01

    Roč. 48, č. 6 (2017), s. 910-913 ISSN 1063-7796 Institutional support: RVO:61389005 Keywords : angular correlation * nuclear track emulsion Subject RIV: BF - Elementary Particles and High Energy Physics OBOR OECD: Particles and field physics Impact factor: 0.681, year: 2016

  4. Few-Body Problems in Experimental Nuclear Astrophysics

    DEFF Research Database (Denmark)

    Fynbo, H.O.U.

    2013-01-01

    The 3α-reaction is one of the key reactions in nuclear astrophysics. Since it is a three-body reaction direct measurement is impossible, and therefore the reaction rate must be estimated theoretically. In this contribution I will discuss uncertainties in this reaction rate both at very low...

  5. The inhibition of apoptosis in EL4 lymphoma cells overexpressing growth hormone.

    Science.gov (United States)

    Arnold, Robyn E; Weigent, Douglas A

    2004-01-01

    The antiapoptotic action of exogenous growth hormone (GH) has been reported for several lymphoid cell lines; however, the potential role of endogenous GH in apoptosis has not been thoroughly investigated. This study was designed to investigate the effects of endogenous GH on apoptosis induced by methyl methanesulfonate (MMS) in a T cell lymphoma overexpressing GH (GHo). The results of these experiments have shown that in EL4 lymphoma cells, overexpression of GH sustained viability after exposure to MMS compared to control cells. The extent of DNA fragmentation measured by ladder formation on agarose gels was reduced in GHo cells following treatment with MMS, when compared to control cells. Adding exogenous GH to control cells and treatment of GHo cells with antibodies to GH had no effect on MMS-induced DNA ladder formation. In further studies, DNA microarray analysis suggested a marked decrease in the constitutive expression of bax, BAD, and caspases 3, 8, and 9 in GHo cells compared to controls. In addition, after treatment with MMS, the activities of caspases 2, 3, 6, 8, and 9 were all lower than control in GHo cells. Western blot analysis detected an increase in Bcl-2 while the levels of nuclear factor kappa B (NFkappaB) remained unchanged in GHo cells. Treatment of EL4 cells with antisense deoxyoligonucleotides to GH and specific inhibitors of NFkappaB (SN-50) increased DNA fragmentation. GHo cells show increased levels of phosphorylated Akt and GSK-3, suggesting inactivation of this proapoptotic protein. The results, taken together with our previous data which showed increased nitric oxide formation in GHo cells, suggest a possible mechanism for the antiapoptotic effects of endogenous GH through the production of nitric oxide and support the idea that endogenous GH may play an important role in the survival of lymphocytes exposed to stressful stimuli. Copyright 2004 S. Karger AG, Basel

  6. Experimental status of the nuclear spin scissors mode

    Science.gov (United States)

    Balbutsev, E. B.; Molodtsova, I. V.; Schuck, P.

    2018-04-01

    With the Wigner function moments (WFM) method the scissors mode of the actinides and rare earth nuclei are investigated. The unexplained experimental fact that in 232Th a double hump structure is found finds a natural explanation within WFM. It is predicted that the lower peak corresponds to an isovector spin scissors mode whereas the higher-lying states corresponds to the conventional isovector orbital scissors mode. The experimental situation is scrutinized in this respect concerning practically all results of M 1 excitations.

  7. Nuclear Physics Division - Inst. of Experimental Physics - Warsaw University - Annual Report 2001

    International Nuclear Information System (INIS)

    Kirejczyk, M.

    2001-01-01

    In the presented report the research activities of Nuclear Physics Division (NPD) of the Warsaw University Institute of Experimental Physics in year of 2001 are described. The report is divided into three parts: Reaction Mechanisms and Nuclear Structure, Experimental Methods and Instrumentation and the third one which contain the lists of personnel, seminars held at the Nuclear Physics Division and list of published papers. A summary of the (NPD) activities are briefly presented in ''Preface'' written by NPD director prof. K. Siwek-Wilczynska

  8. FFTF reload core nuclear design for increased experimental capability

    International Nuclear Information System (INIS)

    Rothrock, R.B.; Nelson, J.V.; Dobbin, K.D.; Bennett, R.A.

    1976-01-01

    In anticipation of continued growth in the FTR experimental irradiations program, the enrichments for the next batches of reload driver fuel to be manufactured have been increased to provide a substantially enlarged experimental reactivity allowance. The enrichments for these fuel assemblies, termed ''Cores 3 and 4,'' were selected to meet the following objectives and constraints: (1) maintain a reactor power capability of 400 MW (based on an evaluation of driver fuel centerline melting probability at 15 percent overpower); (2) provide a peak neutron flux of nominally 7 x 10 15 n/cm 2 -sec, with a minimum acceptable value of 95 percent of this (i.e., 6.65 x 10 15 n/cm 2 -sec); and (3) provide the maximum experimental reactivity allowance that is consistent with the above constraints

  9. Influence of operation of national experimental nuclear reactor on the natural environment

    Directory of Open Access Journals (Sweden)

    Agnieszka Kaczmarek-Kacprzak

    2012-09-01

    Full Text Available This paper presents the impact of experimental nuclear reactor operations on the national environment, based on assessment reports of the radiological protection of active nuclear technology sources. Using the analysis of measurements carried out in the last 15 years, the trends are presented in selected elements of the environment on the Świerk Nuclear Centre site and its surroundings. In addition, the impact of research results is presented from the fi fteen year period of environmental analysis on building public confi dence on the eve of the start of construction of the first Polish nuclear power plant.

  10. Nuclear engineering experiments at experimental facilities of JNC in graduate course of Tokyo Institute of Technology

    International Nuclear Information System (INIS)

    Hayashizaki, Noriyosu; Takahashi, Minoru; Aoyama, Takafumi; Onose, Shoji

    2005-01-01

    Nuclear engineering experiments using outside facilities of the campus have been offered for graduate students in the nuclear engineering course in Tokyo Institute of Technology (Tokyo Tech.). The experiments are managed with the collaboration of Japan Nuclear Cycle Development Institute (JNC), Japan Atomic Energy Research Institute (JAERI) and Research Reactor Institute, Kyoto University (KUR). This report presents the new curriculum of the nuclear engineering experiments at JNC since 2002. The change is due to the shutdown of Deuterium Criticality Assembly Facility (DCA) that was used as an experimental facility until 2001. Reactor physics experiment using the training simulator of the experimental fast reactor JOYO is continued from the previous curriculum with the addition of the criticality approach experiment and control rods calibration. A new experimental subject is an irradiated material experiment at the Material Monitoring Facility (MMF). As a result, both are acceptable as the student experiments on the fast reactor. (author)

  11. The experimental nuclear reaction data (EXFOR): Extended computer database and Web retrieval system

    Science.gov (United States)

    Zerkin, V. V.; Pritychenko, B.

    2018-04-01

    The EXchange FORmat (EXFOR) experimental nuclear reaction database and the associated Web interface provide access to the wealth of low- and intermediate-energy nuclear reaction physics data. This resource is based on numerical data sets and bibliographical information of ∼22,000 experiments since the beginning of nuclear science. The principles of the computer database organization, its extended contents and Web applications development are described. New capabilities for the data sets uploads, renormalization, covariance matrix, and inverse reaction calculations are presented. The EXFOR database, updated monthly, provides an essential support for nuclear data evaluation, application development, and research activities. It is publicly available at the websites of the International Atomic Energy Agency Nuclear Data Section, http://www-nds.iaea.org/exfor, the U.S. National Nuclear Data Center, http://www.nndc.bnl.gov/exfor, and the mirror sites in China, India and Russian Federation.

  12. Elise: a new facility for unprecedented experimental nuclear fission studies

    International Nuclear Information System (INIS)

    Taieb, J.; Belier, G.; Chatillon, A.; Granier, T.; Kelic, A.; Ricciardi, V.; Schmidt, K.H.; Voss, B.; Coste-Delclaux, M.; Diop, C.; Jouanne, C.; Schmitt, C.; Aiche, M.; Czajkowski, S.; Jurado, B.; Audouin, L.; Peyre, J.; Rosier, P.; Tassan-Got, L.; Bertoumieux, E.; Dore, D.; Dupont, E.; Letourneau, A.; Panebianco, S.

    2009-01-01

    A novel experimental program aiming to study the properties of fragments and neutrons emitted in the fission process has been initiated. The experiment will be held at the ELISe electron-ion collider to be constructed at GSI, Darmstadt in the framework of the FAIR extension of the facility. The experiment will take advantage of the inverse kinematics allowing, in particular, a total mass and charge resolution for all fission fragments. (authors)

  13. English Language for Teachers (EL4T): a course for EFL teachers

    OpenAIRE

    Shrestha, Prithvi

    2013-01-01

    This paper reports on the design and implementation of EL4T in a large-scale project. EL4T is a self-study mobile technology-based ESP course designed to enhance Bangladeshi school English language teachers’ English language skills and pedagogical practices. Key implications of developing this course for ESP in EFL contexts will be presented.

  14. Differential downstream functions of protein kinase Ceta and -theta in EL4 mouse thymoma cells.

    Science.gov (United States)

    Resnick, M S; Kang, B S; Luu, D; Wickham, J T; Sando, J J; Hahn, C S

    1998-10-16

    Sensitive EL4 mouse thymoma cells (s-EL4) respond to phorbol esters with growth inhibition, adherence to substrate, and production of cytokines including interleukin 2. Since these cells express several of the phorbol ester-sensitive protein kinase C (PKC) isozymes, the function of each isozyme remains unclear. Previous studies demonstrated that s-EL4 cells expressed substantially more PKCeta and PKCtheta than did EL4 cells resistant to phorbol esters (r-EL4). To examine potential roles for PKCeta and PKCtheta in EL4 cells, wild type and constitutively active versions of the isozymes were transiently expressed using a Sindbis virus system. Expression of constitutively active PKCeta, but not PKCtheta, in s- and r-EL4 cells altered cell morphology and cytoskeletal structure in a manner similar to that of phorbol ester treatment, suggesting a role for PKCeta in cytoskeletal organization. Prolonged treatment of s-EL4 cells with phorbol esters results in inhibition of cell cycling along with a decreased expression of most of the PKC isozymes, including PKCtheta. Introduction of virally expressed PKCtheta, but not PKCeta, overcame the inhibitory effects of the prolonged phorbol ester treatment on cell cycle progression, suggesting a possible involvement of PKCtheta in cell cycle regulation. These results support differential functions for PKCeta and PKCtheta in T cell activation.

  15. Nuclear fission: a review of experimental advances and phenomenology

    Science.gov (United States)

    Andreyev, A. N.; Nishio, K.; Schmidt, K.-H.

    2018-01-01

    In the last two decades, through technological, experimental and theoretical advances, the situation in experimental fission studies has changed dramatically. With the use of advanced production and detection techniques both much more detailed and precise information can now be obtained for the traditional regions of fission research and, crucially, new regions of nuclei have become routinely accessible for fission studies. This work first of all reviews the recent developments in experimental fission techniques, in particular the resurgence of transfer-induced fission reactions with light and heavy ions, the emerging use of inverse-kinematic approaches, both at Coulomb and relativistic energies, and of fission studies with radioactive beams. The emphasis on the fission-fragment mass and charge distributions will be made in this work, though some of the other fission observables, such as prompt neutron and γ-ray emission will also be reviewed. A particular attention will be given to the low-energy fission in the so far scarcely explored nuclei in the very neutron-deficient lead region. They recently became the focus for several complementary experimental studies, such as β-delayed fission with radioactive beams at ISOLDE(CERN), Coulex-induced fission of relativistic secondary beams at FRS(GSI), and several prompt fusion–fission studies. The synergy of these approaches allows a unique insight in the new region of asymmetric fission around {\\hspace{0pt}}180 Hg, recently discovered at ISOLDE. Recent extensive theoretical efforts in this region will also be outlined. The unprecedented high-quality data for fission fragments, completely identified in Z and A, by means of reactions in inverse kinematics at FRS(GSI) and VAMOS(GANIL) will be also reviewed. These experiments explored an extended range of mercury-to-californium elements, spanning from the neutron-deficient to neutron-rich nuclides, and covering both asymmetric, symmetric and transitional fission regions

  16. Experimental nuclear physics. Progress report, June 1974--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Research programs in the following areas are described: inclusive particle and gamma emission resulting from in-flight pion and proton nuclear reactions; elastic and inelastic π + scattering at 25, 50, and 75 MeV; pion absorption reactions A(π,d)B; and inelastic scattering to giant E2 resonances. Work on the computer and data acquisition systems for EPICS is briefly discussed. Short descriptions are given of work under the following headings: theoretical analysis, intrinsic Ge charged-particle spectrometer, scattering stand, data acquisition system at Carnegie-Mellon University, strong interaction effects in antiprotonic atoms, and anti pp and K - p atomic systems. Papers describing completed work have been submitted for publication. A list of publications, reports, theses, proposals, and talks is included. (6 figures, 1 table) (U.S.)

  17. Experimental nuclear physics. Progress report, September 1980-June 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Continuing cooperative research is reported in the areas of, a) In-beam γ-ray spectroscopy with scientists at Oak Ridge and the University of Koeln; b) Coulomb excitation studies at Lawrence Berkeley Laboratory and at GSI, Darmstadt, Germany; c) Maxsive transfer and preequilibrium emission processes in fusion reactions at ORNL; d) Nucleon transfer reaction studies with scientists at ORNL, Los Alamos and Brookhaven; e) delta-electron spectroscopy at the Mas Planck Institute in Heidelberg; f) Heavy ion atomic physics at the ORNL En tandem; g) Studies of nuclei far from stability at UNISOR; and h) Theoretical studies of high spin phenomena with scientists at Lawrence Berkeley, Brookhaven Lab., Univ. of Tubingen, and Copenhagen and of nuclear molecules and their decay processes in very heavy ion collisions with the University of Frankfurt and Vanderbilt theorists. Abstracts of papers published or submitted for publication are presented, and brief reports of work in process are given

  18. Numerical and experimental investigations of water hammers in nuclear industry

    Directory of Open Access Journals (Sweden)

    R Messahel

    2016-10-01

    Full Text Available In nuclear and petroleum industries, supply pipes are often exposed to high pressure loading which can cause to the structure high strains, plasticity and even, in the worst scenario, failure. Fast Hydraulic Transient phenomena such as Water Hammers (WHs are of this type. It generates a pressure wave that propagates in the pipe causing high stress. Such phenomena are of the order of few msecs and numerical simulation can offer a better understanding and an accurate evaluation of the dynamic complex phenomenon including fluid-structure interaction, multi-phase flow, cavitation … For the last decades, the modeling of phase change taking into account the cavitation effects has been at the centre of many industrial applications (chemical engineering, mechanical engineering, … and has a direct impact on the industry as it might cause damages to the installation (pumps, propellers, control valves, …. In this paper, numerical simulation using FSI algorithm and One-Fluid Cavitation models ("Cut-Off" and "HEM (Homogeneous Equilibrium Model Phase-Change" introduced by Saurel et al. [1] of WHs including cavitation effects is presented.

  19. Resveratrol (trans-3,5,4'-trihydroxystilbene) suppresses EL4 tumor growth by induction of apoptosis involving reciprocal regulation of SIRT1 and NF-κB.

    Science.gov (United States)

    Singh, Narendra P; Singh, Udai P; Hegde, Venkatesh L; Guan, Hongbing; Hofseth, Lorne; Nagarkatti, Mitzi; Nagarkatti, Prakash S

    2011-08-01

    Understanding the molecular mechanisms through which natural products and dietary supplements exhibit anticancer properties is crucial and can lead to drug discovery and chemoprevention. The current study sheds new light on the mode of action of resveratrol (RES), a plant-derived polyphenolic compound, against EL-4 lymphoma growth. Immuno-compromised NOD/SCID mice injected with EL-4 tumor cells and treated with RES (100 mg/kg body weight) showed delayed development and progression of tumor growth and increased mean survival time. RES caused apoptosis in EL4 cells through activation of aryl hydrocarbon receptor (AhR) and upregulation of Fas and FasL expression in vitro. Blocking of RES-induced apoptosis in EL4 cells by FasL mAb, cleavage of caspases and PARP, and release of cytochorme c, demonstrated the participation of both extrinsic and intrinsic pathways of apoptosis. RES also induced upregulation of silent mating type information regulation 2 homolog, 1 (SIRT1) and downregulation of nuclear factor kappa B (NF-κB) in EL4 cells. siRNA-mediated downregulation of SIRT1 in EL4 cells increased the activation of NF-κB but decreased RES-mediated apoptosis, indicating the critical role of SIRT1 in apoptosis via blocking activation of NF-κB. These data suggest that RES-induced SIRT1 upregulation promotes tumor cell apoptosis through negative regulation of NF-κB, leading to suppression of tumor growth. Copyright © 2011 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  20. Summary Report of the Workshop on the Experimental Nuclear Reaction Data Database

    International Nuclear Information System (INIS)

    Semkova, V.; Pritychenko, B.

    2014-12-01

    The Workshop on the Experimental Nuclear Reaction Data Database (EXFOR) was held at IAEA Headquarters in Vienna from 6 to 10 October 2014. The workshop was organized to discuss various aspects of the EXFOR compilation process including compilation rules, different techniques for nuclear reaction data measurements, software developments, etc. A summary of the presentations and discussions that took place during the workshop is reported here. (author)

  1. Summary Report of the Workshop on The Experimental Nuclear Reaction Data Database

    Energy Technology Data Exchange (ETDEWEB)

    Semkova, V. [IAEA Nuclear Data Section, Vienna (Austria); Pritychenko, B. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2014-12-01

    The Workshop on the Experimental Nuclear Reaction Data Database (EXFOR) was held at IAEA Headquarters in Vienna from 6 to 10 October 2014. The workshop was organized to discuss various aspects of the EXFOR compilation process including compilation rules, different techniques for nuclear reaction data measurements, software developments, etc. A summary of the presentations and discussions that took place during the workshop is reported here.

  2. Methods and benefits of experimental seismic evaluation of nuclear power plants. Final report

    International Nuclear Information System (INIS)

    1979-07-01

    This study reviews experimental techniques, instrumentation requirements, safety considerations, and benefits of performing vibration tests on nuclear power plant containments and internal components. The emphasis is on testing to improve seismic structural models. Techniques for identification of resonant frequencies, damping, and mode shapes, are discussed. The benefits of testing with regard to increased damping and more accurate computer models are oulined. A test plan, schedule and budget are presented for a typical PWR nuclear power plant

  3. EXFOR – a global experimental nuclear reaction data repository: Status and new developments

    Directory of Open Access Journals (Sweden)

    Semkova Valentina

    2017-01-01

    Full Text Available Members of the International Network of Nuclear Reaction Data Centres (NRDC have collaborated since the 1960s on the worldwide collection, compilation and dissemination of experimental nuclear reaction data. New publications are systematically complied, and all agreed data assembled and incorporated within the EXFOR database. Recent upgrades to achieve greater completeness of the contents are described, along with reviews and adjustments of the compilation rules for specific types of data.

  4. Methods and benefits of experimental seismic evaluation of nuclear power plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1979-07-01

    This study reviews experimental techniques, instrumentation requirements, safety considerations, and benefits of performing vibration tests on nuclear power plant containments and internal components. The emphasis is on testing to improve seismic structural models. Techniques for identification of resonant frequencies, damping, and mode shapes, are discussed. The benefits of testing with regard to increased damping and more accurate computer models are oulined. A test plan, schedule and budget are presented for a typical PWR nuclear power plant.

  5. Aero thermal test results obtained on the n. C 5 EL 4 Cluster in the atmospheric pressure cell

    International Nuclear Information System (INIS)

    Gasc, B.

    1964-01-01

    In the framework of thermal studies on the EL-4 cluster, the full-scale tests at atmospheric pressure are designed to permit measurement of local values of the wall temperature, of the velocity and of the temperature in the fluid. The experimental results, obtained with the help of an original measuring apparatus, make it possible to follow the changes in these values along the cluster and to predict in much detail the in-pile thermal behaviour. In particular it is shown that changes in the wall temperature along the cluster are greatly influenced by disruption of the flow caused by grids and supports. (author) [fr

  6. Nuclear Physics Division Institute of Experimental Physics Warsaw University annual report 1994

    Energy Technology Data Exchange (ETDEWEB)

    Osuch, S. [ed.

    1995-12-31

    In the presented Annual Report the activities of the Nuclear Physics Division of the Institute of Experimental Physics of the Warsaw University in 1994 are described. The report consist of three sections: (i) Reaction Mechanism and Nuclear Structure (12 articles); (ii) Experimental Methods and Instrumentation (2 articles); (iii) Other Research (1 article). Additionally the list of seminars held at the NPD, personnel list and list of published papers is also given. In the first, leading article of the report written by head of NPD prof. Ch. Droste the general description of the Department activity is presented.

  7. Nuclear Physics Division Institute of Experimental Physics Warsaw University annual report 1994

    International Nuclear Information System (INIS)

    Osuch, S.

    1995-01-01

    In the presented Annual Report the activities of the Nuclear Physics Division of the Institute of Experimental Physics of the Warsaw University in 1994 are described. The report consist of three sections: i) Reaction Mechanism and Nuclear Structure (12 articles); ii) Experimental Methods and Instrumentation (2 articles); iii) Other Research (1 article). Additionally the list of seminars held at the NPD, personnel list and list of published papers is also given. In the first, leading article of the report written by head of NPD prof. Ch. Droste the general description of the Department activity is presented

  8. Experimental model of the device for detection of nuclear cycle materials by photoneutron technology

    International Nuclear Information System (INIS)

    Bakalyarov, A.M.; Karetnikov, M.D.; Kozlov, K.N.; Lebedev, V.I.; Meleshko, E.A.; Obinyakov, B.A.; Ostashev, I.E.; Tupikin, N.A.; Yakovlev, G.V.

    2007-01-01

    The inherent complexity of sea container control makes them potentially dangerous for smuggling nuclear materials. The experts believe that only active technologies based on recording the products of induced radiation from sensitive materials might solve the problem. The paper reports on the experimental model of the device on the basis of the electron LINAC U-28 for detection of nuclear materials by photonuclear technology. The preliminary numerical optimization of output units (converter, filter, collimator) for shaping the bremsstrahlung was carried out. The setup of experimental device and initial results of recording the prompt and delayed fission products are discussed

  9. Archival and Dissemination of the U.S. and Canadian Experimental Nuclear Reaction Data (EXFOR Project)

    Science.gov (United States)

    Pritychenko, Boris; Hlavac, Stanislav; Schwerer, Otto; Zerkin, Viktor

    2017-09-01

    The Exchange Format (EXFOR) or experimental nuclear reaction database and the associated Web interface provide access to the wealth of low- and intermediate-energy nuclear reaction physics data. This resource includes numerical data sets and bibliographical information for more than 22,000 experiments since the beginning of nuclear science. Analysis of the experimental data sets, recovery and archiving will be discussed. Examples of the recent developments of the data renormalization, uploads and inverse reaction calculations for nuclear science and technology applications will be presented. The EXFOR database, updated monthly, provides an essential support for nuclear data evaluation, application development and research activities. It is publicly available at the National Nuclear Data Center website http://www.nndc.bnl.gov/exfor and the International Atomic Energy Agency mirror site http://www-nds.iaea.org/exfor. This work was sponsored in part by the Office of Nuclear Physics, Office of Science of the U.S. Department of Energy under Contract No. DE-AC02-98CH10886 with Brookha ven Science Associates, LLC.

  10. Experimental Guidance of ISB Corrections via Direct Nuclear Reactions

    Science.gov (United States)

    Leach, K. G.; Garrett, P. E.; Ball, G. C.; Bangay, J. C.; Bianco, L.; Demand, G. A.; Faestermann, T.; Finlay, P.; Green, K. L.; Hertenberger, R.; Kriicken, R.; Phillips, A. A.; Rand, E. T.; Sumithrarachchi, C. S.; Svensson, C. E.; Towner, I. S.; Triambak, S.; Wirth, H.-F.; Wong, J.

    2011-09-01

    The most recent isospin-symmetry-breaking corrections, δc, of Towner and Hardy for superallowed Fermi β-decay transitions, have included the opening of specific core orbitals. This change has resulted in significant deviations in some of the δc factors from their previous calculations, and an improved agreement of the individual corrected Script Ft values with the overall world average of the 13 most precise cases. While this is consistent with the conserved-vector-current (CVC) hypothesis of the Standard Model, these new calculations must be thoroughly tested, and guidance must be given for the improvement of calculations for the upper-pf shell nuclei. Using the (d,t) reaction mechanism to probe the single neutron wavefunction overlap, information regarding the relevant shell-model configurations needed in the calculation can be determined. An experiment was therefore performed with a 22 MeV polarized deuterium beam from the MP tandem Van de Graaff accelerator in Munich, Germany. Using the Q3D magnetic spectrograph, and a cathode-strip focal-plane detector, outgoing tritons were analyzed at 9 angles between 10° and 60°, up to an excitation energy of 4.8 MeV. This proceeding reports the motivational and experimental details for the 64Zn(d,t)63Zn transfer work presented.

  11. Controlled Nuclear Fusion Research, September 1965: Review Of Experimental Results

    Energy Technology Data Exchange (ETDEWEB)

    Spitzer, Lyman Jr. [Princeton University, Princeton, NJ (United States)

    1966-04-15

    To my way of thinking the most significant milestone of the present meeting is the substantial body of evidence that has been presented on the hydromagnetic stabilization of open-ended systems. The success of minimum magnetic-field ('minimum-B') configurations in stabilizing a plasma marks one more area where theory and experiment in the field of plasma physics have been brought together with gratifying results. Let me go back a little into history and discuss the gradual growth of our information on hydromagnetic instabilities generally. Many of you will remember that hydromagnetic theory was applied to the self-pinched discharge in the early years of the controUed fusion programme. The predictions of this theory were very shortly fulfilled by the observations; the effects were so unmistakable that it was not difficult to compare the theory with the observations. On the streak pictures of the linear or toroidal discharges that were obtained in those early years one saw clearly the diffuse plasma column, which first contracted to a narrow filament and then started to distort and kink until finally it hit the wall. Under some conditions the plasma was observed to break up into a series of blobs like a string of sausages. Since the behaviour was exactly what the theory had predicted, it took no very great experimental wisdom to conclude that observations had confirmed theory.

  12. Data taking and processing system for nuclear experimental physics study

    International Nuclear Information System (INIS)

    Nagashima, Y.; Kimura, H.; Katori, K.; Kuriyama, K.

    1979-01-01

    A multi input, multi mode, multi user data taking and processing system was developed. This system has following special features. 1) It is multi computer system which is constitute with two special processors and two mini computers. 2) The pseudo devices are introduced to make operating procedurs simply and easily. Especially, the selection or modification of 1 - 8 coincidence mode can be done very easily and quickly. 3) A 16 Kch spectrum storage has 8 partitions. Every partitions having floating size are handled automatically by the data taking software SHINE. 4) On line real time data processing can be done. Useing the FORTRAN language, user may prepare the processing software apart from the data taking software. Under the RSX-11D system software, this software runs concurrently with the data taking software by a multi programming mode. 5) The data communication between arbitraly external devices and this system can be done. With this communication procedures, not only the data transfer between computers, but also the control of the experimental devices are realized. Like the real time processing software, this software can be prepared by users and be ran concurrently with other softwares. 6) For data monitoring, two different graphic displays are used complementally. One is a refresh typed high speed display. The other is a storage typed large screen display. Raw datas are displayed on the former. Processed datas or multi parametric large volume datas are displayed on the later one. (author)

  13. Establishment of Experimental Equipment for Training of Professionals in the Nuclear Radiation Measurement

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, S. K.; Seo, K. W.; Joo, Y. C.; Kim, I. C.; Woo, C. K.; Yoo, B. H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-09-15

    The main purpose of this project is to establish experimental equipment for training of professionals and students in the field of radiation measurement, and settle the foundation for the advanced education system and program. The priority for the experimental equipment had been deduced by reviewing of the Nuclear Training and Education Center of KAERI and other country's training courses. Equipment for training of radiation professionals are High-Purity Germanium spectroscopic systems, alpha analyzers, and hand-held gamma/neutron inspector systems. For the basic experiments, electric personal dosimeters and a reader, radiation survey meters, and various alpha, beta and gamma radiation isotopes have been equipped. Some old or disused equipment and devices were disposed and re-arranged, and a new experiment lab had been settled for gamma spectroscopy. Along with the preparation of equipment, 14 experimental modules have been selected for practical and essential experiments training to professionals from industries, universities and research organizations. Among the modules, 7 important experiment notes had been prepared in Korea and also in English. As a consequence, these advanced radiation experimental setting would be a basis to cooperate with IAEA or other countries for international training courses. These activities would be a foundation for our contribution to the international nuclear society and for improving our nuclear competitiveness. The experimental equipment and application notes developed in this study will be used also by other training institutes and educational organizations through introducing and encouraging to use them to the nuclear society.

  14. Establishment of Experimental Equipment for Training of Professionals in the Nuclear Radiation Measurement

    International Nuclear Information System (INIS)

    Ahn, S. K.; Seo, K. W.; Joo, Y. C.; Kim, I. C.; Woo, C. K.; Yoo, B. H.

    2008-09-01

    The main purpose of this project is to establish experimental equipment for training of professionals and students in the field of radiation measurement, and settle the foundation for the advanced education system and program. The priority for the experimental equipment had been deduced by reviewing of the Nuclear Training and Education Center of KAERI and other country's training courses. Equipment for training of radiation professionals are High-Purity Germanium spectroscopic systems, alpha analyzers, and hand-held gamma/neutron inspector systems. For the basic experiments, electric personal dosimeters and a reader, radiation survey meters, and various alpha, beta and gamma radiation isotopes have been equipped. Some old or disused equipment and devices were disposed and re-arranged, and a new experiment lab had been settled for gamma spectroscopy. Along with the preparation of equipment, 14 experimental modules have been selected for practical and essential experiments training to professionals from industries, universities and research organizations. Among the modules, 7 important experiment notes had been prepared in Korea and also in English. As a consequence, these advanced radiation experimental setting would be a basis to cooperate with IAEA or other countries for international training courses. These activities would be a foundation for our contribution to the international nuclear society and for improving our nuclear competitiveness. The experimental equipment and application notes developed in this study will be used also by other training institutes and educational organizations through introducing and encouraging to use them to the nuclear society

  15. Updating and using the international non-neutron experimental nuclear data base in ''Generalized EXFOR'' format

    International Nuclear Information System (INIS)

    Zhuravleva, G.M.; Chukreev, F.E.

    1985-10-01

    A software system for the automatic preparation of non-formalized textual information for the international exchange of nuclear data in the ''Generalized Exchange Format (EXFOR)'' is described. The ''Generalized EXFOR'' format is briefly outlined and data are given on the size of the international non-neutron experimental data base in this format. (author)

  16. Overview of experimental work to ensure innovation of nuclear fuel for future advanced PWRs

    International Nuclear Information System (INIS)

    Zymak, J.; Valach, M.; Hejna, J.

    2002-11-01

    It is envisaged that advanced nuclear fuel will be operated in high burnup conditions, at a high linear power and at considerable mechanical fuel-cladding interactions. The report gives an overview of experimental work investigating phenomena that will affect APWR fuel, such as the manufacturing technology, thermal properties and safety requirements

  17. Experimental investigation into the seismic behavior of nuclear power plant shear wall structures

    International Nuclear Information System (INIS)

    Kenneally, R.M.; Burns, J.J. Jr.

    1988-01-01

    Nuclear power plant structures are designed to resist large earthquakes. However, as new data are obtained on earthquake activity throughout the United States, plant design earthquake levels have increased. The U.S. Nuclear Regulatory Commission is sponsoring an analytical-experimental research program to obtain information on the strucutral response of nuclear power plant shear wall strucutres subjected to earthquake motions within and beyond their design basis. Using different size scale models constructed with microconcrete and prototypical concrete this research has demonstrated consistent results for measured values of stiffness at load levels within the design basis. Furthermore, the values are well below the theoretical stiffnesses calculated from an uncracked cross-section strength-of-materials approach. Current program emphasis is to assess the credibility of previous experimental work by beginning to resolve the 'stiffness difference' issue. (orig.)

  18. Summary of experimental studies on biological effects of radionuclides in Chinese Nuclear Industry

    International Nuclear Information System (INIS)

    Chen Rusong

    1994-11-01

    The experimental studies on the biological effects with internal contamination of radionuclides (Such as Uranium, Plutonium, Tritium, Iodine, Radon and its products, etc.) in the Chinese nuclear industry were summarized systematically. In these studies some institutes in the nuclear industry system and other relevant units in China were involved. The review was carried out in both stochastic and deterministic effects, and focused on the dose-effect relationship. The research work showed that great progress for the experimental studies on biological effects with internal irradiation has been made in China. There is a definite characteristic in a certain extent. It makes contribution to develop the production of nuclear industry and the construction of national economy. Several constructive suggestions of prospects for the work in future were proposed and it will make an attention in the field of radiation protection at home and abroad

  19. Blowing loop in the EL-4 reactor: CO{sub 2} flow control analogue study; Boucle de soufflage de la centrale EL-4 - regulation du debit CO{sub 2} - etude analogique

    Energy Technology Data Exchange (ETDEWEB)

    Chazal, G; Merle, J P; Guillemard, B [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Leroy, C; Robin, L; Jacquin, J C; Cornudet, A [Societe INDATOM, France (France)

    1966-07-01

    This report describes one study which contributed to the construction of the Monts d'Arree nuclear power station: EL-4. The reactor is cooled by a CO{sub 2} current provided by 3 turbo-blower groups. The priming vapour for the turbines is taken at the exit of the main CO{sub 2} - H{sub 2}O exchangers. The operation of EL 4 is based on a high degree of centralization of the controls which attributes an important role to the general regulation circuits. This general regulation includes in particular an internal blowing loop which controls the CO{sub 2} flow. The study of the control of this CO{sub 2} flow is made up of 3 parts: - analogue representation of the reactors cooling circuit and of the turbo blower unit. - first test campaign using the analogue computer describing the natural behaviour of the system in the absence of control. theoretical determination of the regulation factors; definition of the regulation using an analogue computer and second test campaign for recording the performances of the blowing loop. The 4. part of the report deals with the analogue study: analogue equations - development. (authors) [French] Ce rapport prend place parmi les etudes de realisation de la Centrale des Monts d'Arree EL-4. Le reacteur est refroidi par une circulation de CO{sub 2} assuree par 3 groupes turbosoufflantes. La vapeur d'entrainement des turbines est prelevee a la sortie des echangeurs principaux CO{sub 2} - H{sub 2}O. L'exploitation de EL-4 repose sur une centralisation poussee des moyens de controle-commande qui attribue un role essentiel aux circuits de regulation generale. Cette regulation generale comporte en particulier une boucle interne de soufflage qui realise un asservissement du debit de CO{sub 2}. L'etude de cette regulation du debit CO{sub 2} comprend 3 parties: - representation analogique du circuit de refroidissement du reacteur et de l'ensemble turbine-soufflante. - premiere campagne d'essais sur calculateur analogique decrivant le comportement

  20. J.O. no. 10 of the 13 january 2004, page 991, text no. 14. Decrees, orders. General texts. Decree no. 2004-47 of the 12 january 2004 modifying the decree no. 96-978 of the 31 october 1996 relative to the creation of the nuclear installation no. 162 named EL4-D, installation of storage for the Monts d'Arree power plants materials

    International Nuclear Information System (INIS)

    2004-06-01

    The reactor EL4, implemented in december 1966, has definitely shutdown on the 31 july 1985. This reactor was an industrial prototype, built and exploited by Cea and EDF. In the framework of the partial dismantling of the installation, the decree 96-978 of the 31 october 1996 agreed the Cea to modify the installation to become a storage installation. (A.L.B.)

  1. Experimental overview and challenge in strangeness nuclear physics — strangeness in the past and coming decades

    International Nuclear Information System (INIS)

    Imai, Kenichi

    2010-01-01

    A great progress has been made in strangeness nuclear physics in the past decade. Examples are; 1) The "hyperfine" structure of hypernuclei were measured with the Hyperball, and ΛN spin dependent interactions in p-shell hypernuclei were determined. 2) The "complete measurements" of the weak decay of hypernuclei were made and the np ratio puzzle in the non-mesonic decay was solved. 3) The discovery of a clean event of "Lambpha" and determination of its binding energy concluded that the Λ-Λ interaction is weak attractive. However, we still have important questions to be answered in this field, especially in relation with QCD and nuclear physics. For the future strangeness nuclear physics, we have and will have facilities such as JLab, SPring-8, Daphne, J-PARC, FAIR. We discuss experimental challenges in the strangeness nuclear physics and related fields in the next decade. (author)

  2. Can Experimental Scientists, Data Evaluators and Compilers, and Nuclear Data Users Understand One Another?

    International Nuclear Information System (INIS)

    Usachev, L.N.

    1966-01-01

    The International Atomic Energy Agency organizes conferences on a wide variety of scientific subjects, all of which are of fundamental importance for the development of nuclear power. These include the technology of fuel elements, their stability in neutron fields, and chemical reprocessing as well as reactor physics, mathematical computational methods and the problems of protection and dosimetry. The problem of microscopic nuclear data, an essential aspect of reactor work, is just one of these many subjects. On the other hand, it should be remembered that the possibility of releasing nuclear energy was established in the first place by obtaining nuclear data on the fission process occurring in the uranium nucleus following the capture of a neutron and on the escape of the 2-3 secondary fission neutrons. In early nuclear power work the information provided by nuclear data was of considerable, even of decisive, importance. For example, the information available on the neutron balance in fast reactors showed that such reactors could operate as breeders and thus that it was worth while developing them. Strictly speaking, it is of course difficult to speak of a knowledge of nuclear data at this early period. It is perhaps more accurate to speak of the understanding of and the feeling for such data which grew up on the basis of the existing physical ideas on the fission of the nucleus, radiative capture and neutron scattering. Experimental data were very scanty but for that reason they were particularly valuable

  3. Can Experimental Scientists, Data Evaluators and Compilers, and Nuclear Data Users Understand One Another?

    Energy Technology Data Exchange (ETDEWEB)

    Usachev, L. N. [Institute of Physics and Energetics, Obninsk, USSR (Russian Federation)

    1966-07-01

    The International Atomic Energy Agency organizes conferences on a wide variety of scientific subjects, all of which are of fundamental importance for the development of nuclear power. These include the technology of fuel elements, their stability in neutron fields, and chemical reprocessing as well as reactor physics, mathematical computational methods and the problems of protection and dosimetry. The problem of microscopic nuclear data, an essential aspect of reactor work, is just one of these many subjects. On the other hand, it should be remembered that the possibility of releasing nuclear energy was established in the first place by obtaining nuclear data on the fission process occurring in the uranium nucleus following the capture of a neutron and on the escape of the 2-3 secondary fission neutrons. In early nuclear power work the information provided by nuclear data was of considerable, even of decisive, importance. For example, the information available on the neutron balance in fast reactors showed that such reactors could operate as breeders and thus that it was worth while developing them. Strictly speaking, it is of course difficult to speak of a knowledge of nuclear data at this early period. It is perhaps more accurate to speak of the understanding of and the feeling for such data which grew up on the basis of the existing physical ideas on the fission of the nucleus, radiative capture and neutron scattering. Experimental data were very scanty but for that reason they were particularly valuable.

  4. [Establishment and identification of mouse lymphoma cell line EL4 expressing red fluorescent protein].

    Science.gov (United States)

    Li, Yan-Jie; Cao, Jiang; Chen, Chong; Wang, Dong-Yang; Zeng, Ling-Yu; Pan, Xiu-Ying; Xu, Kai-Lin

    2010-02-01

    This study was purposed to construct a lentiviral vector encoding red fluorescent protein (DsRed) and transfect DsRed into EL4 cells for establishing mouse leukemia/lymphoma model expressing DsRed. The bicistronic SIN lentiviral transfer plasmid containing the genes encoding neo and internal ribosomal entry site-red fluorescent protein (IRES-DsRed) was constructed. Human embryonic kidney 293FT cells were co-transfected with the three plasmids by liposome method. The viral particles were collected and used to transfect EL4 cells, then the cells were selected by G418. The results showed that the plasmid pXZ208-neo-IRES-DsRed was constructed successfully, and the viral titer reached to 10(6) U/ml. EL4 cells were transfected by the viral solution efficiently. The transfected EL4 cells expressing DsRed survived in the final concentration 600 microg/ml of G418. The expression of DsRed in the transfected EL4 cells was demonstrated by fluorescence microscopy and flow cytometry. In conclusion, the EL4/DsRed cell line was established successfully.

  5. Calcium signals and caspase-12 participated in paraoxon-induced apoptosis in EL4 cells.

    Science.gov (United States)

    Li, Lan; Cao, Zhiheng; Jia, Pengfei; Wang, Ziren

    2010-04-01

    In order to investigate whether calcium signals participate in paraoxon (POX)-induced apoptosis in EL4 cells, real-time laser scanning confocal microscopy (LSCM) was used to detect Ca(2+) changes during the POX application. Apoptotic rates of EL4 cells and caspase-12 expression were also evaluated. POX (1-10nM) increased intracellular calcium concentration ([Ca(2+)]i) in EL4 cells in a dose-dependent manner at early stage (0-2h) of POX application, and apoptotic rates of EL4 cells after treatment with POX for 16h were also increased in a dose-dependent manner. Pre-treatment with EGTA, heparin or procaine attenuated POX-induced [Ca(2+)]i elevation and apoptosis. Additionally, POX up-regulated caspase-12 expression in a dose-dependent manner, and pre-treatment with EGTA, heparin or procaine significantly inhibited POX-induced increase of caspase-12 expression. Our results suggested that POX induced [Ca(2+)]i elevation in EL4 cells at the early stage of POX-induced apoptosis, which might involve Ca(2+) efflux from the endoplasmic reticulum (ER) and Ca(2+) influx from extracellular medium. Calcium signals and caspase-12 were important upstream messengers in POX-induced apoptosis in EL4 cells. The ER-associated pathway possibly operated in this apoptosis. Copyright (c) 2010 Elsevier Ltd. All rights reserved.

  6. Experimental and calculational works on characteristics of the Dalat Nuclear Research Reactor. Second edition

    International Nuclear Information System (INIS)

    Pham Ngoc Khoi; Nguyen Kim Dung

    2016-03-01

    Recognizing the significant value and necessity of publishing the scientific document of experimental and calculational works on the Dalat Nuclear Research Reactor (DNRR) physics and engineering for research, operation, training activities as well as for international scientific exchange, Vietnam Atomic Energy Agency (VAEA) and Vietnam Atomic Energy Institute have completed editing to publish the “Experimental and Calculational Works on Characteristics of THE DALAT NUCLEAR RESEARCH REACTOR” which consists of 26 typical papers representing the most important experimental and calculational results of the DNRR physics and engineering obtained during 30 years of operation and exploitation with the contribution of Vietnamese and former USSR’s experts, especially scientists and engineers working at the Reactor Center of the NRI

  7. The international thermonuclear experimental reactor and the future of nuclear fusion energy

    International Nuclear Information System (INIS)

    Pan Chuanhong

    2010-01-01

    Energy shortage and environmental problems are now the two largest challenges for human beings. Magnetic confinement nuclear fusion, which has achieved great progress since the 1990's, is anticipated to be a way to realize an ideal source of energy in the future because of its abundance, environmental compatibility, and zero carbon release. Exemplified by the construction of the International Thermonuclear Experimental Reactor (ITER), the development of nuclear fusion energy is now in its engineering phase, and should be realized by the middle of this century if all objectives of the ITER project are met. (author)

  8. Combined conditioning in the high-temperature experimental nuclear reactor (AVR) at Juelich

    International Nuclear Information System (INIS)

    Nieder, R.; Vey, K.; Ivens, G.

    1984-01-01

    The high temperature experimental nuclear reactor (AVR) is the first nuclear power plant in which combined cycle operation has been introduced. The water-steam cycle has been operated for about 15 years according to the alkali method of working with ammonia and hydrazine. The VGB-guidelines have been adhered to througout. Since January 1983 cobined cycle operation has been employed, and in this process a pH-value of about 8.5 and an oxygen concentration of about 200 μg/kg in the feedwater have been used. A distinct reduction of tritium concentration in the water-steam cycle was the outstanding new result. (orig.) [de

  9. Nuclear Physics Division, Institute of Experimental Physics, Warsaw University annual report 1995

    Energy Technology Data Exchange (ETDEWEB)

    Osuch, S [ed.

    1997-12-31

    In the presented Annual Report the activities of Nuclear Physics Division (NPD) of Warsaw University in 1995 are described. The report consists of three sections: (i) Reaction Mechanism and Nuclear Structure (11 articles); (ii) Instrumentation and Experimental Methods (9 articles); (iii) Other Research (1 article). Additionally the list of seminars held at the NPD, personnel list and list of published papers are also given. The first, leading article in the report written by head of NPD prof. Ch. Droste the general description of the Department activity is presented.

  10. Nuclear Physics Division, Institute of Experimental Physics, Warsaw University annual report 1995

    Energy Technology Data Exchange (ETDEWEB)

    Osuch, S. [ed.

    1996-12-31

    In the presented Annual Report the activities of Nuclear Physics Division (NPD) of Warsaw University in 1995 are described. The report consists of three sections: (i) Reaction Mechanism and Nuclear Structure (11 articles); (ii) Instrumentation and Experimental Methods (9 articles); (iii) Other Research (1 article). Additionally the list of seminars held at the NPD, personnel list and list of published papers are also given. The first, leading article in the report written by head of NPD prof. Ch. Droste the general description of the Department activity is presented.

  11. Analysis of experimental data on relativistic nuclear collisions in the Lobachevsky space

    International Nuclear Information System (INIS)

    Baldin, A.A.; Baldina, Eh.G.; Kladnitskaya, E.N.; Rogachevskij, O.V.

    2004-01-01

    Relativistic nuclear collisions are considered in terms of relative 4-velocity and rapidity space (the Lobachevsky space). The connection between geometric relations in the Lobachevsky space and measurable (experimentally determined) kinematic characteristics (transverse momentum, longitudinal rapidity, square relative 4-velocity b ik , etc.) is discussed. The experimental data obtained using the propane bubble chamber are analyzed on the basis of triangulation in the Lobachevsky space. General properties of relativistic invariants distributions characterizing the geometric position of particles in the Lobachevsky space are discussed. The transition energy region is considered on the basis of relativistic approach to experimental data on multiparticle processes. Possible applications of the obtained results for planning of experimental research and analysis of data on multiple particle production are discussed

  12. Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Harms, Gary A.; Helmick, Paul H.; Ford, John T.; Walker, Sharon A.; Berry, Donald T.; Pickard, Paul S.

    2004-01-01

    This report describes criticality benchmark experiments containing rhodium that were conducted as part of a Department of Energy Nuclear Energy Research Initiative project. Rhodium is an important fission product absorber. A capability to perform critical experiments with low-enriched uranium fuel was established as part of the project. Ten critical experiments, some containing rhodium and others without, were conducted. The experiments were performed in such a way that the effects of the rhodium could be accurately isolated. The use of the experimental results to test neutronics codes is demonstrated by example for two Monte Carlo codes. These comparisons indicate that the codes predict the behavior of the rhodium in the critical systems within the experimental uncertainties. The results from this project, coupled with the results of follow-on experiments that investigate other fission products, can be used to quantify and reduce the conservatism of spent nuclear fuel safety analyses while still providing the necessary level of safety

  13. A systematic study of distribution characters of infiltration parameters in an experimental basin by nuclear methods

    International Nuclear Information System (INIS)

    Gu Weizu; Lu Jieju; Lu Mingjiang; Chen Tingyang

    1988-01-01

    A case study of spatial variability of Philip's infiltration parameters was carried out in a small experimental catchment with an area of 0.8 ha by nuclear monitoring methods. Relationships between sorptivity S, parameter A and the average initial soil water content within 0.5 m depth of soil profiles over the catchment have been plotted. A watershed infiltration parameter distribution curve is set up and fitted approximately by f/F=1-(1-S/S M ) n . The parameters of composite infiltration response related to whole catchment are suggested. The author has studied it on an experimental basin by combined method of nuclear technology and micro-geomorphic analysis. The results are satisfactory. (author). 6 refs, 11 figs, 2 tabs

  14. Investigation of analytical and experimental behavior of nuclear facility ventilation systems

    International Nuclear Information System (INIS)

    Smith, P.R.; Ricketts, C.I.; Andrae, R.W.; Bolstad, J.W.; Horak, H.L.; Martin, R.A.; Tang, P.K.; Gregory, W.S.

    1979-01-01

    The behavior of nuclear facility ventilation systems subjected to both natural and man-caused accidents is being investigated. The purpose of the paper is to present a program overview and highlight recent results of the investigations. The program includes both analytical and experimental investigations. Computer codes for predicting accident-induced gas dynamics and test facilities to obtain supportive experimental data to define structural integrity and confinement effectiveness of ventilation system components are described. A unique test facility and recently obtained structural limits for high efficiency particulate air filters are reported

  15. Health and Safety Considerations Associated with Sodium-Cooled Experimental Nuclear Fuel Dismantlement

    Energy Technology Data Exchange (ETDEWEB)

    Carvo, Alan E. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-04-01

    Between the mid-1970s and the mid-1980s Sandia National Laboratory constructed eleven experimental assemblies to simulate debris beds formed in a sodium-cooled fast breeder reactor. All but one of the assemblies were irradiated. The experimental assemblies were transferred to the Idaho National Laboratory (INL) in 2007 and 2008 for storage, dismantlement, recovery of the uranium for reuse in the nuclear fuel cycle, and disposal of unneeded materials. This paper addresses the effort to dismantle the assemblies down to the primary containment vessel and repackage them for temporary storage until such time as equipment necessary for sodium separation is in place.

  16. [Antitumor effects of matrix protein of vesicular stomatic virus on EL4 lymphoma mice].

    Science.gov (United States)

    Lin, Shi-jia; Yu, Qin-mei; Meng, Wen-tong; Wen, Yan-jun; Chen, Li-juan; Niu, Ting

    2011-03-01

    To explore antitumor effects of plasmid pcDNA3. 1-MP encoding matrix protein of vesicular stomatitis virus (VSV) complexed with cationic liposome (DOTAP:CHOL) in mice with EL4 lymphoma. C57BL/6 mouse model with EL4 lymphoma was established. Sixty mice bearing EL4 lymphoma were divided randomly into five groups including Lip-MP, Lip-pVAX, Lip, ADM and NS groups, which were intravenously injected with liposome-pcDNA 3. 1-MP complex, liposome-pVAX complex, empty liposome, Adriamycin and normal saline respectively every three days. Tumor volumes and survival time were monitored. Microvessel density and tumor proliferative index in tumor tissues were determined by CD31, Ki-67 immunohistochemistry staining, meanwhile the tumor apoptosis index was measured by TUNEL method. From 6 days after treatments on, the tumor volume in Lip-MP group was much smaller than that in Lip-pVAX, Lip and NS group (P EL4 tumor cells in vivo (P EL4 lymphoma, which may be related to the induction of tumor cell apoptosis, inhibition of tumor angiogenesis, and suppression of tumor cell proliferation.

  17. Computer techniques for experimental work in GDR nuclear power plants with WWER

    International Nuclear Information System (INIS)

    Stemmler, G.

    1985-01-01

    Nuclear power plant units with WWER are being increasingly equipped with high-performance, programmable process control computers. There are, however, essential reasons for further advancing the development of computer-aided measuring systems, in particular for experimental work. A special structure of such systems, which is based on the division into relatively rigid data registration and primary handling and into further processing by advanced programming language, has proved useful in the GDR. (author)

  18. Progress in nuclear measuring and experimental techniques by application of microelectronics. 1

    International Nuclear Information System (INIS)

    Meiling, W.

    1984-01-01

    In the past decade considerable progress has been made in nuclear measuring and experimental techniques by developing position-sensitive detector systems and widely using integrated circuits and microcomputers for data acquisition and processing as well as for automation of measuring processes. In this report which will be published in three parts those developments are reviewed and demonstrated on selected examples. After briefly characterizing microelectronics, the use of microelectronic elements for radiation detectors is reviewed. (author)

  19. Experimental and phenomenological comparison between Piezonuclear reactions and Condensed Matter Nuclear Science phenomenology

    OpenAIRE

    Cardone, F.; Mignani, R.; Petrucci, A.

    2011-01-01

    The purpose of this paper is to place side by side the experimental results of Piezonu- clear reactions, which have been recently unveiled, and those collected during the last twenty years of experiments on low energy nuclear reactions (LENR). We will briefy re- port the results of our campaign of piezonuclear reactions experiments where ultrasounds and cavitation were applied to solutions of stable elements. These outcomes will be shown to be compatible with the results and evidences obtaine...

  20. Berkeley Nuclear Laboratories Reactor Physics Mk. III Experimental Programme. Description of facility and programme for 1971

    Energy Technology Data Exchange (ETDEWEB)

    Nunn, R M; Waterson, R H; Young, J D

    1971-01-15

    Reactor physics experiments have been carried out at Berkeley Nuclear Laboratories during the past few years in support of the Civil Advanced Gas-Cooled Reactors (Mk. II) the Generating Board is building. These experiments are part of an overall programme whose objective is to assess the accuracy of the calculational methods used in the design and operation of these reactors. This report provides a description of the facility for the Mk. III experimental programme and the planned programme for 1971.

  1. Existing experimental criticality data applicable to nuclear-fuel-transportation systems

    International Nuclear Information System (INIS)

    Bierman, S.R.

    1983-02-01

    Analytical techniques are generally relied upon in making criticality evaluations involving nuclear material outside reactors. For these evaluations to be accepted the calculations must be validated by comparison with experimental data for a known set of conditions having physical and neutronic characteristics similar to those conditions being evaluated analytically. The purpose of this report is to identify those existing experimental data that are suitable for use in verifying criticality calculations on nuclear fuel transportation systems. In addition, near term needs for additional data in this area are identified. Of the considerable amount of criticality data currently existing, that are applicable to non-reactor systems, those particularly suitable for use in support of nuclear material transportation systems have been identified and catalogued into the following groups: (1) critical assemblies of fuel rods in water; (2) critical assemblies of fuel rods in water containing soluble neutron absorbers; (3) critical assemblies containing solid neutron absorber; (4) critical assemblies of fuel rods in water with heavy metal reflectors; and (5) critical assemblies of fuel rods in water with irregular features. A listing of the current near term needs for additional data in each of the groups has been developed for future use in planning criticality research in support of nuclear fuel transportation systems. The criticality experiments needed to provide these data are briefly described and identified according to priority and relative cost of performing the experiments

  2. Development, calibration and experimental results obtained with an innovative calorimeter (CALMOS) for nuclear heating measurements

    International Nuclear Information System (INIS)

    Carcreff, H.; Cloute-Cazalaa, V.; Salmon, L.

    2011-01-01

    Nuclear heating inside an MTR reactor has to be known in order to be able to control samples temperature during irradiation experiments. An R and D program has been carried out at CEA to design a new type of in-core calorimetric system. This new development, started in 2002, has for main objective to manufacture a calorimeter suitable to monitoring nuclear heating inside the 70 MWth OSIRIS material testing reactor operated by CEA's Nuclear Energy Div. at the Saclay research center. An innovative calorimetric probe, associated to a specific handling system, has been designed to provide access to measurements both along the fissile height and on the upper part of the core, where nuclear heating still remains high. Two mock-ups of the probe were manufactured and tested in 2005 and 2009 in ex-core area of OSIRIS reactor for process validation, while a displacement system has been especially studied to move the probe along a given axial measurement range. This paper deals with the development, tests on preliminary mock-ups and the finalization of the probe. Main modeling and experimental results are presented. Moreover, alternative methods to calibration for nuclear heating rate measurements which are now possible with this new calorimeter are presented and discussed. (authors)

  3. Development, calibration, and experimental results obtained with an innovative calorimeter (CALMOS) for nuclear heating measurements

    International Nuclear Information System (INIS)

    Carcreff, Hubert; Cloute-Cazalaa, Veronique; Salmon, Laurent

    2012-01-01

    Nuclear heating inside an MTR reactor has to be known in order to be able to control samples temperature during irradiation experiments. An R and D program has been carried out at CEA to design a new type of in-core calorimetric system. This new development, started in 2002, has for main objective to manufacture a calorimeter suitable to monitoring nuclear heating inside the 70 MWth OSIRIS material testing reactor operated by CEA's Nuclear Energy Division at the Saclay research center. An innovative calorimetric probe, associated to a specific handling system, has been designed to provide access to measurements both along the fissile height and on the upper part of the core, where nuclear heating still remains high. Two mock-ups of the probe were manufactured and tested in 2005 and 2009 in ex-core area of OSIRIS reactor for process validation, while a displacement system has been especially studied to move the probe along a given axial measurement range. This paper deals with the development, tests on preliminary mock-ups and the finalization of the probe. Main modeling and experimental results are presented. Moreover, alternative methods to calibration for nuclear heating rate measurements which are now possible with this new calorimeter are presented and discussed. (authors)

  4. Synergistic effect of EMF-BEMER-type pulsed weak electromagnetic field and HPMA-bound doxorubicin on mouse EL4 T-cell lymphoma.

    Science.gov (United States)

    Říhová, Blanka; Etrych, Tomáš; Šírová, Milada; Tomala, Jakub; Ulbrich, Karel; Kovář, Marek

    2011-12-01

    We have investigated the effects of low-frequency pulsed electromagnetic field (LF-EMF) produced by BEMER device on experimental mouse T-cell lymphoma EL4 growing on conventional and/or athymic (nude) mice. Exposure to EMF-BEMER slowed down the growth of tumor mass and prolonged the survival of experimental animals. The effect was more pronounced in immuno-compromised nude mice compared to conventional ones. Acceleration of tumor growth was never observed. No measurable levels of Hsp 70 or increased levels of specific anti-EL4 antibodies were detected in the serum taken from experimental mice before and at different intervals during the experiment, i.e. before solid tumor appeared, at the time of its aggressive growth, and at the terminal stage of the disease. A significant synergizing antitumor effect was seen when EL4 tumor-bearing mice were simultaneously exposed to EMF-BEMER and treated with suboptimal dose of synthetic HPMA copolymer-based doxorubicin, DOX(HYD)-HPMA. Such a combination may be especially useful for heavily treated patients suffering from advanced tumor and requiring additional aggressive chemotherapy which, however, at that time could represent almost life-threatening way of medication.

  5. Regulation of Id2 expression in EL4 T lymphoma cells overexpressing growth hormone.

    Science.gov (United States)

    Weigent, Douglas A

    2009-01-01

    In previous studies, we have shown that overexpression of growth hormone (GH) in cells of the immune system upregulates proteins involved in cell growth and protects from apoptosis. Here, we report that overexpression of GH in EL4 T lymphoma cells (GHo) also significantly increased levels of the inhibitor of differentiation-2 (Id2). The increase in Id2 was suggested in both Id2 promoter luciferase assays and by Western analysis for Id2 protein. To identify the regulatory elements that mediate transcriptional activation by GH in the Id2 promoter, promoter deletion analysis was performed. Deletion analysis revealed that transactivation involved a 301-132bp region upstream to the Id2 transcriptional start site. The pattern in the human GHo Jurkat T lymphoma cell line paralleled that found in the mouse GHo EL4 T lymphoma cell line. Significantly less Id2 was detected in the nucleus of GHo EL4 T lymphoma cells compared to vector alone controls. Although serum increased the levels of Id2 in control vector alone cells, no difference was found in the total levels of Id2 in GHo EL4 T lymphoma cells treated with or without serum. The increase in Id2 expression in GHo EL4 T lymphoma cells measured by Id2 promoter luciferase expression and Western blot analysis was blocked by the overexpression of a dominant-negative mutant of STAT5. The results suggest that in EL4 T lymphoma cells overexpressing GH, there is an upregulation of Id2 protein that appears to involve STAT protein activity.

  6. Deficient tyrosine phosphorylation of c-Cbl and associated proteins in phorbol ester-resistant EL4 mouse thymoma cells.

    Science.gov (United States)

    Luo, X; Sando, J J

    1997-05-02

    Two tyrosine phosphoproteins in phorbol ester-sensitive EL4 (S-EL4) mouse thymoma cells have been identified as the p120 c-Cbl protooncogene product and the p85 subunit of phosphatidylinositol 3-kinase. Tyrosine phosphorylation of p120 and p85 increased rapidly after phorbol ester stimulation. Phorbol ester-resistant EL4 (R-EL4) cells expressed comparable amounts of c-Cbl and phosphatidylinositol 3-kinase protein but greatly diminished tyrosine phosphorylation. Co-immunoprecipitation experiments revealed complexes of c-Cbl with p85, and of p85 with the tyrosine kinase Lck in phorbol ester-stimulated S-EL4 but not in unstimulated S-EL4 or in R-EL4 cells. In vitro binding of c-Cbl with Lck SH2 or SH3 domains was detected in both S-EL4 and R-EL4 cells, suggesting that c-Cbl, p85, and Lck may form a ternary complex. In vitro kinase assays revealed phosphorylation of p85 by Lck only in phorbol ester-stimulated S-EL4 cells. Collectively, these results suggest that Cbl-p85 and Lck-p85 complexes may form in unstimulated S-EL4 and R-EL4 cells but were not detected due to absence of tyrosine phosphorylation of p85. Greatly decreased tyrosine phosphorylation of c-Cbl and p85 in the complexes may contribute to the failure of R-EL4 cells to respond to phorbol ester.

  7. Experimental Study of Nuclear Security System Components for Achieving the Intrusion Process via Sensor's Network System

    International Nuclear Information System (INIS)

    EL-Kafas, A.A.

    2011-01-01

    Cluster sensors are one of nuclear security system components which are used to detect any intrusion process of the nuclear sites. In this work, an experimental measuring test for sensor performance and procedures are presented. Sensor performance testing performed to determine whether a particular sensor will be acceptable in a proposed design. We have access to a sensors test field in which the sensor of interest is already properly installed and the parameters have been set to optimal levels by preliminary testing. The glass-breakage (G.B) and open door (O.D) sensors construction, operation and design for the investigated nuclear site are explained. Intrusion tests were carried out inside the field areas of the sensors to evaluate the sensor performance during the intrusion process. Experimental trials were performed for achieving the intrusion process via sensor network system. The performance and intrusion senses of cluster sensors inside the internal zones was recorded and evaluated. The obtained results explained that the tested and experimented G.B sensors have a probability of detection P (D) value 65% founded, and 80% P (D) of Open-door sensor

  8. J.O. no. 10 of the 13 january 2004, page 991, text no. 14. Decrees, orders. General texts. Decree no. 2004-47 of the 12 january 2004 modifying the decree no. 96-978 of the 31 october 1996 relative to the creation of the nuclear installation no. 162 named EL4-D, installation of storage for the Monts d'Arree power plants materials; J.O. no. 10 du 13 janvier 2004, page 991, texte no. 14. Decrets, arretes, circulaires. Textes generaux. Decret no. 2004-47 du 12 janvier 2004 modifiant le decret no. 96-978 du 31 octobre 1996 relatif a la creation de l'installation nucleaire de base no. 162 denommee EL4-D, installation d'entreposage de materiels de la centrale nucleaire des monts d'Arree

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-06-01

    The reactor EL4, implemented in december 1966, has definitely shutdown on the 31 july 1985. This reactor was an industrial prototype, built and exploited by Cea and EDF. In the framework of the partial dismantling of the installation, the decree 96-978 of the 31 october 1996 agreed the Cea to modify the installation to become a storage installation. (A.L.B.)

  9. Studies in nuclear structure relevant to Astrophysics: theoretical and experimental efforts

    International Nuclear Information System (INIS)

    Saha Sarkar, Maitreyee

    2016-01-01

    Experimental and theoretical investigations in the region around doubly magic neutron rich 132 Sn nucleus have recently revealed many intriguing issues concerning some newer aspects of nuclear structure in such exotic environments. These nuclei lie on or close to the path of the astrophysical r-process flow. A glimpse of the implication of these studies on the r-process nucleosynthesis will be discussed. Presently, the Nuclear Physics group in Saha Institute of Nuclear Physics is working for installation of a high-current, low energy Accelerator as the primary component of the Facility for Research in low Energy Nuclear Astrophysics (FRENA), a national facility, at Kolkata. Planning for future experiments has been undertaken for successful utilization of this facility. Implantation technique has been found to be one of the most effective methods to produce isotopically pure targets. We have prepared a few isotopically pure targets using this technique. Being the slowest process of the CNO cycle, study of the 14 N(p, γ) 15 O(Q = 7297 keV) capture reaction is of high astrophysical interest. From an experiment utilizing one of the newly prepared 14 N implanted targets, a preliminary estimate of the lifetime of 6792 keV state in 15 O has been obtained, using Doppler shift attenuation method (DSAM). The sensitivity of the results with respect to the uncertainties in various input quantities has been tested. This endeavour will be helpful to design a better experiment to extract more precise lifetime for this important state

  10. Completion of the experimental equipment systems and preparation of practical tutorials on the Dalat Nuclear Research Reactor for nuclear science and technology education

    International Nuclear Information System (INIS)

    Le Vinh Vinh; Huynh Ton Nghiem; Luong Ba Vien; Nguyen Minh Tuan; Nguyen Kien Cuong; Pham Quang Huy; Tran Tri Vien

    2015-01-01

    The project Completion of the experimental equipment systems and preparation of practical tutorials on the Dalat Nuclear Research Reactor for nuclear science and technology education performed by Dalat Nuclear Research Institute and financed by Ministry of Science and Technology aimed at strengthening the training capability of nuclear human resources. The content of this work includes: i) Improvement of experimental equipment; ii) Compilation of training material for experiments with the improved equipment systems on the reactor; iii) Compilation of training material for reactor calculations includes the following areas: neutronics, hydrothermal, safety analysis and accident consequence analysis. Results of the project provide important conditions to support practical educational and training curriculums in nuclear science and technology. (author)

  11. The JAERI-KEK joint project on high intensity proton accelerator and overview of nuclear transmutation experimental facilities

    International Nuclear Information System (INIS)

    Ikeda, Yujiro

    2001-01-01

    A status of the JAERI/KEK joint project on High Intensity Proton Accelerator is overviewed. It is highlighted that Experimental facilities for development of the accelerator driven system (ADS) for nuclear transmutation technology is proposed under the project. (author)

  12. Flux distribution by neutrons semi-conductors detectors during the startup of the EL4 reactor

    International Nuclear Information System (INIS)

    Fuster, S.; Tarabella, A.

    1967-01-01

    The Cea developed neutron semi-conductors detectors which allows a quasi-instantaneous monitoring of neutrons flux distribution, when placed in a reactor during the tests. These detectors have been experimented in the EL4 reactor. The experiment and the results are presented and compared with reference mappings. (A.L.B.)

  13. Experimental nuclear level densities and γ-ray strength functions in Sc and V isotopes

    International Nuclear Information System (INIS)

    Larsen, A. C.; Guttormsen, M.; Ingebretsen, F.; Messelt, S.; Rekstad, J.; Siem, S.; Syed, N. U. H.; Chankova, R.; Loennroth, T.; Schiller, A.; Voinov, A.

    2008-01-01

    The nuclear physics group at the Oslo Cyclotron Laboratory has developed a method to extract nuclear level density and γ-ray strength function from first-generation γ-ray spectra. This method is applied on the nuclei 44,45 Sc and 50,51 V in this work. The experimental level densities of 44,45 Sc are compared to calculated level densities using a microscopic model based on BCS quasiparticles within the Nilsson level scheme. The γ-ray strength functions are also compared to theoretical expectations, showing an unexpected enhancement of the γ-ray strength for low γ energies (E γ ≤3 MeV) in all the isotopes studied here. The physical origin of this enhancement is not yet understood

  14. Experimental studies of keV energy neutron-induced reactions relevant to astrophysics and nuclear physics

    Energy Technology Data Exchange (ETDEWEB)

    Shima, T.; Kii, T.; Kikuchi, T.; Okazaki, F.; Kobayashi, T.; Baba, T.; Nagai, Y. [Tokyo Inst. of Tech. (Japan). Faculty of Science; Igashira, M.

    1997-03-01

    Nuclear reactions induced by keV energy neutrons provide a plenty of informations for studies of both astrophysics and nuclear physics. In this paper we will show our experimental studies of neutron- induced reactions of light nuclei in the keV energy region by means of a pulsed keV neutron beam and high-sensitivity detectors. Also we will discuss astrophysical and nuclear-physical consequences by using the obtained results. (author)

  15. Experimental aspect of solid-state nuclear magnetic resonance studies of biomaterials such as bones.

    Science.gov (United States)

    Singh, Chandan; Rai, Ratan Kumar; Sinha, Neeraj

    2013-01-01

    Solid-state nuclear magnetic resonance (SSNMR) spectroscopy is increasingly becoming a popular technique to probe micro-structural details of biomaterial such as bone with pico-meter resolution. Due to high-resolution structural details probed by SSNMR methods, handling of bone samples and experimental protocol are very crucial aspects of study. We present here first report of the effect of various experimental protocols and handling methods of bone samples on measured SSNMR parameters. Various popular SSNMR experiments were performed on intact cortical bone sample collected from fresh animal, immediately after removal from animal systems, and results were compared with bone samples preserved in different conditions. We find that the best experimental conditions for SSNMR parameters of bones correspond to preservation at -20 °C and in 70% ethanol solution. Various other SSNMR parameters were compared corresponding to different experimental conditions. Our study has helped in finding best experimental protocol for SSNMR studies of bone. This study will be of further help in the application of SSNMR studies on large bone disease related animal model systems for statistically significant results. © 2013 Elsevier Inc. All rights reserved.

  16. Differential Expression of Ccn4 and Other Genes Between Metastatic and Non-metastatic EL4 Mouse Lymphoma Cells

    OpenAIRE

    S. CHAHAL, MANPREET; TERESA KU, H.; ZHANG, ZHIHONG; M. LEGASPI, CHRISTIAN; LUO, ANGELA; M. HOPKINS, MANDI; E. MEIER, KATHRYN

    2016-01-01

    Background: Previous work characterized variants of the EL4 murine lymphoma cell line. Some are non-metastatic, and others metastatic, in syngenic mice. In addition, metastatic EL4 cells were stably transfected with phospholipase D2 (PLD2), which further enhanced metastasis. Materials and Methods: Microarray analyses of mRNA expression was performed for non-metastatic, metastatic, and PLD2-expressing metastatic EL4 cells. Results: Many differences were observed between non-metastatic and meta...

  17. Methods of experimental settlement of contradicting data in evaluated nuclear data libraries

    Directory of Open Access Journals (Sweden)

    V. A. Libman

    2016-12-01

    Full Text Available The latest versions of the evaluated nuclear data libraries (ENDLs have contradictions concerning data about neutron cross sections. To resolve this contradiction we propose the method of experimental verification. This method is based on using of the filtered neutron beams and following measurement of appropriate samples. The basic idea of the method is to modify the suited filtered neutron beam so that the differences between the neutron cross sections in accordance with different ENDLs become measurable. Demonstration of the method is given by the example of cerium, which according to the latest versions of four ENDLs has significantly different total neutron cross section.

  18. Optimization of preventive maintenance cycle based on experimental feedback in nuclear power plants

    International Nuclear Information System (INIS)

    Shi Jie

    2010-01-01

    The preventive replacement method based on the experimental feedback was introduced. In this method, the initial preventive replacement cycle was acquired by expert votes. The preventive replacement cycle combined with the operation experience of the equipment was gained by means of Bayesian theorem. The Optimized preventive replacement cycle can be acquired by comparing the two probabilities that no fault occurs within the cycle. This method was tested on the switches which were used in Daya Bay Nuclear Power Plant and the results indicated its validity. (authors)

  19. On experimental determination of characteristics of nuclear fusion reactions from mu-molecular resonance states

    International Nuclear Information System (INIS)

    Bystritskij, V.M.; Pen'kov, F.M.

    1997-01-01

    Charge-nonsymmetrical deuterium-helium muon complexes (dμHe) are studied. A method is proposed for experimentally determining the rates of nuclear fusion reactions in dμHe molecules in the J=1 and J=0 states (J is the orbital moment of the system) and the partial rates for radiative decay of these complexes in these states. Experiments are supposed to be carried out at meson factories with gaseous and cryogenic targets filled with a mixture of deuterium and helium

  20. Facilities for post-irradiation examination of experimental fuel elements at Chalk River Nuclear Laboratories

    International Nuclear Information System (INIS)

    Mizzan, E.; Chenier, R.J.

    1979-10-01

    Expansion of post-irradiation facilities at the Chalk River Nuclear Laboratories and steady improvement in hot-cell techniques and equipment are providing more support to Canada's reactor fuel development program. The hot-cell facility primarily used for examination of experimental fuels averages a quarterly throughput of 40 elements and 110 metallographic specimens. New developments in ultrasonic testing, metallographic sample preparation, active storage, active waste filtration, and fissile accountability are coming into use to increase the efficiency and safety of hot-cell operations. (author)

  1. Cannabinoid inhibition of adenylate cyclase-mediated signal transduction and interleukin 2 (IL-2) expression in the murine T-cell line, EL4.IL-2.

    Science.gov (United States)

    Condie, R; Herring, A; Koh, W S; Lee, M; Kaminski, N E

    1996-05-31

    Cannabinoid receptors negatively regulate adenylate cyclase through a pertussis toxin-sensitive GTP-binding protein. In the present studies, signaling via the adenylate cyclase/cAMP pathway was investigated in the murine thymoma-derived T-cell line, EL4.IL-2. Northern analysis of EL4.IL-2 cells identified the presence of 4-kilobase CB2 but not CB1 receptor-subtype mRNA transcripts. Southern analysis of genomic DNA digests for the CB2 receptor demonstrated identical banding patterns for EL4.IL-2 cells and mouse-derived DNA, both of which were dissimilar to DNA isolated from rat. Treatment of EL4.IL-2 cells with either cannabinol or Delta9-THC disrupted the adenylate cyclase signaling cascade by inhibiting forskolin-stimulated cAMP accumulation which consequently led to a decrease in protein kinase A activity and the binding of transcription factors to a CRE consensus sequence. Likewise, an inhibition of phorbol 12-myristate 13-acetate (PMA)/ionomycin-induced interleukin 2 (IL-2) protein secretion, which correlated to decreased IL-2 gene transcription, was induced by both cannabinol and Delta9-THC. Further, cannabinoid treatment also decreased PMA/ionomycin-induced nuclear factor binding to the AP-1 proximal site of the IL-2 promoter. Conversely, forskolin enhanced PMA/ionomycin-induced AP-1 binding. These findings suggest that inhibition of signal transduction via the adenylate cyclase/cAMP pathway induces T-cell dysfunction which leads to a diminution in IL-2 gene transcription.

  2. Experimental and computational investigation of flow of pebbles in a pebble bed nuclear reactor

    Science.gov (United States)

    Khane, Vaibhav B.

    The Pebble Bed Reactor (PBR) is a 4th generation nuclear reactor which is conceptually similar to moving bed reactors used in the chemical and petrochemical industries. In a PBR core, nuclear fuel in the form of pebbles moves slowly under the influence of gravity. Due to the dynamic nature of the core, a thorough understanding about slow and dense granular flow of pebbles is required from both a reactor safety and performance evaluation point of view. In this dissertation, a new integrated experimental and computational study of granular flow in a PBR has been performed. Continuous pebble re-circulation experimental set-up, mimicking flow of pebbles in a PBR, is designed and developed. Experimental investigation of the flow of pebbles in a mimicked test reactor was carried out for the first time using non-invasive radioactive particle tracking (RPT) and residence time distribution (RTD) techniques to measure the pebble trajectory, velocity, overall/zonal residence times, flow patterns etc. The tracer trajectory length and overall/zonal residence time is found to increase with change in pebble's initial seeding position from the center towards the wall of the test reactor. Overall and zonal average velocities of pebbles are found to decrease from the center towards the wall. Discrete element method (DEM) based simulations of test reactor geometry were also carried out using commercial code EDEM(TM) and simulation results were validated using the obtained benchmark experimental data. In addition, EDEM(TM) based parametric sensitivity study of interaction properties was carried out which suggests that static friction characteristics play an important role from a packed/pebble beds structural characterization point of view. To make the RPT technique viable for practical applications and to enhance its accuracy, a novel and dynamic technique for RPT calibration was designed and developed. Preliminary feasibility results suggest that it can be implemented as a non

  3. Experimental investigation between attentional-resource effectiveness and perception and diagnosis in nuclear power plants

    International Nuclear Information System (INIS)

    Ha, Jun Su; Seong, Poong Hyun

    2014-01-01

    Highlights: • Effectiveness in information searching is measured by two eye-tracking measures. • The relationship between the effectiveness and perception and diagnosis is addressed. • An experimental study is conducted to investigate the relationship. • The experimental results show close correlation. • The eye-tracking measures as inferential measures for perception and diagnosis. - Abstract: Eye-tracking-based measures of attentional-resource effectiveness in information searching such as FIR (fixation to importance ratio) and SAE (selective attention effectiveness) have been developed based on cost-benefit principles. The relationship between the eye-tracking-based measures and perception and diagnosis of operators during operating tasks in main control rooms (MCRs) of nuclear power plants (NPPs) is investigated with experimental studies. The FIR and the SAE, which represent how effectively an operator attends to important information sources, are used as measures of the effectiveness in information searching. Perception failure rate (PFR) and diagnosis score (DS) are used as measures of perception and diagnosis, respectively. Experimental results show that the FIR and the SAE correlate closely with the PFR and the DS, respectively. It is concluded that the FIR and the SAE can be used as inferential measures of perception and diagnosis for human factors in NPP MCRs

  4. Experimental investigation between attentional-resource effectiveness and perception and diagnosis in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Jun Su, E-mail: junsu.ha@kustar.ac.ae [Nuclear Engineering Department, Khalifa University of Science, Technology and Research, P.O. Box 127788, Abu Dhabi (United Arab Emirates); Seong, Poong Hyun, E-mail: phseong@kaist.ac.kr [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1 Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)

    2014-10-15

    Highlights: • Effectiveness in information searching is measured by two eye-tracking measures. • The relationship between the effectiveness and perception and diagnosis is addressed. • An experimental study is conducted to investigate the relationship. • The experimental results show close correlation. • The eye-tracking measures as inferential measures for perception and diagnosis. - Abstract: Eye-tracking-based measures of attentional-resource effectiveness in information searching such as FIR (fixation to importance ratio) and SAE (selective attention effectiveness) have been developed based on cost-benefit principles. The relationship between the eye-tracking-based measures and perception and diagnosis of operators during operating tasks in main control rooms (MCRs) of nuclear power plants (NPPs) is investigated with experimental studies. The FIR and the SAE, which represent how effectively an operator attends to important information sources, are used as measures of the effectiveness in information searching. Perception failure rate (PFR) and diagnosis score (DS) are used as measures of perception and diagnosis, respectively. Experimental results show that the FIR and the SAE correlate closely with the PFR and the DS, respectively. It is concluded that the FIR and the SAE can be used as inferential measures of perception and diagnosis for human factors in NPP MCRs.

  5. Neutron dosimetry in EDF experimental surveillance programme for VVER-440 nuclear power plants

    International Nuclear Information System (INIS)

    Brumovsky, M.; Erben, O.; Novosad, P.; Zerola, L.; Hogel, J.; Trollat, C.

    2001-01-01

    Fourteen chains containing experimental surveillance material specimens of the VVER 440/213 nuclear power reactor pressure vessels were irradiated in the surveillance channels of the Nuclear Power Plant Dukovany in the Czech Republic. The irradiation periods were one, two or three cycles. The chains contained different number and types of containers, the omitted ones were replaced by chain elements. All of the containers were instrumented with wire neutron fluence detectors, some of the containers in the chain had spectrometric sets of neutron fluence monitors. For the absolute fluence values evaluation it was taken into account time history of the reactor power and local changes of the neutron flux along the reactor core height, correction factors due to the orientation of monitors with respect to the reactor core centre. Unfolding programs SAND-II or BASA-CF were used. The relative axial fluence distribution was obtained from the O-wire measurements. Neutron fluence values above 0.5 MeV energy and above 1.0 MeV energy in the container axis on the axial positions of the sample centres and fluence values in the geometric centre of the samples was calculated making use the exponential attenuation model of the incident neutron beam. Received fast neutron fluence values can be used as reference values to all VVER-440 type 213 nuclear power plant reactors. (author)

  6. Experimental evidence of independence of nuclear de-channeling length on the particle charge sign

    Energy Technology Data Exchange (ETDEWEB)

    Bagli, E.; Guidi, V.; Mazzolari, A.; Bandiera, L.; Germogli, G.; Sytov, A.I. [Universita di Ferrara, Dipartimento di Fisica e Scienze della Terra (Italy); INFN Sezione di Ferrara (Italy); De Salvador, D. [Universita di Padova, Dipartimento di Fisica e Astronomia, Padua (Italy); INFN Laboratori Nazionali di Legnaro (Italy); Berra, A.; Prest, M. [Universita dell' Insubria, Como (Italy); INFN Sezione di Milano Bicocca, Milan (Italy); Vallazza, E. [INFN Sezione di Trieste (Italy)

    2017-02-15

    Under coherent interactions, particles undergo correlated collisions with the crystal lattice and their motion result in confinement in the fields of atomic planes, i.e. particle channeling. Other than coherently interacting with the lattice, particles also suffer incoherent interactions with individual nuclei and may leave their bounded motion, i.e., they de-channel. The latter is the main limiting factor for applications of coherent interactions in crystal-assisted particle steering. We experimentally investigated the nature of de-channeling of 120 GeV/c e{sup -} and e{sup +} in a bent silicon crystal at H4-SPS external line at CERN. We found that while channeling efficiency differs significantly for e{sup -} (2 ± 2%) and e{sup +} (54 ± 2%), their nuclear de-channeling length is comparable, (0.6 ± 0.1) mm for e{sup -} and (0.7 ± 0.3) mm for e{sup +}. The experimental proof of the equality of the nuclear de-channeling length for positrons and electrons is interpreted in terms of similar dynamics undergone by the channeled particles in the field of nuclei irrespective of their charge. (orig.)

  7. Isomer depletion as experimental evidence of nuclear excitation by electron capture

    Science.gov (United States)

    Chiara, C. J.; Carroll, J. J.; Carpenter, M. P.; Greene, J. P.; Hartley, D. J.; Janssens, R. V. F.; Lane, G. J.; Marsh, J. C.; Matters, D. A.; Polasik, M.; Rzadkiewicz, J.; Seweryniak, D.; Zhu, S.; Bottoni, S.; Hayes, A. B.; Karamian, S. A.

    2018-02-01

    The atomic nucleus and its electrons are often thought of as independent systems that are held together in the atom by their mutual attraction. Their interaction, however, leads to other important effects, such as providing an additional decay mode for excited nuclear states, whereby the nucleus releases energy by ejecting an atomic electron instead of by emitting a γ-ray. This ‘internal conversion’ has been known for about a hundred years and can be used to study nuclei and their interaction with their electrons. In the inverse process—nuclear excitation by electron capture (NEEC)—a free electron is captured into an atomic vacancy and can excite the nucleus to a higher-energy state, provided that the kinetic energy of the free electron plus the magnitude of its binding energy once captured matches the nuclear energy difference between the two states. NEEC was predicted in 1976 and has not hitherto been observed. Here we report evidence of NEEC in molybdenum-93 and determine the probability and cross-section for the process in a beam-based experimental scenario. Our results provide a standard for the assessment of theoretical models relevant to NEEC, which predict cross-sections that span many orders of magnitude. The greatest practical effect of the NEEC process may be on the survival of nuclei in stellar environments, in which it could excite isomers (that is, long-lived nuclear states) to shorter-lived states. Such excitations may reduce the abundance of the isotope after its production. This is an example of ‘isomer depletion’, which has been investigated previously through other reactions, but is used here to obtain evidence for NEEC.

  8. Experimental and numerical characterization of wind-induced pressure coefficients on nuclear buildings and chimney exhausts

    Energy Technology Data Exchange (ETDEWEB)

    Ricciardi, Laurent, E-mail: laurent.ricciardi@irsn.fr; Gélain, Thomas; Soares, Sandrine

    2015-10-15

    Highlights: • Experiments on scale models of nuclear buildings and chimney exhausts were performed. • Pressure coefficient fields on buildings are shown for various wind directions. • Evolution of pressure coefficient vs U/W ratio is given for various chimney exhausts. • RANS simulations using SST k–ω turbulence model were performed on most studied cases. • A good agreement is overall observed, with Root Mean Square Deviation lower than 0.15. - Abstract: Wind creates pressure effects on different surfaces of buildings according to their exposure to the wind, in particular at external communications. In nuclear facilities, these effects can change contamination transfers inside the building and can even lead to contamination release into the environment, especially in damaged (ventilation stopped) or accidental situations. The diversity of geometries of facilities requires the use of a validated code for predicting pressure coefficients, which characterize the wind effect on the building walls and the interaction between the wind and chimney exhaust. The first aim of a research program launched by the French Institut de Radioprotection et de Sûreté Nucléaire (IRSN), was therefore to acquire experimental data of the mean pressure coefficients for different geometries of buildings and chimneys through wind tunnel tests and then to validate a CFD code (ANSYS CFX) from these experimental results. The simulations were performed using a steady RANS approach and a two-equation SST k–ω turbulence model. After a mesh sensitivity study for one configuration of building and chimney, a comparison was carried out between the numerical and experimental values for other studied configurations. This comparison was generally satisfactory, averaged over all measurement points, with values of Root Mean Square Deviations lower than 0.15 for most cases.

  9. Extrusion and drawing of zircaloy 2. Production of pressure tubes for EL-4; Filage et etirage du zircaloy 2. Realisation des tubes de force pour EL-4

    Energy Technology Data Exchange (ETDEWEB)

    Thevenet, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Buffet, J [Cefilac (France)

    1964-07-01

    The authors give briefly the physical mechanical and chemical properties of zircaloy 2, as far as the transformation of this alloy is concerned. Extrusion: After a few general remarks concerning the extrusion and co-extrusion, including a comparison of the deformation resistance of canning metals and of zircaloy 2, the following points are considered: - the difficulties occurring because of the use of this alloy: - atmosphere protection - adjustment on to the machine tools - low thermal conductivity - economy of the metal (price) - the factors affecting the quality of the extruded products extrusion under a copper can and under lubricant glass - fine grain structure - temperature homogeneity - working temperature The transformation cycle - '550 kg ingot - preliminary shape 'for drawing of EL-4 tubes (112 x 120 L 12 m)' - is described in detail (extrusion or forging of the {phi} = 340 ingot into {phi} = 220 billets, cutting into lengths and hot drilling at {phi} = 125, fixing into a copper can and rough extrusion). Drawing: The main difficulties are due to seizing of the tools and to the necessity of protecting the alloy from the atmosphere during annealings. A brief description is given of drawing out on a short mandrel, on a long mandrel, of laminating on a reducing machine and of the carrying out of an annealing, as well as of the production of EL-4 tubes ({phi} =107 x 113 L 430 m) by drawing out shapes having a size of 112 x 120 on long mandrels. Conclusion: It is possible by extrusion and drawing to produce zircaloy 2 tubes similar to those which may be obtained normally using stainless steel. (authors) [French] Les auteurs donnent un resume succint des proprietes physiques mecaniques et chimiques du zircaloy 2 en ce qui concerne la transformation de cet alliage. Filage: Apres quelques generalites sur le filage et le cofilage, dont une comparaison entre les resistances a la deformation des metaux de gainage et du zircaloy 2, on etudie successivement: - les

  10. The effects of tributyltin oxide and deoxynivalenol on the transcriptome of the mouse thymoma cell line EL-4

    NARCIS (Netherlands)

    Schmeits, P.J.M.; Kol, S.; Loveren, van H.; Peijnenburg, A.A.C.M.; Hendriksen, P.J.M.

    2014-01-01

    The main goal of this study was to assess the potential of the mouse thymoma EL-4 cell line in screening for chemical induced immunotoxicity. Therefore, EL-4 cells were exposed to two well-known immunotoxicants, organotin compound tributyltin oxide (TBTO, 0.5 and 1 µM for 3 or 6 h) and the mycotoxin

  11. Cytotoxic T lymphocyte recognition of HLA-A/B antigens introduced into EL4 cells by cell-liposome fusion.

    Science.gov (United States)

    Engelhard, V H; Powers, G A; Moore, L C; Holterman, M J; Correa-Freire, M C

    1984-01-01

    HLA-A2 and -B7 antigens were introduced into EL4 (H-2b) cells by cell-liposome fusion and were used as targets or stimulators for cytotoxic T lymphocytes (CTL) generated in C57B1/6 (H-2b) mice. It was found that such EL4-HLA cells were not recognized by CTL that had been raised against either a human cell line bearing these HLA antigens or the purified HLA-A2 and -B7 antigens reconstituted into liposomes. In addition, EL4-HLA cells were not capable of inducing CTL that could recognize a human cell line bearing HLA-A2 and -B7 antigens. Instead, EL4-HLA cells induced CTL that specifically lysed EL4-HLA cells and not human cells expressing HLA-A2 and -B7. CTL recognition required the presence of HLA antigens on the EL4 cell surface and was inhibited by antibodies against either H-2b or HLA-A/B. Monoclonal antibody binding studies showed that the expected polymorphic determinants of the HLA-A2 and -B7 antigens were still present on EL4-HLA cells. However, the specificity of CTL or their precursors that are capable of recognizing HLA-A2 or -B7 was altered after these antigens became associated with the EL4 surface. Possible explanations for these results are discussed.

  12. Experimental study of nuclear models. I. Decay schemes and nuclear reactions. II. Muonic x-ray studies. Progress report, October 1, 1974--September 30, 1975

    International Nuclear Information System (INIS)

    Sheline, R.K.

    1975-01-01

    Progress on the research on our AT-(40-1)-2434 Contract is summarized for the twelve month contract year beginning October 1, 1974, and ending September 30, 1975. The main emphasis of our research continues to be an experimental study of nuclear models. Some change of emphasis is occurring. In the past, the emphasis has been overwhelmingly nuclear reaction spectroscopy and comparison with theoretical models. This year an increasing percentage of the emphasis (perhaps 25 percent) is on the study of nuclear structure from the view point of muonic x-ray spectroscopy. A list of publications is included. (U.S.)

  13. RasGRP1 confers the phorbol ester-sensitive phenotype to EL4 lymphoma cells.

    Science.gov (United States)

    Han, Shujie; Knoepp, Stewart M; Hallman, Mark A; Meier, Kathryn E

    2007-01-01

    The murine EL4 lymphoma cell line exists in variants that are either sensitive or resistant to the tumor promoter phorbol 12-myristate 13-acetate (PMA). In sensitive EL4 cells, PMA causes robust Erk mitogen-activated protein kinase activation that results in growth arrest. In resistant cells, PMA induces minimal Erk activation, without growth arrest. PMA stimulates IL-2 production in sensitive, but not resistant, cells. The role of RasGRP1, a PMA-activated guanine nucleotide exchange factor for Ras, in EL4 phenotype was examined. Endogenous RasGRP1 protein is expressed at much higher levels in sensitive than in resistant cells. PMA-induced Ras activation is observed in sensitive cells but not in resistant cells lacking Ras-GRP1. PMA induces down-regulation of RasGRP1 protein in sensitive cells but increases RasGRP1 in resistant cells. Transfection of RasGRP1 into resistant cells enhances PMA-induced Erk activation. In the reverse experiment, introduction of small interfering RNA (siRNA) for RasGRP1 suppresses PMA-induced Ras and Erk activations in sensitive cells. Sensitive cells incubated with siRNA for RasGRP1 exhibit the PMA-resistant phenotype, in that they are able to proliferate in the presence of PMA and do not secrete IL-2 when stimulated with PMA. These studies indicate that the PMA-sensitive phenotype, as previously defined for the EL4 cell line, is conferred by endogenous expression of RasGRP1 protein.

  14. [Regulatory T cells inhibit proliferation of mouse lymphoma cell line EL4 in vitro].

    Science.gov (United States)

    Zhang, Chen; Kong, Yan; Guo, Jun; Ying, Zhi-Tao; Yuan, Zhi-Hong; Zhang, Yun-Tao; Zheng, Wen; Song, Yu-Qin; Li, Ping-Ping; Zhu, Jun

    2010-10-01

    This study was aimed to investigate the effect of regulatory T (Treg) cells on the T cell lymphoma EL4 cells and its mechanism in vitro. C57BL/6 mouse Treg cells were isolated by magnetic cell sorting (MACS). The purity of Treg cells and their expression of Foxp3 were identified by flow cytometry (FCM) and PT-PCR respectively. The suppression of Treg cells on EL4 cells was detected by 3H-TdR method. At the same time, enzyme-linked immunosorbent assay (ELISA) was used to detect the secretion of cytokine TGF-β1 and IL-10. The results showed that CD4+CD25+ T cells could be successfully isolated by MACS with the purity reaching 94.52% and the expression of Foxp3 reaching 84.72%. After sorting, the expression of Foxp3 mRNA could be detected by RT-PCR. 3H-TdR assay confirmed that regulatory T cells could suppress the proliferation of EL4 cells with or without antigen presenting cells (APC) or dendritic cells (DC), APC or DC might effectively enhance the suppression. In addition, DC alone also suppressed the proliferation. TGF-β1 and IL-10 could be detected in the supernatant by ELISA. It is concluded that the Treg cells can obviously suppress the proliferation of T cell lymphoma cells in vitro, APC or DC can enhance this suppressive effect, while the DC alone also can suppress the proliferation of EL4 cells, the TGF-β1 and IL-10 cytokine pathway may be one of the mechanisms of suppression.

  15. B7-2 Expressed on EL4 Lymphoma Suppresses Antitumor Immunity by an Interleukin 4–dependent Mechanism

    Science.gov (United States)

    Stremmel, C.; Greenfield, E.A.; Howard, E.; Freeman, G.J.; Kuchroo, V.K.

    1999-01-01

    For T cells to become functionally activated they require at least two signals. The B7 costimulatory molecules B7-1 and B7-2 provide the “second signal” pivotal for T cell activation. In this report, we studied the relative roles of B7-1 and B7-2 molecules in the induction of antitumor immunity to the T cell thymoma, EL4. We generated EL4 tumor cells that expressed B7-1, B7-2, and B7-1+B7-2 by transfecting murine cDNAs. Our results demonstrate that EL4–B7-1 cells are completely rejected in syngeneic mice. Unlike EL4–B7-1 cells, we find that EL4–B7-2 cells are not rejected but progressively grow in the mice. A B7-1– and B7-2–EL4 double transfectant was generated by introducing B7-2 cDNA into the EL4–B7-1 tumor line that regressed in vivo. The EL4–B7-1+B7-2 double transfectant was not rejected when implanted into syngeneic mice but progressively grew to produce tumors. The double transfectant EL4 cells could costimulate T cell proliferation that could be blocked by anti–B7-1 antibodies, anti–B7-2 antibodies, or hCTLA4 immunoglobulin, showing that the B7-1 and B7-2 molecules expressed on the EL4 cells were functional. In vivo, treatment of mice implanted with double-transfected EL4 cells with anti–B7-2 monoclonal antibody resulted in tumor rejection. Furthermore, the EL4–B7-2 and EL4–B7-1+B7-2 cells, but not the wild-type EL4 cells, were rejected in interleukin 4 (IL-4) knockout mice. Our data suggests that B7-2 expressed on some T cell tumors inhibits development of antitumor immunity, and IL-4 appears to play a critical role in abrogation of the antitumor immune response. PMID:10075975

  16. B7-2 expressed on EL4 lymphoma suppresses antitumor immunity by an interleukin 4-dependent mechanism.

    Science.gov (United States)

    Stremmel, C; Greenfield, E A; Howard, E; Freeman, G J; Kuchroo, V K

    1999-03-15

    For T cells to become functionally activated they require at least two signals. The B7 costimulatory molecules B7-1 and B7-2 provide the "second signal" pivotal for T cell activation. In this report, we studied the relative roles of B7-1 and B7-2 molecules in the induction of antitumor immunity to the T cell thymoma, EL4. We generated EL4 tumor cells that expressed B7-1, B7-2, and B7-1+B7-2 by transfecting murine cDNAs. Our results demonstrate that EL4-B7-1 cells are completely rejected in syngeneic mice. Unlike EL4-B7-1 cells, we find that EL4-B7-2 cells are not rejected but progressively grow in the mice. A B7-1- and B7-2-EL4 double transfectant was generated by introducing B7-2 cDNA into the EL4-B7-1 tumor line that regressed in vivo. The EL4-B7-1+B7-2 double transfectant was not rejected when implanted into syngeneic mice but progressively grew to produce tumors. The double transfectant EL4 cells could costimulate T cell proliferation that could be blocked by anti-B7-1 antibodies, anti-B7-2 antibodies, or hCTLA4 immunoglobulin, showing that the B7-1 and B7-2 molecules expressed on the EL4 cells were functional. In vivo, treatment of mice implanted with double-transfected EL4 cells with anti-B7-2 monoclonal antibody resulted in tumor rejection. Furthermore, the EL4-B7-2 and EL4-B7-1+B7-2 cells, but not the wild-type EL4 cells, were rejected in interleukin 4 (IL-4) knockout mice. Our data suggests that B7-2 expressed on some T cell tumors inhibits development of antitumor immunity, and IL-4 appears to play a critical role in abrogation of the antitumor immune response.

  17. Basic study on apoptosis induction into cancer cells U-937 and EL-4 by ultrasound exposure.

    Science.gov (United States)

    Takeuchi, Shinichi; Udagawa, Yoshiko; Oku, Yumiko; Fujii, Takuma; Nishimura, Hiroyuki; Kawashima, Norimichi

    2006-12-22

    Recently, the low invasive cancer treatments with small aftereffects have been considered. We are studying on the suppression methods of cancer cell proliferation with ultrasound. Cancer cells of mouse T lymphoma (EL-4) have been used in our study. The human histitocytic lymphoma cells (U-937) was used in this time. The cancer cells were cultured in a culture medium of RPMI1640. The standing wave acoustic field was formed in a water tank of our ultrasound exposure system by a vibrating plate driven with a Langevine type transducer. The U-937 and EL-4 were exposed to ultrasound in the acoustic field with spatial average acoustic intensity of 350 mW/cm(2) at 150 kHz. The viable rate of EL-4 decreased with the lapse of culture time after ultrasound exposure. U-937 did not show the remarkable decrease tendency. The proliferation of U-937 which exposed to ultrasound with 700 mW/cm(2) was suppressed. It can be thought that apoptosis was induced in the cancer cells in this condition. We observed the morphological change on the U-937 exposed to ultrasound with this condition. The morphological changes by apoptosis like the shrink of cells, formation of apoptotic bodies etc. can be observed with an optical microscope and a phase contrast microscope.

  18. The short term effects of Low-dose-rate Radiation on EL4 Lymphoma Cell

    International Nuclear Information System (INIS)

    Bong, Jin Jong; Kang, Yu Mi; Shin, Suk Chull; Choi, Moo Hyun; Choi, Seung Jin; Kim, Hee Sun; Lee, Kyung Mi

    2012-01-01

    To determine the biological effects of low-dose-rate radiation ( 137 Cs, 2.95 mGy/h) on EL4 lymphoma cells during 24 h, we investigated the expression of genes related to apoptosis, cell cycle arrest, DNA repair, iron transport, and ribonucleotide reductase. EL4 cells were continuously exposed to low-dose-rate radiation (total dose: 70.8 mGy) for 24 h. We analyzed cell proliferation and apoptosis by trypan blue exclusion and flow cytometry, gene expression by real-time PCR, and protein levels with the apoptosis ELISA kit. Apoptosis increased in the Low-dose-rate irradiated cells, but cell number did not differ between non- (Non-IR) and Low-dose-rate irradiated (LDR-IR) cells. In concordance with apoptotic rate, the transcriptional activity of ATM, p53, p21, and Parp was upregulated in the LDR-IR cells. Similarly, Phospho-p53 (Ser15), cleaved caspase 3 (Asp175), and cleaved Parp (Asp214) expression was upregulated in the LDR-IR cells. No difference was observed in the mRNA expression of DNA repair-related genes (Msh2, Msh3, Wrn, Lig4, Neil3, ERCC8, and ERCC6) between Non-IR and LDR-IR cells. Interestingly, the mRNA of Trfc was upregulated in the LDR-IR cells. Therefore, we suggest that short-term Low-dose-rate radiation activates apoptosis in EL4 lymphoma cells.

  19. Pretreatment of low dose radiation reduces radiation-induced apoptosis in mouse lymphoma (EL4) cells.

    Science.gov (United States)

    Kim, J H; Hyun, S J; Yoon, M Y; Ji, Y H; Cho, C K; Yoo, S Y

    1997-06-01

    Induction of an adaptive response to ionizing radiation in mouse lymphoma (EL4) cells was studied by using cell survival fraction and apoptotic nucleosomal DNA fragmentation as biological end points. Cells in early log phase were pre-exposed to low dose of gamma-rays (0.01 Gy) 4 or 20 hrs prior to high dose gamma-ray (4, 8 and 12 Gy for cell survival fraction analysis; 8 Gy for DNA fragmentation analysis) irradiation. Then cell survival fractions and the extent of DNA fragmentation were measured. Significant adaptive response, increase in cell survival fraction and decrease in the extent of DNA fragmentation were induced when low and high dose gamma-ray irradiation time interval was 4 hr. Addition of protein or RNA synthesis inhibitor, cycloheximide or 5,6-dichloro-1-beta-d-ribofuranosylbenzimidazole (DRFB), respectively during adaptation period, the period from low dose gamma-ray irradiation to high dose gamma-ray irradiation, was able to inhibit the induction of adaptive response, which is the reduction of the extent DNA fragmentation in irradiated EL4 cells. These data suggest that the induction of adaptive response to ionizing radiation in EL4 cells required both protein and RNA synthesis.

  20. The short term effects of Low-dose-rate Radiation on EL4 Lymphoma Cell

    Energy Technology Data Exchange (ETDEWEB)

    Bong, Jin Jong; Kang, Yu Mi; Shin, Suk Chull; Choi, Moo Hyun; Choi, Seung Jin; Kim, Hee Sun [Radiation Health Research Institute, Korea Hydro and Nuclear Power Co., Ltd, Seoul (Korea, Republic of); Lee, Kyung Mi [Global Research Lab, BAERI Institute, Dept. of Biochemistry and Molecular Biology, Korea University College of Medicine, Seoul (Korea, Republic of)

    2012-06-15

    To determine the biological effects of low-dose-rate radiation ({sup 137}Cs, 2.95 mGy/h) on EL4 lymphoma cells during 24 h, we investigated the expression of genes related to apoptosis, cell cycle arrest, DNA repair, iron transport, and ribonucleotide reductase. EL4 cells were continuously exposed to low-dose-rate radiation (total dose: 70.8 mGy) for 24 h. We analyzed cell proliferation and apoptosis by trypan blue exclusion and flow cytometry, gene expression by real-time PCR, and protein levels with the apoptosis ELISA kit. Apoptosis increased in the Low-dose-rate irradiated cells, but cell number did not differ between non- (Non-IR) and Low-dose-rate irradiated (LDR-IR) cells. In concordance with apoptotic rate, the transcriptional activity of ATM, p53, p21, and Parp was upregulated in the LDR-IR cells. Similarly, Phospho-p53 (Ser15), cleaved caspase 3 (Asp175), and cleaved Parp (Asp214) expression was upregulated in the LDR-IR cells. No difference was observed in the mRNA expression of DNA repair-related genes (Msh2, Msh3, Wrn, Lig4, Neil3, ERCC8, and ERCC6) between Non-IR and LDR-IR cells. Interestingly, the mRNA of Trfc was upregulated in the LDR-IR cells. Therefore, we suggest that short-term Low-dose-rate radiation activates apoptosis in EL4 lymphoma cells.

  1. Quark deconfinement in nuclei: A review of experimental tests based on nuclear magnetic moment measurements

    International Nuclear Information System (INIS)

    Stone, N.J.; Rikovska, J.

    1988-01-01

    The introduction very briefly outlines the basic idea and experimental evidence to suggest that quarks may behave differently in nuclei and in individual nucleons, with possible consequences for the calculation of nuclear magnetic dipole moments. After description of a calculation of moments made using the extreme model of total quark deconfinement (the MIT bag model) attention is focussed on experimental tests and the state of current evidence for more partial quark deconfinement. The arguments of Yamazaki which give an experimental basis for distinguishing quark deconfinement effects from, specifically, effects caused by pion exchange currents, are given in more detail. The reasons underlying choice of nuclei in which meaningful tests may be possible are given. Early claims by Karl et al. to have demonstrated the existence of quark deconfinement in mass 3 nuclei are discussed. The current status of evidence for deconfinement based on orbital g-factor measurements in heavier nuclei is also summarised. Finally some examples are given of possible experiments using recently developed on-line facilities which may provide further tests of these ideas. (orig.)

  2. Experimental observations on electrorefining spent nuclear fuel in molten LiCl-KCl/liquid cadmium system

    International Nuclear Information System (INIS)

    Johnson, T. A.; Laug, D. V.; Li, S. X.; Sofu, T.

    1999-01-01

    Argonne National Laboratory (ANL) is currently performing a demonstration program for the Department of Energy (DOE) which processes spent nuclear fuel from the Experimental Breeder Reactor (EBR-II). One of the key steps in this demonstration program is electrorefining of the spent fuel in a molten LiCl-KCl/liquid cadmium system using a pilot scale electrorefiner (Mk-IV ER). This article summarizes experimental observations and engineering aspects for electrorefining spent fuel in the molten LiCl-KCl/liquid cadmium system. It was found that the liquid cadmium pool acted as an intermediate electrode during the electrorefining process in the ER. The cadmium level was gradually decreased due to its high vapor pressure and vaporization rate at the ER operational temperature. The low cadmium level caused the anode assembly momentarily to touch the ER vessel hardware, which generated a periodic current change at the salt/cathode interface and improved uranium recovery efficiency for the process. The primary current distributions calculated by numerical simulations were used in interpreting the experimental results

  3. Experimental study of radioactive aerosols emission during the thermal degradation of organic materials in nuclear facilities

    International Nuclear Information System (INIS)

    Fernandez, Yvette

    1993-01-01

    Radioactive products may be released during a fire in nuclear fuel cycles facilities. These products must be confined to avoid a contamination spread in the environment. It is therefore necessary to be able to predict the amount and the physico-chemical forms of radioactive material that may be airborne. The aim of this study is to determine experimentally the release of contamination aerosols in a typical fire scenario involving plutonium oxide in a glove box. Firstly, this phenomenon has been studied in a small scale test chamber where samples of polymethylmethacrylate (Plexiglas) contaminated by cerium oxide (used as a substitute for plutonium oxide) were submitted to thermal degradation (pyrolysis and combustion). The release of radioactive material is determined by the quantity of contaminant emitted, the kinetics of the release and the particle size distribution of aerosols. Secondly, the development of an experimental procedure allowed to realize large scale fires in more realistic conditions. The experimental tools developed in the course of this study allow to consider application to other scenarios. (author) [fr

  4. Experimental and analytical studies on soil-structure interaction behavior of nuclear reactor building

    International Nuclear Information System (INIS)

    Tsushima, Y.

    1978-01-01

    The purpose of this study is to estimate damping effects due to soil-structure interaction by the dissipation of vibrational energy to the ground through the foundation in a building with a short fundamental period such as a nuclear reactor building. The author performed experimental and analytical studies on the vibrational characteristics of model steel structures ranging from one to four stories high erected on the rigid base and located on soil, which are simulated from the vibrational characteristics of a prototype reactor building: the former study is to obtain damping effects due to inner friction of steel frames and the latter to obtain radiation damping effects due to soil-structure interaction. The author also touches upon the results of experiments performed on a BWR-type reactor building in 1974, which showed damping ratios higher than 20% of those in fundamental modes. Then the author attempts to estimate the damping effects of the reactor building by his own method proposed in the report. Through these studies the author finally concludes that the experimental damping effects are remarkable in the lower modes by the energy dissipation and the analytical results show a fairly good fit to the experimental ones

  5. The stimulation of EL-4 cells to produce interleukin-2 and its potential use in immunocytotoxicity testing

    International Nuclear Information System (INIS)

    Lasek, W.; Steer, S.; Clothier, R.; Balls, M.

    1989-01-01

    The ability of EL-4 thymoma cells to produce interleukin-2 (IL-2) following exposure to phorbol-12-myristate 13-acetate (PMA) and Concanavalin A (Con A) has been studied in vitro using medium containing either 10% or 1% fetal calf serum (FCS). The potent stimulatory effect of PMA on IL-2 production by EL-4 cells has been confirmed by measuring 3H-thymidine incorporation by the IL-2-dependent T cell line, CTLL-2, in the presence of conditioned medium (CM) from stimulated cultures. EL-4 cells produced several times more IL-2 when cultured in medium containing 10% FCS than when only 1% FCS was present. Added together, PMA and Con A acted synergistically in some EL-4 cell cultures. The ability of E:-4 cells to produce IL-2 was maintained after further incubation without stimulants. CM with IL-2 activity from stimulated EL-4 cells could prove useful in immunotoxicity testing

  6. Radiation Damage in Nuclear Fuel for Advanced Burner Reactors: Modeling and Experimental Validation

    Energy Technology Data Exchange (ETDEWEB)

    Jensen, Niels Gronbech; Asta, Mark; Ozolins, Nigel Browning' Vidvuds; de Walle, Axel van; Wolverton, Christopher

    2011-12-29

    The consortium has completed its existence and we are here highlighting work and accomplishments. As outlined in the proposal, the objective of the work was to advance the theoretical understanding of advanced nuclear fuel materials (oxides) toward a comprehensive modeling strategy that incorporates the different relevant scales involved in radiation damage in oxide fuels. Approaching this we set out to investigate and develop a set of directions: 1) Fission fragment and ion trajectory studies through advanced molecular dynamics methods that allow for statistical multi-scale simulations. This work also includes an investigation of appropriate interatomic force fields useful for the energetic multi-scale phenomena of high energy collisions; 2) Studies of defect and gas bubble formation through electronic structure and Monte Carlo simulations; and 3) an experimental component for the characterization of materials such that comparisons can be obtained between theory and experiment.

  7. Numerical and experimental analysis of the impact of a nuclear spent fuel cask

    Energy Technology Data Exchange (ETDEWEB)

    Aquaro, D. [Department of Mechanical, Nuclear and Production Engineering (DIMNP), Pisa University, Via Diotisalvi, Pisa (Italy); Zaccari, N., E-mail: nicola.zaccari@enel.i [Department of Mechanical, Nuclear and Production Engineering (DIMNP), Pisa University, Via Diotisalvi, Pisa (Italy); Di Prinzio, M.; Forasassi, G. [Department of Mechanical, Nuclear and Production Engineering (DIMNP), Pisa University, Via Diotisalvi, Pisa (Italy)

    2010-04-15

    This paper deals with the numerical and experimental analyses of a shell type shock absorber for a nuclear spent fuel cask. Nine-meter free drop tests performed on reduced scale models are described. The results are compared with numerical simulations performed with FEM computer codes, considering reduced scale models as well as the prototype. The paper shows the results of a similitude analysis, with which the data obtained by means of the reduced scale models can be extrapolated to the prototype. Small discrepancies were obtained using large-scale models (1:2 and 1:6), while small-scale models (1:12) did not give reliable results. A 1:9 scale model provided useful information with a less than 20% error.

  8. Experimental researches of nuclear reactor neutron and gamma radiation scattering into the atmosphere

    International Nuclear Information System (INIS)

    Istomin, Yu.L.; Zelensky, D.I.; Cherepnin, Yu.S.; Orlov, Yu.V.; Netecha, M.E.; Avaev, V.N.; Vasel'ev, G.A.; Sakamoto, H.; Nomura, Y.; Naito, Y.

    1998-01-01

    In the report there are results of measuring radiation distribution on the caps of the RA and IWG.1M research reactors. Comparative analysis of the results is also in the report. There are neutron spectra in the interval of energies from 10 -9 to 13 MeV above RA and IWG.1M reactors. The spectra were measured with a set of activation detectors. Measurements were calculated to a nominal rate: for RA reactor - 300 kw, for IWG.1M - 7 MW. Thus, in the course of the experiment, vast experimental information relating to distribution of the RA and IWG.1M reactor gamma and neutron radiation scattered in the air for distances varying from 50 to 1000 m from the reactors has become available. The data obtained are to be used to verify the calculation codes and to validate the group nuclear constants

  9. The Joint Institute for Nuclear Research in Experimental Physics of Elementary Particles

    Science.gov (United States)

    Bednyakov, V. A.; Russakovich, N. A.

    2018-05-01

    The year 2016 marks the 60th anniversary of the Joint Institute for Nuclear Research (JINR) in Dubna, an international intergovernmental organization for basic research in the fields of elementary particles, atomic nuclei, and condensed matter. Highly productive advances over this long road clearly show that the international basis and diversity of research guarantees successful development (and maintenance) of fundamental science. This is especially important for experimental research. In this review, the most significant achievements are briefly described with an attempt to look into the future (seven to ten years ahead) and show the role of JINR in solution of highly important problems in elementary particle physics, which is a fundamental field of modern natural sciences. This glimpse of the future is full of justified optimism.

  10. Experimental methods of investigation of kinetics and dynamics of nuclear reactors

    International Nuclear Information System (INIS)

    Costa Oliveira, Jaime M.

    1969-03-01

    The author presents experimental methods used to study kinetic and dynamic properties of nuclear reactors. Kinetic methods aim at determining characteristic parameters of the behaviour in time of neutrons. Dynamic methods aim at establishing the relationships between the reactor behaviour and its internal and external causes (notably the measurement of transfer functions). The author proposes a classification with respect to the excitation type: periodic excitation (reactivity sinusoidal modulation, source sinusoidal modulation, periodic pulse excitation), non periodic excitation (reactivity monitoring, reactivity linear variation, reactivity variation according to any given law, removal of starting source), random excitation (random reactivity or source excitation), natural fluctuations (alpha-Rossi method, methods of reduced variance, probabilistic methods, correlation methods, spectral analysis method). He also addresses space and energy effects. Applications are reported for low power and power reactors

  11. Experimental analysis of a nuclear reactor prestressed concrete pressure vessels model

    International Nuclear Information System (INIS)

    Vallin, C.

    1980-01-01

    A comprehensible analysis was made of the performance of each set of sensors used to measure the strain and displacement of a 1/20 scale Prestressed Concrete Pressure Vessel (PCPV) model tested at the Instituto de Pesquisas Energeticas e Nucleares (IPEN). Among the three Kinds of sensors used (strain gage, displacement transducers and load cells) the displacement transducers showed the best behavior. The displacemente transducers data was statistically analysed and a linear behavior of the model was observed during the first pressurizations tests. By means of a linear statistical correlation between experimental and expected theoretical data it was found that the model looses the linearity at a pressure between 110-125 atm. (Author) [pt

  12. Scale-up considerations relevant to experimental studies of nuclear waste-package behavior

    International Nuclear Information System (INIS)

    Coles, D.G.; Peters, R.D.

    1986-04-01

    Results from a study that investigated whether testing large-scale nuclear waste-package assemblages was technically warranted are reported. It was recognized that the majority of the investigations for predicting waste-package performance to date have relied primarily on laboratory-scale experimentation. However, methods for the successful extrapolation of the results from such experiments, both geometrically and over time, to actual repository conditions have not been well defined. Because a well-developed scaling technology exists in the chemical-engineering discipline, it was presupposed that much of this technology could be applicable to the prediction of waste-package performance. A review of existing literature documented numerous examples where a consideration of scaling technology was important. It was concluded that much of the existing scale-up technology is applicable to the prediction of waste-package performance for both size and time extrapolations and that conducting scale-up studies may be technically merited. However, the applicability for investigating the complex chemical interactions needs further development. It was recognized that the complexity of the system, and the long time periods involved, renders a completely theoretical approach to performance prediction almost hopeless. However, a theoretical and experimental study was defined for investigating heat and fluid flow. It was concluded that conducting scale-up modeling and experimentation for waste-package performance predictions is possible using existing technology. A sequential series of scaling studies, both theoretical and experimental, will be required to formulate size and time extrapolations of waste-package performance

  13. Research in nuclear reactor theory and experimental reactors; Istrazivanja u teoriji nuklearnih reaktora i ekspeimentalni reaktori

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Elektrotehnicki fakultet, Beograd (Yugoslavia)

    1978-05-15

    The paper is devoted to the possibilities of using experimental reactors for scientific research in nuclear power with a stress on problems in nuclear reactor theory. The stationary and nonstationary neutron fields, burnup prediction and analyses as well as fuel element development and the corresponding role of test-reactors were dealt with. It was shown that the investigations in nuclear reactor theory in Yugoslavia were developing continuously and in a useful interaction with experiments on research reactors. The needs for continuing the work on fundamental problems in neutron transport theory and on improving the calculation methods for thermal power reactors, together with the improvement of performances of existing research systems, were pointed out. A new quality in scientific work could be obtained dealing with the problems connected to a possible introduction of test-reactors, and fast systems later on. It was also pleaded for the corresponding orientations in fundamental sciences. (author) Rad je posvecen mogucnostima koriscenja eksperimentalnih reaktora za naucna istrazivanja u nuklearnoj energetici, sa akcentom na probleme teorije nuklearnih reaktora. Obradjena su stacionarna i nestacionarna neutronska polja, predikcija i analize sagorevanja, kao i razvoj gorivnih elemenata te uloga test-reaktora u osvajanju njihove tehnologije. Pokazano je da su se istrazivanja u teoriji nuklearnih reaktora u nas odvijala kontinualno i u korisnoj interakciji sa eksperimentima na istrazivackim reaktorima. Istaknuta je potreba nastavljanja rada na fundamentalnim problemima transportne teorije neutrona i na usavrsavanju metoda proracuna termalnih enerrgetskih reaktora, uz poboljsanje performansi postojecih istrazivackih sistema. Novi kvalitet u naucnom radu bi predstavljala orijentacija na probleme vezane sa eventualnim uvodjenjem test-reaktora, a zatim i brzih sistema. Pledirano je i za odgovarajuca usmeravanja u fundamentalnim naukama. (author)

  14. Nuclear design of the blanket/shield system for a Tokamak Experimental Power Reactor

    International Nuclear Information System (INIS)

    Abdou, M.A.

    1976-01-01

    The various options and trade-offs in the nuclear design of the blanket/shield for a Tokamak Experimental Power Reactor (TEPR) are investigated. The TEPR size and cost are particularly sensitive to the blanket/shield thickness, Δ/sub BS/, on the inner side of the torus. Radition damage to the components of the superconducting magnet and refrigeration power requirements set lower limits on Δ/sub BS/. These limits are developed in terms of TEPR design parameters such as the wall loading, duty cycle, and frequency of magnet anneals. The study of the nuclear performance of various material compositions shows that mixtures of tungsten, or tantalum, or stainless-steel alloys and boron carbide require the smallest Δ/sub BS/ for a given attenuation. This Δ/sub BS/ has to be doubled if the low induced activation materials graphite and aluminum are used. The space problems are greatly eased in the Argonne National Laboratory ANL-TEPR reference design by using two separate segments of the blanket/shield. The inner segment occupies the region of the high magnetic field, uses very efficient attenuators (tungsten- or tantalum- or stainless-steel-boron carbide mixtures), and is only 1 m thick. The outer blanket/shield is 131 cm and consists of an optimized composition of stainless steel and boron carbide. For the design parameters of 0.2 MW/m 2 neutron wall loading and 50 percent duty cycle, the reactor components can operate satisfactorily up to (a) 10 yr for the stainless-steel first wall, (b) 10 yr for the superconductor composite after which magnet warmup becomes necessary, and (c) 30 yr for the Mylar insulation. Nuclear heat generation rates in the blanket/shield and magnet are well within the practical limits for heat removal

  15. Molten Core - Concrete interactions in nuclear accidents. Theory and design of an experimental facility

    International Nuclear Information System (INIS)

    Sevon, T.

    2005-11-01

    In a hypothetical severe accident in a nuclear power plant, the molten core of the reactor may flow onto the concrete floor of containment building. This would cause a molten core . concrete interaction (MCCI), in which the heat transfer from the hot melt to the concrete would cause melting of the concrete. In assessing the safety of nuclear reactors, it is important to know the consequences of such an interaction. As background to the subject, this publication includes a description of the core melt stabilization concept of the European Pressurized water Reactor (EPR), which is being built in Olkiluoto in Finland. The publication includes a description of the basic theory of the interaction and the process of spalling or cracking of concrete when it is heated rapidly. A literature survey and some calculations of the physical properties of concrete and corium. concrete mixtures at high temperatures have been conducted. In addition, an equation is derived for conservative calculation of the maximum possible concrete ablation depth. The publication also includes a literature survey of experimental research on the subject of the MCCI and discussion of the results and deficiencies of the experiments. The main result of this work is the general design of an experimental facility to examine the interaction of molten metals and concrete. The main objective of the experiments is to assess the probability of spalling, or cracking, of concrete under pouring of molten material. A program of five experiments has been designed, and pre-test calculations of the experiments have been conducted with MELCOR 1.8.5 accident analysis program and conservative analytic calculations. (orig.)

  16. Experimental study of the burned of nuclear fuel by the gamma spectroscopy method

    International Nuclear Information System (INIS)

    Amador V, P.

    2009-01-01

    Accurate information on nuclear fuel burnup is of vital importance in reactor operation, fuel management and fuel-characteristics studies. Conventionally fuel management of the TRIGA III Reactor from the National Institute of Nuclear Research (ININ) is done through the thermal balance method (management) of the power generated during reactor operation, since it is known that with 1.24 grams of 235 U is possible to generate a power or 1 MW per day during the reactor operation. On the other hand, it is possible to calculate the operation time in days during a power of 1 MW with the help of the data registered in logs. With the information just mentioned one can calculate the quantity of 235 U consumed in the fuel during a complete period of irradiation. In order to compare and prove that the burnup values, calculated through the thermal balance method, are correct, the ININ implemented, for the first time, the gamma-ray spectroscopy method as an experimental technique to calculate the burnup of several fuel elements. Gamma-ray spectroscopy is a nondestructive method, so that the integrity of the fuel element is not affected which is of great importance. Since there is a direct relation between the activity of 137 Cs contained in the fuel elements and a series of constants which are unique for the radioisotope and for the high resolution system, the problem just simplifies in measuring the 137 Cs activities. Furthermore the 137 Cs concentration equation was developed theoretically and I wrote a computer program (AMAVAL) in Fortran. The task of this program is to calculate the concentrations and the activity through the use of the equation just mentioned and the history of each fuel element. The purpose of this is to compare and validate the experimental activities with the theoretical ones for each fuel element. (Author)

  17. Experimental and analytical studies of the thermal aspects of deep geologic disposal of commercial nuclear wastes

    International Nuclear Information System (INIS)

    Christensen, R.N.; Kulacki, F.A.; Keyhani, M.; Hsieh, S.S.; Osborne, R.; Keyhani, V.

    1987-11-01

    Effects of smooth and rough surfaces on an underground nuclear waste repository were studied using a rectangular duct to simulate thermal and hydraulic conditions at a nuclear waste repository. Experiments performed on smooth walls revealed that increasing the aspect ratio increases the air velocity, which leads to an increase in convective heat transfer coefficients and a decrease in the temperature difference between the air stream and the heated wall. The heated length required for fully developed heat transfer was also determined for various aspect ratios. In experiments involving rough walls, two surface roughnesses were characterized by the average height and the pitch-to-height ratio. A combination of two roughness heights and three pitches was constructed covering the ranges 0.088 to 0.12 and 2.0 to 4.7, respectively. A friction factor correlation was developed based on the velocity distribution and pressure drop measurements. Heat transfer data at the downstream end of the test section were correlated as a function of the Reynolds number. A heat momentum analogy was correlated using temperature and velocity distribution measurements. An approximate analytical solution through numerical analysis for correlating the Nusselt numbers at the downstream end of the test section was compared with corresponding experimental results. 47 refs., 105 figs., 33 tabs

  18. Shielding analysis method applied to nuclear ship 'MUTSU' and its evaluation based on experimental analyses

    International Nuclear Information System (INIS)

    Yamaji, Akio; Miyakoshi, Jun-ichi; Iwao, Yoshiaki; Tsubosaka, Akira; Saito, Tetsuo; Fujii, Takayoshi; Okumura, Yoshihiro; Suzuoki, Zenro; Kawakita, Takashi.

    1984-01-01

    Procedures of shielding analysis are described which were used for the shielding modification design of the Nuclear Ship ''MUTSU''. The calculations of the radiation distribution on board were made using Sn codes ANISN and TWOTRAN, a point kernel code QAD and a Monte Carlo code MORSE. The accuracies of these calculations were investigated through the analysis of various shielding experiments: the shield tank experiment of the Nuclear Ship ''Otto Hahn'', the shielding mock-up experiment for ''MUTSU'' performed in JRR-4, the shielding benchmark experiment using the 16 N radiation facility of AERE Harwell and the shielding effect experiment of the ship structure performed in the training ship ''Shintoku-Maru''. The values calculated by the ANISN agree with the data measured at ''Otto Hahn'' within a factor of 2 for fast neutrons and within a factor of 3 for epithermal and thermal neutrons. The γ-ray dose rates calculated by the QAD agree with the measured values within 30% for the analysis of the experiment in JRR-4. The design values for ''MUTSU'' were determined in consequence of these experimental analyses. (author)

  19. Experimental and Theoretical Dynamic Study of the Aagesta Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Bliselius, P A; Vollmer, H; Aakerhielm, F

    1969-12-15

    The report presents a final review and summary of all dynamic investigations of the Aagesta nuclear power station. Special attention is paid to the final and unpublished experiments performed in 1965-66. These experiments are discussed and compared to the theoretical predictions. Transfer functions and step responses were measured by perturbations in reactivity and steam load. Three methods were used for transfer function measurements: step functions, trapeze waves and multifrequency functions based on the pseudo-random binary sequence (PRBS). From the frequency analysis we found that the different perturbation methods led to quite consistent results. For the Agesta application the PRBS method is demonstrated to be an accurate and practical method for obtaining experimental transfer functions. The step technique did not give satisfactory results for frequencies above approximately 0.01 Hz. From the static check of the model we may conclude that the experiments agree fairly well mutually and with theory. The measured reactivity coefficients tend to be smaller than the predicted ones. The predicted transients compare well with the measured ones. However, there is a tendency to more peaked power transients from the model. This is believed to be due to the assumption that the moderator could be regarded as one channel. The dynamic experiments carried out at the Agesta nuclear power station demonstrate both the inherent stability and the safety of this plant.

  20. Radiation monitoring program at nuclear scientific experimental and educational center - IRT-Sofia

    International Nuclear Information System (INIS)

    Mladenov, A.; Stankov, D.; Marinov, K.; Nonova, T.; Krezhov, K.

    2012-01-01

    Ensuring minimal risk of personnel exposure without exceeding the dose limits is the main task of the General Program for Radiation Monitoring of Nuclear Scientific Experimental and Education Centre (NSEEC) with research reactor IRT. Since 2006 the IRT-Sofia is equipped with a new and modern Radiation Monitoring System (RMS). All RMS detectors are connected to the server RAMSYS. They have online (real-time) visualization in two workstations with RAMVISION software. The RMS allows the implementation of technological and environmental monitoring at the nuclear facility site. Environmental monitoring with the RMS external system includes monitoring of dose rate; alpha and beta activity; radon activity; Po-218, Po-214, Po-212 activity; gamma control of vehicles. Technological control of reactor gases includes: Alpha beta particulate monitor; Iodine monitor; Noble gases monitor; Stack flow monitor. The General Program based on the radiation monitoring system allows real-time monitoring and control of radiation parameters in the controlled area and provides for a high level of radiation protection of IRT staff and users of its facilities. This paper presents the technical and functional parameters of the radiation monitoring system and radiation protection activities within the restricted zone in IRT facilities. (authors)

  1. The Cyrano program. 1 - description and operation of an irradiation device 'Cyrano'. 2 - results of the experiments Cyrano 1 and 2 (study of the EL 4 first-bach pencil); measurement of the thermal conductivity integral for UO2 sintered up to 2300 deg C; evolution of fission gases at constant power

    International Nuclear Information System (INIS)

    Stora, J.P.; Chenebault, P.

    1968-01-01

    Two rods of the type 'EL 4 first score' have been irradiated in 'Cyrano' capsules which are suited for continuous measurement of the nuclear power evolved and equipped with thermocouples. The variations of the integral of conductivity of sintered 96 per cent theoretical dense UO 2 has been established until 2300 deg. C; these variations are coherent with those previously measured out-of-pile. The released fission gases have been recovered at different times during the irradiation: the kinetics of release of stable gases is such that, in the experimental conditions (T surface = 610 deg. C, ∫ T s T c kdT = 34.7 W cm -1 ) the fraction of released gases is still widely increasing after 12 days of irradiation. Numerous observations have been made on concentrations of rare gases locally present in the irradiated fuel. (authors) [fr

  2. Effect of X-irradiation on DNA binding activity of NF-kB in EL-4 cells

    International Nuclear Information System (INIS)

    He Shujie; Jin Shunzi; Liu Shuzheng

    2002-01-01

    Changes in time course of the DNA-binding activity of NF-κB as well as the subcellular localization of p65 subunit and expression of IκBα in EL-4 cells after irradiation with 2 Gy and 0.075 Gy X-rays were examined using electrophoresis mobility shift assay (EMSA) and immunohistochemistry (IHC), respectively. Results showed that the increases in DNA-binding activity of NF-κB p50/p50 and p50/p65 were induced by both 0.075 Gy and 2 Gy X-rays. However, the amplitude of the increase in activity of the two dimers was different after irradiation with the two doses of X-rays. After irradiation with 0.075 Gy, the increase in p50/p65 activity was higher than that of p50/p50 activity. After irradiation with 2 Gy, the situation was reversed. Irradiation with both 2 Gy and 0.075 Gy induced an increase in the rate of p65 nuclear translocation and the degradation of IκBα before the increase of its expression, but the degree of these changes after different dose irradiation was different. These results suggest that the transcriptional regulation of NF-κB changes with irradiation dose, resulted in the difference in responses of cells

  3. A new experimental setup established for low-energy nuclear astrophysics studies

    International Nuclear Information System (INIS)

    Chen, S.Z.; Xu, S.W.; He, J.J.; Hu, J.; Rolfs, C.E.; Zhang, N.T.; Ma, S.B.; Zhang, L.Y.; Hou, S.Q.; Yu, X.Q.; Ma, X.W.

    2014-01-01

    An experimental setup for low-energy nuclear astrophysics studies has been recently established at the Institute of Modern Physics (IMP), Lanzhou, China. The driver machine is a 320 kV high voltage platform, which can provide intense currents of proton, alpha and many heavy ion beams. The energy of a proton beam was calibrated against the nominal platform high voltage by using a well-known resonant reaction of 11 B(p,γ) 12 C and a non-resonant reaction 12 C(p,γ) 13 N. The accuracy was achieved to be better than ±0.5 keV. The detection system consists of a Clover-type high-purity germanium detector, a silicon detector and a plastic scintillator. The performance of the detectors was tested by several experiments. The astrophysical S-factors of the 7 Li(p,γ) 8 Be and 7 Li(p,α) 3 He reactions were measured with this new setup, and our data agree with the values found in the literature. In addition, the upgrade of our driver machine and experimental setup has been discussed. As a future goal, a fascinating National Deep Underground Laboratory in China, the deepest underground laboratory all over the world, is prospected

  4. Experimental benchmarking of quantum control in zero-field nuclear magnetic resonance.

    Science.gov (United States)

    Jiang, Min; Wu, Teng; Blanchard, John W; Feng, Guanru; Peng, Xinhua; Budker, Dmitry

    2018-06-01

    Demonstration of coherent control and characterization of the control fidelity is important for the development of quantum architectures such as nuclear magnetic resonance (NMR). We introduce an experimental approach to realize universal quantum control, and benchmarking thereof, in zero-field NMR, an analog of conventional high-field NMR that features less-constrained spin dynamics. We design a composite pulse technique for both arbitrary one-spin rotations and a two-spin controlled-not (CNOT) gate in a heteronuclear two-spin system at zero field, which experimentally demonstrates universal quantum control in such a system. Moreover, using quantum information-inspired randomized benchmarking and partial quantum process tomography, we evaluate the quality of the control, achieving single-spin control for 13 C with an average fidelity of 0.9960(2) and two-spin control via a CNOT gate with a fidelity of 0.9877(2). Our method can also be extended to more general multispin heteronuclear systems at zero field. The realization of universal quantum control in zero-field NMR is important for quantum state/coherence preparation, pulse sequence design, and is an essential step toward applications to materials science, chemical analysis, and fundamental physics.

  5. Static analytical and experimental research of shock absorber to safeguard the nuclear fuel assemblies

    Energy Technology Data Exchange (ETDEWEB)

    Dundulis, Gintautas [Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos Street 3, LT-44403 Kaunas (Lithuania)], E-mail: gintas@mail.lei.lt; Grybenas, Albertas [Laboratory of Materials Research and Testing, Lithuanian Energy Institute, Breslaujos Street 3, LT-44403 Kaunas (Lithuania); Karalevicius, Renatas [Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos Street 3, LT-44403 Kaunas (Lithuania); Makarevicius, Vidas [Laboratory of Materials Research and Testing, Lithuanian Energy Institute, Breslaujos Street 3, LT-44403 Kaunas (Lithuania); Rimkevicius, Sigitas; Uspuras, Eugenijus [Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos Street 3, LT-44403 Kaunas (Lithuania)

    2009-01-15

    The Ignalina Nuclear Power Plant (NPP) has two RBMK-1500 graphite-moderated boiling water multi-channel reactors. The Ignalina NPP Unit 1 was shutdown at the end of 2004, while Unit 2 is foreseen to be shutdown at the end of 2009. At the Ignalina NPP Unit 1 remains approximately 1000 spent fuel assemblies with low burn-up depth. A special set of equipment was developed to reuse these assemblies in the reactor of Unit 2. One of most important items of this set is a container, which is used for the transportation of spent fuel assemblies between the reactors of Unit 1 and Unit 2. A special shock absorber was designed to avoid failure of fuel assemblies in case of hypothetical spent fuel assemblies drop accident during uploading/unloading of spent fuel assemblies to/from container. This shock absorber was examined by using scaled experiments. The objective of this article is the estimation whether the proposed design of shock absorber fulfils the function of the absorber and the optimization of its geometrical parameters using the results of the performed investigations. Static analytical and experimental investigations are presented in the article. The finite element code BRIGADE/Plus was used for the analytical analysis. The calculation model was verified by comparing the experimental investigation and simulation results for further employment of this finite element model in the development of an optimum design of shock absorber. Static simulation was used to perform primary optimization of design and dimension of the shock absorber.

  6. Experimental validation of decay heat calculation codes and associated nuclear data libraries for fusion energy

    International Nuclear Information System (INIS)

    Maekawa, Fujio; Wada, Masayuki; Ikeda, Yujiro

    2001-01-01

    Validity of decay heat calculations for safety designs of fusion reactors was investigated by using decay heat experimental data on thirty-two fusion reactor relevant materials obtained at the 14-MeV neutron source facility of FNS in JAERI. Calculation codes developed in Japan, ACT4 and CINAC version 4, and nuclear data bases such as JENDL/Act-96, FENDL/A-2.0 and Lib90 were used for the calculation. Although several corrections in algorithms for both the calculation codes were needed, it was shown by comparing calculated results with the experimental data that most of activation cross sections and decay data were adequate. In cases of type 316 stainless steel and copper which were important for ITER, prediction accuracy of decay heat within ±10% was confirmed. However, it was pointed out that there were some problems in parts of data such as improper activation cross sections, e,g., the 92 Mo(n, 2n) 91g Mo reaction in FENDL, and lack of activation cross section data, e.g., the 138 Ba(n, 2n) 137m Ba reaction in JENDL. Modifications of cross section data were recommended for 19 reactions in JENDL and FENDL. It was also pointed out that X-ray and conversion electron energies should be included in decay data. (author)

  7. Experimental validation of decay heat calculation codes and associated nuclear data libraries for fusion energy

    Energy Technology Data Exchange (ETDEWEB)

    Maekawa, Fujio; Wada, Masayuki; Ikeda, Yujiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-01-01

    Validity of decay heat calculations for safety designs of fusion reactors was investigated by using decay heat experimental data on thirty-two fusion reactor relevant materials obtained at the 14-MeV neutron source facility of FNS in JAERI. Calculation codes developed in Japan, ACT4 and CINAC version 4, and nuclear data bases such as JENDL/Act-96, FENDL/A-2.0 and Lib90 were used for the calculation. Although several corrections in algorithms for both the calculation codes were needed, it was shown by comparing calculated results with the experimental data that most of activation cross sections and decay data were adequate. In cases of type 316 stainless steel and copper which were important for ITER, prediction accuracy of decay heat within {+-}10% was confirmed. However, it was pointed out that there were some problems in parts of data such as improper activation cross sections, e,g., the {sup 92}Mo(n, 2n){sup 91g}Mo reaction in FENDL, and lack of activation cross section data, e.g., the {sup 138}Ba(n, 2n){sup 137m}Ba reaction in JENDL. Modifications of cross section data were recommended for 19 reactions in JENDL and FENDL. It was also pointed out that X-ray and conversion electron energies should be included in decay data. (author)

  8. Experimental realization of Shor's quantum factoring algorithm using nuclear magnetic resonance.

    Science.gov (United States)

    Vandersypen, L M; Steffen, M; Breyta, G; Yannoni, C S; Sherwood, M H; Chuang, I L

    The number of steps any classical computer requires in order to find the prime factors of an l-digit integer N increases exponentially with l, at least using algorithms known at present. Factoring large integers is therefore conjectured to be intractable classically, an observation underlying the security of widely used cryptographic codes. Quantum computers, however, could factor integers in only polynomial time, using Shor's quantum factoring algorithm. Although important for the study of quantum computers, experimental demonstration of this algorithm has proved elusive. Here we report an implementation of the simplest instance of Shor's algorithm: factorization of N = 15 (whose prime factors are 3 and 5). We use seven spin-1/2 nuclei in a molecule as quantum bits, which can be manipulated with room temperature liquid-state nuclear magnetic resonance techniques. This method of using nuclei to store quantum information is in principle scalable to systems containing many quantum bits, but such scalability is not implied by the present work. The significance of our work lies in the demonstration of experimental and theoretical techniques for precise control and modelling of complex quantum computers. In particular, we present a simple, parameter-free but predictive model of decoherence effects in our system.

  9. The experimental facility for investigation of MHD heat transfer in perspective coolants in nuclear energetics.

    Science.gov (United States)

    Batenin, B. M.; Belyaev, I. A.; Birukov, D. A.; Frick, P. G.; Nikitina, I. S.; Manchkha, S. P.; Pyatnitskaya, N. Yu; Razuvanov, N. G.; Sviridov, E. V.; Sviridov, V. G.

    2017-11-01

    Paper presents the current results of work conducted by a joint research group of MPEI-JIHT RAS for experimental study of liquid metals heat transfer. The team of specialists of MPEI-JIHT RAS put into operation a new mercury MHD facility RK-3. The main components of this stand are: a unique electromagnet, created by specialists of the Budker Institute of Nuclear Physics (BINP), and a sealed liquid-metal circuit. The facility will be explored lifting and standpipe flow of liquid metal in a transverse magnetic field in channels of different forms. For the experiments on the study of heat transfer and hydrodynamics of flows for measuring characteristics such as temperature, speed, pulse characteristics, probe method is used. Presents the first experimental results obtained for a pipe in a transverse magnetic field. During the experiments with various flow parameters data was obtained and processed with constructing temperature fields, dimensionless wall temperature distributions and heat transfer coefficients along the perimeter of the work area. Modes with low frequency pulsations of temperature were discovered. The boundaries where low frequency temperature fluctuations occur were defined in a circular tube.

  10. Experimental and computational studies of thermal mixing in next generation nuclear reactors

    Science.gov (United States)

    Landfried, Douglas Tyler

    The Very High Temperature Reactor (VHTR) is a proposed next generation nuclear power plant. The VHTR utilizes helium as a coolant in the primary loop of the reactor. Helium traveling through the reactor mixes below the reactor in a region known as the lower plenum. In this region there exists large temperature and velocity gradients due to non-uniform heat generation in the reactor core. Due to these large gradients, concern should be given to reducing thermal striping in the lower plenum. Thermal striping is the phenomena by which temperature fluctuations in the fluid and transferred to and attenuated by surrounding structures. Thermal striping is a known cause of long term material failure. To better understand and predict thermal striping in the lower plenum two separate bodies of work have been conducted. First, an experimental facility capable of predictably recreating some aspects of flow in the lower plenum is designed according to scaling analysis of the VHTR. Namely the facility reproduces jets issuing into a crossflow past a tube bundle. Secondly, extensive studies investigate the mixing of a non-isothermal parallel round triple-jet at two jet-to-jet spacings was conducted. Experimental results were validation with an open source computational fluid dynamics package, OpenFOAMRTM. Additional care is given to understanding the implementation of the realizable k-a and Launder Gibson RSM turbulence Models in OpenFOAMRTM. In order to measure velocity and temperature in the triple-jet experiment a detailed investigation of temperature compensated hotwire anemometry is carried out with special concern being given to quantify the error with the measurements. Finally qualitative comparisons of trends in the experimental results and the computational results is conducted. A new and unexpected physical behavior was observed in the center jet as it appeared to spread unexpectedly for close spacings (S/Djet = 1.41).

  11. Growth of the parvovirus minute virus of mice MVMp3 in EL4 lymphocytes is restricted after cell entry and before viral DNA amplification: cell-specific differences in virus uncoating in vitro.

    Science.gov (United States)

    Previsani, N; Fontana, S; Hirt, B; Beard, P

    1997-10-01

    Two murine parvoviruses with genomic sequences differing only in 33 nucleotides (8 amino acids) in the region coding for the capsid proteins show different host cell specificities: MVMi grows in EL4 T lymphocytes and MVMp3 grows in A9 fibroblasts. In this study we compared the courses of infections with these two viruses in EL4 cells in order to investigate at which step(s) the infection process of MVMp3 is interrupted. The two viruses bound equally well to EL4 cells, and similar amounts of MVMi and MVMp3 input virion DNA appeared in the nuclear fractions of EL4 cells 1 h after infection. However, double-stranded replicative-form (RF) DNA of the two viruses appeared at different times, at 10 h postinfection with MVMi and at 24 h postinfection with MVMp3. The amount of MVMp3 RF DNA detected at 24 h was very small because it was produced only in a tiny subset of the population of EL4 cells that proved to be permissive for MVMp3. Replication of double-stranded viral DNA in EL4 cells was measured after transfection of purified RF DNA, cloned viral DNA, and cloned viral DNA with a mutation preventing synthesis of the capsid proteins. In each of these cases, DNA replication was comparable for MVMi and MVMp3. Production of virus particles also appeared to be similar after transfection of the two types of RF DNA into EL4 cells. Conversion of incoming 32P-labeled single-stranded MVM DNA to 32P-labeled double-stranded RF DNA was detected only after RF DNA amplification, indicating that few molecules serve as templates for viral DNA amplification. We showed that extracts of EL4 cells contain a factor which can destabilize MVMi virions but not MVMp3 by testing the sensitivity of viral DNA to DNase and by CsCl gradient analyses of viral particles. We therefore conclude that the MVMp3 life cycle is arrested after the transport of virions to the nucleus and prior to the replication of RF DNA, most likely at the stage of viral decapsidation.

  12. Paraoxon induces apoptosis in EL4 cells via activation of mitochondrial pathways.

    Science.gov (United States)

    Saleh, A M; Vijayasarathy, C; Masoud, L; Kumar, L; Shahin, A; Kambal, A

    2003-07-01

    The toxicity of organophosphorus compounds, such as paraoxon (POX), is due to their anticholinesterase action. Recently, we have shown that, at noncholinergic doses (1 to 10 nM), POX (the bioactive metabolite of parathion) causes apoptotic cell death in murine EL4 T-lymphocytic leukemia cell line through activation of caspase-3. In this study, by employing caspase-specific inhibitors, we extend our observations to elucidate the sequence of events involved in POX-stimulated apoptosis. Pretreatment of EL4 cells with the caspase-9-specific inhibitor zLEHD-fmk attenuated POX-induced apoptosis in a dose-dependent manner, whereas the caspase-8 inhibitor zIETD-fmk had no effect. Furthermore, the activation of caspase-9, -8, and -3 in response to POX treatment was completely inhibited in the presence of zLEHD-fmk, implicating the involvement of caspase 9-dependent mitochondrial pathways in POX-stimulated apoptosis. Indeed, under both in vitro and in vivo conditions, POX triggered a dose- and time-dependent translocation of cytochrome c from mitochondria into the cytosol, as assessed by Western blot analysis. Investigation of the mechanism of cytochrome c release revealed that POX disrupted mitochondrial transmembrane potential. Neither this effect nor cytchrome c release was dependent on caspase activation, since the general inhibitor of the caspase family zVAD-fmk did not influence both processes. Finally, POX treatment also resulted in a time-dependent up-regulation and translocation of the proapoptotic molecule Bax to mitochondria. Inhibition of this event by zVAD-fmk suggests that the activation and translocation of Bax to mitochondria is subsequent to activation of the caspase cascades. The results indicate that POX induces apoptosis in EL4 cells through a direct effect on mitochondria by disrupting its transmembrane potential, causing the release of cytochrome c into the cytosol and subsequent activation of caspase-9. Inhibition of this specific pathway might provide

  13. Doxorubicin attached to HPMA copolymer via amide bond modifies the glycosylation pattern of EL4 cells.

    Science.gov (United States)

    Kovar, Lubomir; Etrych, Tomas; Kabesova, Martina; Subr, Vladimir; Vetvicka, David; Hovorka, Ondrej; Strohalm, Jiri; Sklenar, Jan; Chytil, Petr; Ulbrich, Karel; Rihova, Blanka

    2010-08-01

    To avoid the side effects of the anti-cancer drug doxorubicin (Dox), we conjugated this drug to a N-(2-hydroxypropyl)methacrylamide (HPMA) copolymer backbone. Dox was conjugated via an amide bond (Dox-HPMA(AM), PK1) or a hydrazone pH-sensitive bond (Dox-HPMA(HYD)). In contrast to Dox and Dox-HPMA(HYD), Dox-HPMA(AM) accumulates within the cell's intracellular membranes, including those of the Golgi complex and endoplasmic reticulum, both involved in protein glycosylation. Flow cytometry was used to determine lectin binding and cell death, immunoblot to characterize the presence of CD7, CD43, CD44, and CD45, and high-performance anion exchange chromatography with pulsed amperometric detector analysis for characterization of plasma membrane saccharide composition. Incubation of EL4 cells with Dox-HPMA(AM) conjugate, in contrast to Dox or Dox-HPMA(HYD), increased the amounts of membrane surface-associated glycoproteins, as well as saccharide moieties recognized by peanut agglutinin, Erythrina cristagalli, or galectin-1 lectins. Only Dox-HPMA(AM) increased expression of the highly glycosylated membrane glycoprotein CD43, while expression of others (CD7, CD44, and CD45) was unaffected. The binding sites for galectin-1 are present on CD43 molecule. Furthermore, we present that EL4 treated with Dox-HPMA(AM) possesses increased sensitivity to galectin-1-induced apoptosis. In this study, we demonstrate that Dox-HPMA(AM) treatment changes glycosylation of the EL4 T cell lymphoma surface and sensitizes the cells to galectin-1-induced apoptosis.

  14. Mechanism of phorbol ester-mediated protein kinase C activation in EL4 thymoma cells

    International Nuclear Information System (INIS)

    Huang, F.L.; Arora, P.K.; Hanna, E.E.; Huang, K.P.

    1987-01-01

    Mouse thymoma EL4 cells respond to phorbol 12-myristate 13-acetate (PMA) in interleukin-2 secretion and growth inhibition. A rapid translocation of protein kinase C (PKC) from cytosol to the particulate fraction and followed by proteolytic degradation occur when EL4 cells are incubated with PMA. In the present study the translocated membrane-associated PKC (PP-PKC) was solubilized by buffer containing NP-40 and its behavior on column chromatography, molecular weight, and kinetic properties were compared to the cytosolic PKC (CS-PKC) from untreated cells. From DE-52 cellulose column, CS-PKC could be eluted by buffer containing 0.1 M KCl, whereas PP-PKC was eluted with buffer containing 0.25 M KCl and 0.2% NP-40. On gel filtration the partially purified PP-PKC from DE-52 was separated into two species: a high Mr species, which was a complex of 82KDa PKC, PMA, and lipid as evidenced by immunoblot analysis and labeling with [ 3 H]PMA and [ 3 H]myristic acid, and a 82KDa species, which was free of PMA and lipid. This 82KDa PP-PKC, though similar to the CS-PKC in molecular weight, is distinguishable from the CS-PKC in having lower Ka values for both Ca 2+ and PS and no longer requires diacylglycerol for maximum activation. These results indicate that upon PMA treatment of EL4 cells, the CS-PKC was modified through enhancing the kinase activity and affinity for membrane lipid. The modification results in the translocation and complexing of PKC with membrane lipid and PMA and subsequent degradation

  15. Experimental studies of thermal and chemical interactions between molten aluminum and nuclear dispersion fuels with water

    International Nuclear Information System (INIS)

    Farahani, A.A.

    1997-01-01

    Because of the possibility of rapid physical and chemical molten fuel-water interactions during a core melt accident in noncommercial or experimental reactors, it is important to understand the interactions that might occur if these materials were to contact water. An existing vertical 1-D shock tube facility was improved and a gas sampling device to measure the gaseous hydrogen in the upper chamber of the shock tube was designed and built to study the impact of a water column driven downward by a pressurized gas onto both molten aluminum (6061 alloy) and oxide and silicide depleted nuclear dispersion fuels in aluminum matrices. The experiments were carried out with melt temperatures initially at 750 to 1,000 C and water at room temperature and driving pressures of 0.5 and 1 MPa. Very high transient pressures, in many cases even larger than the thermodynamic critical pressure of the water (∼ 20 MPa), were generated due to the interactions between the water and the crucible and its contents. The molten aluminum always reacted chemically with the water but the reaction did not increase consistently with increasing melt temperature. An aluminum ignition occurred when water at room temperature impacted 28.48 grams of molten aluminum at 980.3 C causing transient pressures greater than 69 MPa. No signs of aluminum ignition were observed in any of the experiments with the depleted nuclear dispersion fuels, U 3 O 8 -Al and U 3 Si 2 -Al. The greater was the molten aluminum-water chemical reaction, the finer was the debris recovered for a given set of initial conditions. Larger coolant velocities (larger driving pressures) resulted in more melt fragmentation but did not result in more molten aluminum-water chemical reaction. Decreasing the water temperature also resulted in more melt fragmentation and did not suppress the molten aluminum-water chemical reaction

  16. Phospholipase D2 Enhances Epidermal Growth Factor-Induced Akt Activation in EL4 Lymphoma Cells

    Directory of Open Access Journals (Sweden)

    Manpreet S. Chahal

    2010-07-01

    Full Text Available Phospholipase D2 (PLD2 generates phosphatidic acid through hydrolysis of phosphatidylcholine. PLD2 has been shown to play a role in enhancing tumorigenesis. The epidermal growth factor receptor (EGFR can both activate and interact with PLD2. Murine lymphoma EL4 cells lacking endogenous PLD2 present a unique model to elucidate the role of PLD2 in signal transduction. In the current study, we investigated effects of PLD2 on EGF response. Western blotting and RT-PCR were used to establish that both parental cells and PLD2 transfectants express endogenous EGFR. Levels of EGFR protein are increased in cells expressing active PLD2, as compared to parental cells or cells expressing inactive PLD2. EGF stimulates proliferation of EL4 cells transfected with active PLD2, but not parental cells or cells transfected with inactive PLD2. EGF-mediated proliferation in cells expressing active PLD2 is dependent on the activities of both the EGFR and the PI3K/Akt pathway, as demonstrated by studies using protein kinase inhibitors. EGF-induced invasion through a synthetic extracellular matrix is enhanced in cells expressing active PLD2, as compared to parental cells or cells expressing inactive PLD2. Taken together, the data suggest that PLD2 acts in concert with EGFR to enhance mitogenesis and invasion in lymphoma cells.

  17. Phospholipase D2 Enhances Epidermal Growth Factor-Induced Akt Activation in EL4 Lymphoma Cells.

    Science.gov (United States)

    Chahal, Manpreet S; Brauner, Daniel J; Meier, Kathryn E

    2010-07-02

    Phospholipase D2 (PLD2) generates phosphatidic acid through hydrolysis of phosphatidylcholine. PLD2 has been shown to play a role in enhancing tumorigenesis. The epidermal growth factor receptor (EGFR) can both activate and interact with PLD2. Murine lymphoma EL4 cells lacking endogenous PLD2 present a unique model to elucidate the role of PLD2 in signal transduction. In the current study, we investigated effects of PLD2 on EGF response. Western blotting and RT-PCR were used to establish that both parental cells and PLD2 transfectants express endogenous EGFR. Levels of EGFR protein are increased in cells expressing active PLD2, as compared to parental cells or cells expressing inactive PLD2. EGF stimulates proliferation of EL4 cells transfected with active PLD2, but not parental cells or cells transfected with inactive PLD2. EGF-mediated proliferation in cells expressing active PLD2 is dependent on the activities of both the EGFR and the PI3K/Akt pathway, as demonstrated by studies using protein kinase inhibitors. EGF-induced invasion through a synthetic extracellular matrix is enhanced in cells expressing active PLD2, as compared to parental cells or cells expressing inactive PLD2. Taken together, the data suggest that PLD2 acts in concert with EGFR to enhance mitogenesis and invasion in lymphoma cells.

  18. TGF-beta1 expression in EL4 lymphoma cells overexpressing growth hormone.

    Science.gov (United States)

    Farmer, John T; Weigent, Douglas A

    2006-03-01

    Our previous studies show that growth hormone overexpression (GHo) upregulates the expression of the IGF-1R and IGF-2R resulting in the protection of the EL4 lymphoma cell line from apoptosis. In this study, we report that GHo also increases TGF-beta1 protein expression measured by luciferase promoter assay, Western analysis, and ELISA. Further, the data show that antibody to TGF-betaR2 decreases TGF-beta1 promoter activity to the level of vector alone control cells. GHo cells treated with (125)I-rh-latent TGF-beta1 showed increased activation of latent TGF-beta1 as measured by an increase in the active 24kDa, TGF-beta1 compared to vector alone control cells. The ability of endogenous GH to increase TGF-beta1 expression is blocked in EL4 cells by antisense but not sense oligodeoxynucleotides or in cells cultured with antibody to growth hormone (GH). The data suggest that endogenous GH may protect from apoptosis through the IGF-1R receptor while limiting cellular growth through increased expression and activation of TGF-beta1.

  19. Activation of macrophages for microbicidal and tumoricidal effector functions by soluble factors from EL-4, a continuous T cell line.

    OpenAIRE

    Nacy, C A; James, S L; Benjamin, W R; Farrar, J J; Hockmeyer, W T; Meltzer, M S

    1983-01-01

    Macrophages treated with culture fluids from EL-4 cells, a continuous T cell line, were activated to kill mKSA-TU-5 fibrosarcoma cells, amastigotes of Leishmania tropica, and schistosomula of Schistosoma mansoni. Active EL-4 factors eluted from Sephadex G-100 in two distinct regions: molecular weight 45,000 (activities induced killing of unrelated intracellular and extracellular targets) and molecular weight 23,000 (activities induced killing of extracellular targets only). These results conf...

  20. Dynamic analytical and experimental research of shock absorber to safeguard the nuclear fuel assemblies

    Energy Technology Data Exchange (ETDEWEB)

    Dundulis, Gintautas, E-mail: gintas@mail.lei.lt [Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos str. 3, LT-44403 Kaunas (Lithuania); Grybenas, Albertas [Laboratory of Materials Research and Testing, Lithuanian Energy Institute, Breslaujos str. 3, LT-44403 Kaunas (Lithuania); Karalevicius, Renatas [Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos str. 3, LT-44403 Kaunas (Lithuania); Makarevicius, Vidas [Laboratory of Materials Research and Testing, Lithuanian Energy Institute, Breslaujos str. 3, LT-44403 Kaunas (Lithuania); Rimkevicius, Sigitas; Uspuras, Eugenijus [Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos str. 3, LT-44403 Kaunas (Lithuania)

    2013-07-15

    Highlights: • Plastical deformation of the shock absorber. • Dynamic testing of the scaled shock absorber. • Dynamic simulation of the shock absorber using finite element method. • Strain-rate evaluation in dynamic analysis. • Variation of displacement, acceleration and velocity during dynamic impact. -- Abstract: The Ignalina Nuclear Power Plant (NPP) has two RBMK-1500 graphite moderated boiling water multi-channel reactors. The Ignalina NPP Unit 1 was shut down at the end of 2004 while Unit 2 has been in operation for over 5 years. After shutdown at the Unit 1 remained spent fuel assemblies with low burn-up depth. In order to reuse these assemblies in the reactor of Unit 2 a special set of equipment was developed. One of the most important items of this set is a container, which is used for the transportation of spent fuel assemblies between the reactors of Unit 1 and Unit 2. A special shock absorber was designed to avoid failure of fuel assemblies in case of hypothetical spent fuel assemblies drop accident during uploading/unloading of spent fuel assemblies to/from container. This shock absorber was examined using scaled experiments and finite element analysis. Static and dynamic investigations of the shock absorber were performed for the estimation and optimization of its geometrical parameters. The objective of this work is the estimation whether the proposed design of shock absorber can fulfil the stopping function of the spent fuel assemblies and is capable to withstand the dynamics load. Experimental testing of scaled shock absorber models and dynamic analytical investigations using the finite element code ABAQUS/Explicit were performed. The simulation model was verified by comparing the experimental and simulation results and it was concluded that the shock absorber is capable to withstand the dynamic load, i.e. successful force suppression function in case of accident.

  1. On the uncertainty of experimental nuclear data. Taking a lesson from the other

    International Nuclear Information System (INIS)

    Harada, Hideo

    2013-01-01

    Possible paths to obtain the nuclear data with the required target accuracy are discussed based on the lessons from the research field of fundamental physical constants and recent advancements on nuclear data measurement techniques. (author)

  2. Research in experimental nuclear physics: Progress report, April 1, 1988--March 31, 1989

    International Nuclear Information System (INIS)

    Moore, C.F.

    1988-11-01

    This report summarizes the work carried out by personnel from the University of Texas at Austin at the Los Alamos Clinton P. Anderson Meson Physics Facility (LAMPF) during the calendar year 1987 under grant AS05-87ER40343 between The University of Texas at Austin and the United States Department of Energy. The research activities involved experiments done with the Energetic Pion Channel and Spectrometer (EPICS), the Low Energy Pion Channel (LEP), the Pion and Particle Physics Channel (P 3 ), and the High Resolution Spectrometer (HRS). A brief overview of work supported by this grant is given. This report contains a list of abstracts of papers reported at scientific meetings, a list of invited papers, and a list of published papers and preprints. These papers summarize experiments undertaken in this grant period and indicate the work accomplished by the participants in this program of medium energy nuclear physics research. Much of the experimental work that has been attempted during the period covered by this report has either been published or submitted for publication. Also included is a list of the recent proposals on which we have participation at LAMPF, and a list of personnel who have participated in this research program

  3. Experimental studies of thermal and chemical interactions between oxide and silicide nuclear fuels with water

    Energy Technology Data Exchange (ETDEWEB)

    farahani, A.A.; Corradini, M.L. [Univ. of Wisconsi, Madison, WI (United States)

    1995-09-01

    Given some transient power/cooling mismatch is a nuclear reactor and its inability to establish the necessary core cooling, energetic fuel-coolant interactions (FCI`s commonly called `vapor explosions`) could occur as a result of the core melting and coolant contact. Although a large number of studies have been done on energetic FCI`s, very few experiments have been performed with the actual fuel materials postulated to be produced in severe accidents. Because of the scarcity of well-characterized FCI data for uranium allows in noncommercial reactors (cermet and silicide fuels), we have conducted a series of experiments to provide a data base for the foregoing materials. An existing 1-D shock-tube facility was modified to handle depleted radioactive materials (U{sub 3}O{sub 8}-Al, and U{sub 3}Si{sub 2}-Al). Our objectives have been to determine the effects of the initial fuel composition and temperature and the driving pressure (triggering) on the explosion work output, dynamic pressures, transient temperatures, and the hydrogen production. Experimental results indicate limited energetics, mainly thermal interactions, for these fuel materials as compared to aluminum where more chemical reactions occur between the molten aluminum and water.

  4. An aerial radiological survey of the Saxton Nuclear Experimental Corporation facility and surrounding area, Saxton, Pennsylvania

    International Nuclear Information System (INIS)

    Hoover, R.A.

    1991-10-01

    An aerial radiological survey was conducted during the period July 5 to 22, 1989, over an 83-square kilometer (32-square-mile) area surrounding the Saxton Nuclear Experimental Corporation (SNEC) facility which is owned by General Public Utilities and located near Saxton, Pennsylvania. The survey was conducted at a nominal altitude of 61 meters (200 feet) with line spacings of 91 meters (300 feet). A contour map of the terrestrial gamma exposure rate extrapolated to 1 meter above ground level (AGL) was prepared and overlaid on an aerial photograph and a set of United States Geological Survey (USGS) topographic maps of the area. The terrestrial exposure rates varied from about 9 to 11 microroentgens per hour (μR/h) over most of the survey area. The levels over the SNEC family did not differ from the exposure rates seen over the entire survey area. Cesium-137 (Cs-137) levels typical of worldwide fallout deposition were detected throughout the surveyed area. No other trends of Cs-137 were observed. Soil samples and pressurized ion chamber measurements were obtained at six locations within the survey boundaries to support the aerial data

  5. Read-only-memory-based quantum computation: Experimental explorations using nuclear magnetic resonance and future prospects

    International Nuclear Information System (INIS)

    Sypher, D.R.; Brereton, I.M.; Wiseman, H.M.; Hollis, B.L.; Travaglione, B.C.

    2002-01-01

    Read-only-memory-based (ROM-based) quantum computation (QC) is an alternative to oracle-based QC. It has the advantages of being less 'magical', and being more suited to implementing space-efficient computation (i.e., computation using the minimum number of writable qubits). Here we consider a number of small (one- and two-qubit) quantum algorithms illustrating different aspects of ROM-based QC. They are: (a) a one-qubit algorithm to solve the Deutsch problem; (b) a one-qubit binary multiplication algorithm; (c) a two-qubit controlled binary multiplication algorithm; and (d) a two-qubit ROM-based version of the Deutsch-Jozsa algorithm. For each algorithm we present experimental verification using nuclear magnetic resonance ensemble QC. The average fidelities for the implementation were in the ranges 0.9-0.97 for the one-qubit algorithms, and 0.84-0.94 for the two-qubit algorithms. We conclude with a discussion of future prospects for ROM-based quantum computation. We propose a four-qubit algorithm, using Grover's iterate, for solving a miniature 'real-world' problem relating to the lengths of paths in a network

  6. Aerosols from metal cutting techniques typical of decommissioning nuclear facilities - experimental system for collection and characterization

    International Nuclear Information System (INIS)

    Newton, G.J.; Hoover, M.D.; Barr, E.B.; Wong, B.A.; Ritter, P.D.

    1982-01-01

    Decommissioning of radioactively contaminated sites has the potential for creating radioactive and other potentially toxic aerosols. We describe an experimental system to collect and characterize aerosols from metal cutting activities typical of those used in decommissioning of nuclear facilities. A special enclosure was designed for the experiment and consisted of a 2-in. x 4-in. stud frame with double walls of flame retardant polyethylene film. Large plexiglass windows allowed the cutting operations to be directed and filmed. Ventilation was 8500 L/min (300 CFM) exhausted through HEPA filters. Seven cutting techniques were evaluated: pipe cutter, reciprocating saw, band saw, chop saw, oxy-acetylene torch, electric arc cut rod and plasma torch. Two grinding tools were also evaluated. Materials cut were 2-, 3- and 4-in. dia schedule 40, 80 and 180 type 304L stainless steel pipe. Basic studies were done on uncontaminated pipe. Four-inch-diameter sections of schedule 180 type 304L stainless steel pipe with radioactively contaminated internal surfaces were also cut. The experiments controlled important variables including tools, cutting technique, and type and thickness of material. 15 references, 4 figures, 2 tables

  7. Training Course of Experimental Chemistry in the Nuclear Fuel Cycle: Solid State and Solution Chemistry

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ju hyeong; Park, Kwangheon; Kim, Tae hoon; Park, Hyoung gyu; Kim, Jisu [Kyunghee University, Yongin (Korea, Republic of); Song, Hyuk jin [Dongguk University, Gyeongju (Korea, Republic of); Lee, Chan ki; Kang, Do kyu; Jeong, Hyeon jun [UNIST, Ulsan (Korea, Republic of)

    2016-10-15

    In this experimental study program in Tohoku University, basic experiments were done by the participants. First one is the hydrogen reduction experiment of the mixture of UO{sub 2} and ZrO{sub 2}. Second one is to observe microscopic structure of solid solution of UO{sub 2} and ZrO{sub 2} using SEM/EDX and XRD system, simulated fuel debris. Third one is milking process of {sup 239}Np from {sup 243}Am by solvent extraction using Tri-n-Octylamine (TOA). Last one is solvent extraction in PUREX by the simulated mixed aqueous solution of U, {sup 85}Sr and {sup 239}Np which is represented minor actinide elements included in the spent nuclear fuel. Uranium is separated from aqueous phase to organic phase during solvent extraction procedure using TBP and dodecane. Also, neptunium can be extracted to organic phase as nitric acid concentration change. The extraction behavior of neptunium is different by oxidation state in aqueous phase. The behavior of neptunium is represented as a combined form of these oxidation states in experiment. Therefore, because the oxidation states of neptunium can be controlled by controlling the concentration of nitric acid, the extractability of neptunium can be controlled.

  8. Alteration of 'R7T7' type nuclear glasses: statistical approach, experimental validation, local evolution model

    International Nuclear Information System (INIS)

    Thierry, F.

    2003-02-01

    The aim of this work is to propose an evolution of nuclear (R7T7-type) glass alteration modeling. The first part of this thesis is about development and validation of the 'r(t)' model. This model which predicts the decrease of alteration rates in confined conditions is based upon a coupling between a first-order dissolution law and a diffusion barrier effect of the alteration gel layer. The values and the uncertainties regarding the main adjustable parameters of the model (α, Dg and C*) have been determined from a systematic study of the available experimental data. A program called INVERSION has been written for this purpose. This work lead to characterize the validity domain of the 'r(t)' model and to parametrize it. Validation experiments have been undertaken, confirming the validity of the parametrization over 200 days. A new model is proposed in the second part of this thesis. It is based on an inhibition of glass dissolution reaction by silicon coupled with a local description of silicon retention in the alteration gel layer. This model predicts the evolutions of boron and silicon concentrations in solution as well as the concentrations and retention profiles in the gel layer. These predictions have been compared to measurements of retention profiles by the secondary ion mass spectrometry (SIMS) method. The model has been validated on fractions of gel layer which reactivity present low or moderate disparities. (author)

  9. Experimental simulation study on hydraulic behavior of the main heat exchanger of Daqing 200 MW nuclear heating reactor

    International Nuclear Information System (INIS)

    Jiang Shengyao; Zhang Youjie; Jia Haijun; Bo Jinhai; Hong Liuming; Bo Hanliang; Liu Zhiyong

    1997-07-01

    The hydraulic behavior of the main heat exchanger of Daqing 200 MW nuclear heating reactor is studied through a 1:2.33 test model. The design and other feature of the test model is described. The experimental results show that the flow resistance coefficient of the heat exchanger becomes self-simulation when Reynolds number is greater than 5000. The value of flow resistance coefficient at self-simulation condition and the distribution of pressure drop in the heat exchanger are given through experiment. The option design to reduce flow resistance is proposed. The designed and experimental value for the flow resistance coefficient are in good agreement. The variation of system parameters during flow excursion was described. The experimental results are of great significant for the final design of the main heat exchanger of Daqing 200 MW nuclear heating reactor. (2 refs., 5 figs., 1 tab.)

  10. Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors

    Science.gov (United States)

    Bersano, Andrea

    With reference to innovative heat exchangers to be used in passive safety system of Gen- eration IV nuclear reactors and Small Modular Reactors it is necessary to study the natural circulation and the efficiency of heat removal systems. Especially in safety systems, as the decay heat removal system of many reactors, it is increasing the use of passive components in order to improve their availability and reliability during possible accidental scenarios, reducing the need of human intervention. Many of these systems are based on natural circulation, so they require an intense analysis due to the possible instability of the related phenomena. The aim of this thesis work is to build a scaled facility which can reproduce, in a simplified way, the decay heat removal system (DHR2) of the lead-cooled fast reactor ALFRED and, in particular, the bayonet heat exchanger, which transfers heat from lead to water. Given the thermal power to be removed, the natural circulation flow rate and the pressure drops will be studied both experimentally and numerically using the code RELAP5 3D. The first phase of preliminary analysis and project includes: the calculations to design the heat source and heat sink, the choice of materials and components and CAD drawings of the facility. After that, the numerical study is performed using the thermal-hydraulic code RELAP5 3D in order to simulate the behavior of the system. The purpose is to run pretest simulations of the facility to optimize the dimensioning setting the operative parameters (temperature, pressure, etc.) and to chose the most adequate measurement devices. The model of the system is continually developed to better simulate the system studied. High attention is dedicated to the control logic of the system to obtain acceptable results. The initial experimental tests phase consists in cold zero power tests of the facility in order to characterize and to calibrate the pressure drops. In future works the experimental results will be

  11. The effect of medium composition on interleukin-2 production by murine EL-4 thymoma cells

    Directory of Open Access Journals (Sweden)

    Galesi A. L. L.

    2004-01-01

    Full Text Available Due to the role of interleukin-2 (IL-2 in the mediation of immune response, this cytokine has been used in the treatment of some types of cancer and infectious diseases. However, relatively high levels of this cytokine are required to achieve significant activity. The aim of this work was to study a culture medium composition designed to increase the production of IL-2 by suspended murine EL-4 cells. The cultivations were carried out aiming at producing IL-2 in stirred bioreactors. The effects of concentration of glutamine, phorbol-12-myristate-13-acetate (PMA, concanavalin A (Con A, Pluronic F68, and fetal calf serum (FCS on cell viability and IL-2 production were evaluated. PMA alone was more efficient in IL-2 production than it was in association with Con A. The maximum IL-2 production was around 162 ng/mL with 856 ng/mL PMA and 1.45% (v/v FCS.

  12. The EL-4 reactor. Changing of a pressure tube on a test loop

    International Nuclear Information System (INIS)

    Foulquier, H.; Clara, P.

    1964-01-01

    Right from the beginning of the EL-4 project, the research convected with the overall design of the reactor was guided by the various technical specifications resulting from a justifiable concern about the reliability. The external and internal tubes of each layer situated in the reactor block had in particular to be interchangeable. The research alone into the dismantling of the external tube, i.e in fact the pressure tube, justified a certain number of full-scale tests on a model. The tests carried out under relevant conditions on a non-irradiated structure made it possible to define a complete ranger of of positioning and un-positioning sequences at a distance for such a pressure tube. (authors) [fr

  13. The inhibition of superoxide production in EL4 lymphoma cells overexpressing growth hormone.

    Science.gov (United States)

    Arnold, Robyn E; Weigent, Douglas A

    2003-05-01

    A substantial body of research exists to support the production of growth hormone by cells of the immune system. However, the function and mechanism of action of lymphocyte-derived growth hormone remain largely unelucidated. Since, it has been found that exogenous growth hormone (GH) primes neutrophils for the production of reactive oxygen intermediates (ROI) and in particular superoxide (O2-), we investigated the role of GH on the production of O2- in T cells. Furthermore, we examined whether endogenous and exogenous GH act similarly. Our studies show that overexpression of GH in EL4, a T-cell lymphoma cell line, results in a decrease in the production of O2- compared to control cells, as detected using the fluorescent dye, dihydroethidium. O2- production in control cells was not affected by treatment with inhibitors of xanthine oxidase or a non-specific NADPH-oxidase inhibitor. However, treatment with diallyl sulfide, an inhibitor of cytochrome P450 2E1 mimicked the reduction in O2- production seen in cells overexpressing GH. Although no significant change could be detected in CYP2E1 protein levels, CYP2E1 activity was found to be greater in control EL4 than in cells overexpressing GH. Both the decrease in O2- production and the lower CYP2E1 activity in GH overexpressing cells could be abrogated by treatment with N(G)-monomethyl-L-arginine, an inhibitor of nitric oxide synthase. The overexpression of GH protects cells from apoptosis induced by isoniazid, a CYP2E1 inducer, suggesting a role for nitric oxide as a mediator in the regulation of xenobiotic metabolism and apoptosis-protection by lymphocyte GH.

  14. Integrated modulation of phorbol ester-induced Raf activation in EL4 lymphoma cells.

    Science.gov (United States)

    Han, Shujie; Meier, Kathryn E

    2009-05-01

    The EL4 murine lymphoma cell line exists in variant phenotypes that differ with respect to responses to the tumor promoter phorbol 12-myristate 13-acetate (PMA1). Previous work showed that "PMA-sensitive" cells, characterized by a high magnitude of PMA-induced Erk activation, express RasGRP, a phorbol ester receptor that directly activates Ras. In "PMA-resistant" and "intermediate" EL4 cell lines, PMA induces Erk activation to lesser extents, but with a greater response in intermediate cells. In the current study, these cell lines were used to examine mechanisms of Raf-1 modulation. Phospho-specific antibodies were utilized to define patterns and kinetics of Raf-1 phosphorylation on several sites. Further studies showed that Akt is constitutively activated to a greater extent in PMA-resistant than in PMA-sensitive cells, and also to a greater extent in resistant than intermediate cells. Akt negatively regulates Raf-1 activation (Ser259), partially explaining the difference between resistant and intermediate cells. Erk activation exerts negative feedback on Raf-1 (Ser289/296/301), thus resulting in earlier termination of the signal in cells with a higher level of Erk activation. RKIP, a Raf inhibitory protein, is expressed at higher levels in resistant cells than in sensitive or intermediate cells. Knockdown of RKIP increases Erk activation and also negative feedback. In conclusion, this study delineates Raf-1 phosphorylation events occurring in response to PMA in cell lines with different extents of Erk activation. Variations in the levels of expression and activation of multiple signaling proteins work in an integrated fashion to modulate the extent and duration of Erk activation.

  15. Extrusion and drawing of zircaloy 2. Production of pressure tubes for EL-4

    International Nuclear Information System (INIS)

    Thevenet, J.

    1964-01-01

    The authors give briefly the physical mechanical and chemical properties of zircaloy 2, as far as the transformation of this alloy is concerned. Extrusion: After a few general remarks concerning the extrusion and co-extrusion, including a comparison of the deformation resistance of canning metals and of zircaloy 2, the following points are considered: - the difficulties occurring because of the use of this alloy: - atmosphere protection - adjustment on to the machine tools - low thermal conductivity - economy of the metal (price) - the factors affecting the quality of the extruded products extrusion under a copper can and under lubricant glass - fine grain structure - temperature homogeneity - working temperature The transformation cycle - '550 kg ingot - preliminary shape 'for drawing of EL-4 tubes (112 x 120 L 12 m)' - is described in detail (extrusion or forging of the φ = 340 ingot into φ = 220 billets, cutting into lengths and hot drilling at φ = 125, fixing into a copper can and rough extrusion). Drawing: The main difficulties are due to seizing of the tools and to the necessity of protecting the alloy from the atmosphere during annealings. A brief description is given of drawing out on a short mandrel, on a long mandrel, of laminating on a reducing machine and of the carrying out of an annealing, as well as of the production of EL-4 tubes (φ =107 x 113 L 430 m) by drawing out shapes having a size of 112 x 120 on long mandrels. Conclusion: It is possible by extrusion and drawing to produce zircaloy 2 tubes similar to those which may be obtained normally using stainless steel. (authors) [fr

  16. Construction of the core of the 'heavy water-gas' reactor EL 4; Structures du coeur du reacteur 'eau- lourde-gaz EL 4'

    Energy Technology Data Exchange (ETDEWEB)

    Bernard, J L; Foulquier, H; Thome, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The core of this reactor consists of a vessel containing heavy water, through which pass a series of pressure tubes for circulation of the cooling gas under boat pressure. The basic specifications which greatly influenced the design of this construction relate to aspects of safety in operation (fuel loading from both faces of the reactor, replacement of the components on both faces), neutronic demands (minimum absorption of the components lattice parameter, diameter of the pressure tubes) and thermal considerations (output temperature 500 C). These specifications have led to a' horizontal arrangement of the pressure tubes and raised very difficult problems of clearance, which make it impossible (for the dimensions of EL 4) to resort to expansion bellows on the pressure tubes. The result is a semi-rigid vessel in which the pressure tubes contribute to a large extent the mechanical resistance of the system by acting as a brace, whence the high stresses on the joints and pressure tubes (and the choice of zirconium alloys). The construction components include the pressure tube, the joints, the thermal insulation and the liner tube. A brief account is given of the testing methods used and the performances of these various units is particular. The safety factors foreseen for the pressure tube, and the design and manufacture, taking account of tolerances of the thickened ends necessary for fitting the tubes in place and designing the joints. The joints connecting the pressure tubes to the reactor tank, which are only accessible through the inside of the channel prolonging the pressure tube. These joints must not be a weak part in the construction. Two types have been developed: a rolled joint where the ends of the pressure tube are directly flanged onto the tank, and a welded joint using zircaloy-stainless steel transition pieces added to the ends of the pressure tube. All these joints are made by remote control and are removable. Two solutions have been found to the

  17. An experimental study of assessment of weld quality on fatigue reliability analysis of a nuclear pressure vessel

    International Nuclear Information System (INIS)

    Dai Shuhe

    1993-01-01

    The steam generator in PWR primary coolant system China of Qinshan Nuclear Power Plant is a crucial unit belonging to the category of nuclear pressure vessel. The purpose of this research work is to make an examination of the weld quality of the steam generator under fatigue loading and to assess its reliability by using the experimental results of fatigue test of material of nuclear pressure vessel S-271 (Chinese Standard) and of qualified tests of welded seams of a simulated prototype of bottom closure head of the steam generator. A guarantee of weld quality is proposed as a subsequent verification for China National Nuclear Safety Supervision Bureau. The results of reliability analysis reported in this work can be taken as a supplementary material of Probabilistic Safety Assessment (PSA) of Qinshan Nuclear Power Plant. According to the requirement of Provision II-1500 cyclic testing, ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plant Components, a simulated prototype of the bottom closure head of the steam generator was made for qualified tests. To find the quantified results of reliability assessment by using the testing data, two proposals are presented

  18. Summary of experimental tests of elastomeric seismic isolation bearings for use in nuclear reactor plants

    International Nuclear Information System (INIS)

    Seidensticker, R.W.; Chang, Y.W.; Kulak, R.F.

    1992-01-01

    This paper describes an experimental test program for isolator bearings which was developed to help establish the viability of using laminated elastomer bearings for base isolation of nuclear reactor plants. The goal of the test program is to determine the performance characteristics of laminated seismic isolation bearings under a wide range of loadings. Tests were performed on scale-size laminated seismic isolators both within the design shear strain range to determine the response of the bearing under expected earthquake loading conditions, and beyond the design range to determine failure modes and to establish safety margins. Three types of bearings, each produced from a different manufacturer, have been tested: (1) high shape factor-high damping-high shear modulus bearings; (2) medium shape factor-high damping-high shear modulus bearings; and (3) medium shape factor-high damping-low shear modulus bearings. All of these tests described in this report were performed at the Earthquake Engineering Research Center at the University of California, Berkeley, with technical assistance from ANL. The tests performed on the three types of bearings have confirmed the high performance characteristics of the high damping-high and low shear modulus elastomeric bearings. The bearings have shown that they are capable of having extremely large shear strains before failure occurs. The most common failure mechanism was the debonding of the top steel plate from the isolators. This failure mechanism can be virtually eliminated by improved manufacturing quality control. The most important result of the failure test of the isolators is the fact that bearings can sustain large horizontal displacement, several times larger than the design value, with failure. Their performance in moderate and strong earthquakes will be far superior to conventional structures

  19. State of the art of computer codes and experimental investigations on safety of nuclear power plants with reactors of WWER type

    International Nuclear Information System (INIS)

    Asmolov, V.G.; Volkov, G.A.; Elikin, I.V.; Mysenkov, A.I.

    1987-01-01

    As is well-known investigations on mathematical models of accidental situations from the point of view of nuclear safety as well as their experimental investigation are of great importance in the design of reactor units for nuclear power plants. This paper gives a review of the state of the art of thermodynamic models and computer codes used for safety analysis of WWER reactors in the USSR, the experimental basis and experimental investigations of the appropriate thermal processes. The actual and future trends of theoretical and experimental investigation on safety problems of WWER type nuclear power plants are briefly described. (author)

  20. An experimental study on the effect of TV commercials on the attitudes towards nuclear power generation

    Energy Technology Data Exchange (ETDEWEB)

    Tada, Yasuyuki [Institute of Nuclear Safety System Inc., Seika, Kyoto (Japan)

    1999-09-01

    The present study is about the effect TV commercials have on the subjects' attitudes towards nuclear power generation. A number of 191 female students participated in the experiment. It was hypothesized that TV commercials would have a positive effect on the viewer's attitude towards nuclear power generation. The main results of the study supported this hypothesis, demonstrating that TV commercials constitute an effective means for changing people's perception of nuclear power generation. (author)

  1. An experimental study on the effect of TV commercials on the attitudes towards nuclear power generation

    International Nuclear Information System (INIS)

    Tada, Yasuyuki

    1999-01-01

    The present study is about the effect TV commercials have on the subjects' attitudes towards nuclear power generation. A number of 191 female students participated in the experiment. It was hypothesized that TV commercials would have a positive effect on the viewer's attitude towards nuclear power generation. The main results of the study supported this hypothesis, demonstrating that TV commercials constitute an effective means for changing people's perception of nuclear power generation. (author)

  2. Some experimental justifications of constructions of nuclear reactors with the use of solid coolant

    International Nuclear Information System (INIS)

    Deniskin, V.; Nalivaev, V.; Fedik, I.; Vishnevski, U.; Dmitriev, A.

    2003-01-01

    Full text: The work that has been conducted so far justifies a possibility of constructing a reactor with a non-traditional coolant to develop radically new reactors and their cycles with perfect architecture. A solid coolant, for example, the carbon-based one, allows to design the primary circuit of nuclear reactor without excess pressure. Such coolant withstands temperatures up to ∼4000 deg. K without a collapse. The analysis of theory and experiments produced requirements to be met by a solid coolant used in the primary circuit of nuclear reactor. One of the most important requirements is the arrangements for a continuous and homogeneous gravity flow of the coolant through all core sections taking into account the dust caused by wear and some amount of fractured particles. Therefore, the idea is that the mass of particles should resemble a liquid to a certain extend. The particles should be sphere like with average diameter from 0.5 to 2.0 mm and nonsphericity rate not more than 10%. 'Angle of repose' of particles to the horizon can be utilised as a validity criterion of particles which should not exceed 25 deg. The heat transfer coefficient should be increased up to the practical maximum value. In 1996 - 1997 the system of experimental facilities were built in the Scientific and Research Institute 'Luch' to prove the possibility to reliably cool a nuclear reactor with a flow of solid particles and to obtain a minimum set of data for the conceptual design of such reactor with solid coolant. The facility allows the research of the flow stability, heat mass transfer in the core, lifetime wearing of particles of the solid coolant. In 1994-1999 5 batches of particles of different size were fabricated in accordance to different technologies. Four batches were graphite-based and one was aluminium oxide-based (Al 2 O 3 ). The purpose was to verify how the heat transfer coefficient was changing as the particle size varied. The average diameter of graphite particles

  3. Lysosomal processing of sialoglycoconjugates in a wheat germ agglutinin resistant variant of EL4 murine leukemia cells

    International Nuclear Information System (INIS)

    Devino, N.L.

    1989-01-01

    Metabolic studies were undertaken in EL4 murine leukemia in WB6, a wheat germ agglutinin-resistant variant of EL4, in order to identify any differences in lysosomal processing of sialoglyco-conjugates. Five lysosomal acid hydrolases, acetylesterase, acid phosphatase, β-galactosidase, α-mannosidase, and neuraminidase, were studied using fluorescent 4-methylumbelliferyl substrates. No significant differences were found in the total activity of any of these enzymes in EL4 and WB6. Cells were incubated in the presence of N-acetylmannosamine, the metabolic precursor of sialic acid (N-acetylneuraminic acid). Free sialic acid accumulated in the lysosomes of WB6 but not of EL4. The accumulation of lysosomal free sialic acid in WB6 showed a dependence on the concentration of N-acetylmannosamine in the growth medium. Metabolic labelling with [6- 3 H]-N-acetylmannosamine showed that WB6 accumulated lysosomal free sialic acid even at very low concentrations of N-acetylmannosamine. The two cell lines differed in their distribution of radiolabelled neutral sugars, free sialic acid, and sialoglycoproteins. The velocity of 3 H-sialic acid release was 3.7-fold lower in WB6 than in EL4, suggesting that WB6 has a defect in lysosomal sialic acid transport. The metabolic consequences of this defect are examined, in light of other biochemical and immunological data on these cells

  4. Determining of the nuclear composition of primary cosmic rays from the experimental distributions of multiple muons in atmospheric showers

    International Nuclear Information System (INIS)

    Beshtoev, Kh.M.

    1993-01-01

    Various approaches are discussed for determining the nuclear composition of the primary cosmic radiation from the distributions of multiple muons. Results are presented of calculations of the distributions of multiple muons for A 1 , A 4 , A 14 , A 26 , A 56 nuclei for an infinite plane and for the underground scintillation telescope of the Institute for Nuclear Research of the Academy of Sciences of Russia.The most suitable technique for determination of the primary nuclear composition of cosmic rays from the distribution of multiple muons is shown to be the approximate solution of a set of N equations, in which the respective coefficients of the contributions of various nuclei A i (i=1-N) to the primary composition serve as variables, while the remaining parts of these equations are the distributions of multiple muons obtained experimentally. 7 refs.; 2 tabs

  5. CFD analysis and experimental investigation associated with the design of the Los Alamos nuclear materials storage facility

    International Nuclear Information System (INIS)

    Bernardin, J.D.; Hopkins, S.; Gregory, W.S.; Martin, R.A.

    1997-01-01

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory is being renovated for long-term storage of canisters designed to hold heat-generating nuclear materials, such as powders, ingots, and other components. The continual heat generation within the canisters necessitates a reliable cooling scheme of sufficient magnitude which maintains the stored material temperatures within acceptable limits. The primary goal of this study was to develop both an experimental facility and a computational fluid dynamics (CFD) model of a subsection of the NMSF which could be used to observe general performance trends of a proposed passive cooling scheme and serve as a design tool for canister holding fixtures. Comparisons of numerical temperature and velocity predictions with empirical data indicate that the CFD model provides an accurate representation of the NMSF experimental facility. Minor modifications in the model geometry and boundary conditions are needed to enhance its accuracy, however, the various fluid and thermal models correctly capture the basic physics

  6. Comparisons of experimental beta-ray spectra important to decay heat predictions with ENSDF [Evaluated Nuclear Structure Data File] evaluations

    International Nuclear Information System (INIS)

    Dickens, J.K.

    1990-03-01

    Graphical comparisons of recently obtained experimental beta-ray spectra with predicted beta-ray spectra based on the Evaluated Nuclear Structure Data File are exhibited for 77 fission products having masses 79--99 and 130--146 and lifetimes between 0.17 and 23650 sec. The comparisons range from very poor to excellent. For beta decay of 47 nuclides, estimates are made of ground-state transition intensities. For 14 cases the value in ENSDF gives results in very good agreement with the experimental data. 12 refs., 77 figs., 1 tab

  7. Experimental studies on optimal process of the iodine-sulfur cycle for nuclear hydrogen production

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Ho Joon

    2010-02-15

    For nuclear hydrogen production, we selected Iodine-Sulfur (I-S) cycle as the most promising one by screening process among 115 thermo-chemical water splitting technologies. We developed a thermo-physical model for the hydrogen-iodide (HI) VLE and decomposition behavior in the iodine-sulfur (IS) cycle to improve the conventional I-S cycle suggested by GA. Neumann's modified NRTL model was improved by correcting an unphysical assumption for the non-randomness parameter, and using the two-step equilibrium approach for the HI decomposition modeling. However, the parameters of the model were decided through regression with the 271 sets of existing experimental data: the accuracy of the model should be improved by more experimental data over all operating ranges, especially, in the high temperature and high pressure regions. To obtain the data of those regions, an autoclave for high temperature and high pressure was designed and manufactured. Various materials and surface coating technologies were investigated for preventing corrosion from acids. However, we have currently failed to overcome the corrosion problems with highly corrosive acids at a high temperature and high pressure. We experimentally validated that azeotropic constraint between acid and H{sub 2}O undermined the total efficiency of the I-S cycle. As mentioned above, the conventional I-S cycle suffers from low thermal efficiency and highly corrosive streams. To alleviate these problems, we have proposed the optimal operating conditions for the Bunsen reaction and devised a new KAIST flowsheet that produces highly enriched HI through spontaneous L-L phase separation and simple flash processes under low pressure. A series of phase separation experiments were performed to validate the new flowsheet and extend its feasibility. When the molar ratio of I{sub 2}/H{sub 2}SO{sub 4} in the feed increased from 2 to 4, the molar ratio of HI/(HI+H{sub 2}O) in the HI{sub x} phase improved from 0.157 to 0.22, which

  8. Experimental studies on optimal process of the iodine-sulfur cycle for nuclear hydrogen production

    International Nuclear Information System (INIS)

    Yoon, Ho Joon

    2010-02-01

    For nuclear hydrogen production, we selected Iodine-Sulfur (I-S) cycle as the most promising one by screening process among 115 thermo-chemical water splitting technologies. We developed a thermo-physical model for the hydrogen-iodide (HI) VLE and decomposition behavior in the iodine-sulfur (IS) cycle to improve the conventional I-S cycle suggested by GA. Neumann's modified NRTL model was improved by correcting an unphysical assumption for the non-randomness parameter, and using the two-step equilibrium approach for the HI decomposition modeling. However, the parameters of the model were decided through regression with the 271 sets of existing experimental data: the accuracy of the model should be improved by more experimental data over all operating ranges, especially, in the high temperature and high pressure regions. To obtain the data of those regions, an autoclave for high temperature and high pressure was designed and manufactured. Various materials and surface coating technologies were investigated for preventing corrosion from acids. However, we have currently failed to overcome the corrosion problems with highly corrosive acids at a high temperature and high pressure. We experimentally validated that azeotropic constraint between acid and H 2 O undermined the total efficiency of the I-S cycle. As mentioned above, the conventional I-S cycle suffers from low thermal efficiency and highly corrosive streams. To alleviate these problems, we have proposed the optimal operating conditions for the Bunsen reaction and devised a new KAIST flowsheet that produces highly enriched HI through spontaneous L-L phase separation and simple flash processes under low pressure. A series of phase separation experiments were performed to validate the new flowsheet and extend its feasibility. When the molar ratio of I 2 /H 2 SO 4 in the feed increased from 2 to 4, the molar ratio of HI/(HI+H 2 O) in the HI x phase improved from 0.157 to 0.22, which is high enough to generate

  9. Proposal and experimental validation of analytical models for seismic and vibration isolation devices in nuclear and non-nuclear facilities

    International Nuclear Information System (INIS)

    Serino, G.; Bonacina, G.; Bettinali, F.

    1993-01-01

    Two analytical-experimental models of HDLRBs having different levels of approximations are presented. Comparison with available experimental data shows that a non-linear hysteretic model, defined by three rubber parameters only, allows a very good complete simulation of the dynamic behavior of the isolation devices. A simpler equivalent linear viscous model reproduces less exactly the experimental behavior, but permits a good prediction of peak response values in the earthquake analysis of an isolated structure, if bearing stiffness and damping parameters are properly selected. The models have been used in preliminary design and subsequent check of the isolation system of two different types of Gas-Insulated Electric Substations (GIS), in view of possible future installation of isolated GISes in areas of high seismic risk. (author)

  10. Construction of an experimental simplified model for determining of flow parameters in chemical reactors, using nuclear techniques

    International Nuclear Information System (INIS)

    Araujo Paiva, J.A. de.

    1981-03-01

    The development of a simplified experimental model for investigation of nuclear techniques to determine the solid phase parameters in gas-solid flows is presented. A method for the measurement of the solid phase residence time inside a chemical reactor of the type utilised in the cracking process of catalytic fluids is described. An appropriate radioactive labelling technique of the solid phase and the construction of an eletronic timing circuit were the principal stages in the definition of measurement technique. (Author) [pt

  11. B7-2 Expressed on EL4 Lymphoma Suppresses Antitumor Immunity by an Interleukin 4–dependent Mechanism

    OpenAIRE

    Stremmel, C.; Greenfield, E.A.; Howard, E.; Freeman, G.J.; Kuchroo, V.K.

    1999-01-01

    For T cells to become functionally activated they require at least two signals. The B7 costimulatory molecules B7-1 and B7-2 provide the “second signal” pivotal for T cell activation. In this report, we studied the relative roles of B7-1 and B7-2 molecules in the induction of antitumor immunity to the T cell thymoma, EL4. We generated EL4 tumor cells that expressed B7-1, B7-2, and B7-1+B7-2 by transfecting murine cDNAs. Our results demonstrate that EL4–B7-1 cells are completely rejected in sy...

  12. NUCLEAR HEATING IN LIF DOSEMETERS IN A FUSION NEUTRON FIELD, TRIAL OF DIRECT COMPARISON OF EXPERIMENTAL AND SIMULATED RESULTS.

    Science.gov (United States)

    Pohorecki, Wladyslaw; Obryk, Barbara

    2017-09-29

    The results of nuclear heating measured by means of thermoluminescent dosemeters (TLD-LiF) in a Cu block irradiated by 14 MeV neutrons are presented. The integral Cu experiment relevant for verification of copper nuclear data at neutron energies characteristic for fusion facilities was performed in the ENEA FNG Laboratory at Frascati. Five types of TLDs were used: highly photon sensitive LiF:Mg,Cu,P (MCP-N), 7LiF:Mg,Cu,P (MCP-7) and standard, lower sensitivity LiF:Mg,Ti (MTS-N), 7LiF:Mg,Ti (MTS-7) and 6LiF:Mg,Ti (MTS-6). Calibration of the detectors was performed with gamma rays in terms of air-kerma (10 mGy of 137Cs air-kerma). Nuclear heating in the Cu block was also calculated with the use of MCNP transport code Nuclear heating in Cu and air in TLD's positions was calculated as well. The nuclear heating contribution from all simulated by MCNP6 code particles including protons, deuterons, alphas tritons and heavier ions produced by the neutron interactions were calculated. A trial of the direct comparison between experimental results and results of simulation was performed. © The Author 2017. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  13. Experimental and theoretical studies of nuclear generation of ozone and its photolysis into singlet delta oxygen

    International Nuclear Information System (INIS)

    Elsayed-Ali, H.E.

    1985-01-01

    A series of measurements of O 3 yield in nuclear induced O 2 and O 2 -SF 6 discharges created by bombardment with energetic particles from the 10 B(n,α) 7 Li reaction are reported. Continuous irradiation at dose ratios of 10 15 -10 17 eV.cm -3 .s -1 and pulsed irradiation (approx.10 ms FWHM) at a peak dose rate of approx.10 20 eV.cm -3 .s -1 were conducted. At the lower dose rates, SF 6 addition generally increased the ozone yield, which at the high dose rates, SF 6 addition decreased the observed ozone concentration. A numerical model was developed and applied to experimental conditions. The steady-state ozone concentration was found to be limited by the reaction O 3 - + O 3 → 2O 2 + O 2 - . A simplified analytical model of steady-state conditions was used to predict model sensitivity to various parameters. In addition to dose rate effects, pressure and temperature effect on ozone production were discussed. The present study was extended to noble gas (He, Ne, and Ar)-O 2 and noble gas - O 2 -SF 6 mixtures. Without SF 6 , steady-state ozone concentrations were found to be about an order of magnitude lower than that observed for oxygen at similar dose rates. Addition of SF 6 was found to significantly increase the steady-state ozone concentration (3-6 times) in noble gas-O 2 mixtures. The developed models were amended to study noble gas-O 2 discharges. A detailed computer model of ultraviolet irradiation of O 3 -O 2 -noble gas mixtures was presented. Dependence of O 2 (a 1 Δ/sub g/) yield on various parameters was investigated. Conditions needed to create O 2 (a 1 Δ/sub g/) concentrations sufficient for pumping an atomic iodine laser were identified. The model was tested by applying it to date on quantum yield of ozone decomposition for various mixtures and by observation of the absolute O 2 (a 1 Δ/sub g/) concentration generated under various conditions

  14. Specific anti-EL4-lymphoma immunity in mice cured 2 years earlier with doxorubicin and interleukin-2.

    Science.gov (United States)

    Ehrke, M J; Verstovsek, S; Zaleskis, G; Ho, R L; Ujházy, P; Maccubbin, D L; Mihich, E

    1996-05-01

    This laboratory has reported the conditions for an effective, non-toxic, chemoimmunotherapy utilizing doxorubicin in combination with prolonged administration of interleukin-2 and the identification of the critical role of activated CD8+ T cells in the therapeutic effect. Mice (C57BL/6) cured in those studies have been followed for the remainder of their life spans. These mice, approximately 2 months of age when initially inoculated with syngeneic EL4 lymphoma, survived for more than 2 years, the normal life span of C57BL/6 mice. Mice 4 months old reinoculated with the EL4 cells all survived. At about 1 year of age mice were sacrificed and the ability of their thymocytes and splenocytes to develop specific CD8+ anti-EL4 activity was as high as it had been at the time of tumor rejection. At about 2 years of age EL4 was reimplanted into mice; all of them survived. These surviving mice, at 2 years 2 months of age, as well as a group of 2-year-old mice not rechallenged, were killed and functional antitumor activity and phenotype characteristics of various lymphocyte populations were determined in comparison to those of young and age-matched control mice. The phenotyping of the lymphocytes from the cured mice indicated very notable differences in subset distribution and increased CD44 expression. Functionally they developed high levels of anti-EL4 activity, which was ablated by combined treatment with monoclonal antibodies against CD8 and CD44, indicating the role of memory cells. Consistent with cells from aged mice, these same cell populations had a very reduced allogeneic responsiveness. It appears that cured mice have developed an immune memory specific for EL4.

  15. Phorbol esters induce interleukin 2 mRNA in sensitive but not in resistant EL4 cells

    International Nuclear Information System (INIS)

    Harrison, J.R.; Lynch, K.R.; Sando, J.J.

    1986-01-01

    Phorbol ester (PE) sensitive EL4 cells are growth-inhibited and produce interleukin 2 (IL2) when treated with PE. Resistant EL4 cells lack both responses. To determine whether the defect in resistant cells occurs pre or post-transcriptionally, an assay for IL2 mRNA was developed using a synthetic oligonucleotide to mouse IL2 as a probe. Total RNA (15 μg) from cells +/- PE was electrophoresed, blotted onto a cationic nylon membrane, and probed with radiolabeled oligomer. This probe hybridized to a 1.1 kb band in RNA from PE-treated sensitive cells. This RNA was detectable within 3h of PE administration, was clearly visible by 6h, and peaked by 9 to 12h. No bands hybridizing with the IL2 probe were detected in RNA isolated from unstimulated cells or from resistant EL4 cells at any time following PE stimulation. Since levels of the protooncogene c-myc have been shown to decrease in a number of cell lines during differentiation and growth inhibition, total RNA from EL4 cells was probed with a nick-translated plasmid containing the protein coding region of the c-myc gene. In PE sensitive cells, levels of c-myc RNA are markedly reduced by 3h. In a pilot experiment with resistant cells, c-myc levels appeared to remain constant. These results demonstrate that PE induced IL2 mRNA in PE sensitive but not resistant EL4 cells. Sensitive and resistant EL4 cell lines provide a useful model for the investigation of the regulation of gene expression by PE

  16. Effect of RNAi p21 gene on uncoupling of EL-4 cells induced by X-irradiation

    International Nuclear Information System (INIS)

    Ju Guizhi; Yan Fengqin; Fu Shibo; Shen Bo; Sun Shilong; Yang Ying; Li Pengwu

    2008-01-01

    Objective: To investigate the effect of RNAi p21 gene on uncoupling of EL-4 cells induced by X-irradiation. Methods: Construction of RNAi p21 plasmid of pSileneer3.1-H1 neo-p21 was performed. Lipofectamine transfection assay was used to transfer the p21siBNA into EL-4 cells. Fluorescent staining and flow cytometry (FCM) analysis were employed for measurement of protein expression. Fluorescent staining of propidium iodide (PI) and FCM were used for measurement of potyploid cells. Results: In dose-effect experiment it was found that the expression of P21 protein of EL-4 cells increased significantly 24 h after X- irradiation with different doses compared with sham-inadiated control. In time course experiment it was found that the expression of P21 protein of EL-4 cells increased significantly at 8 h to 72 h after 4.0 Gy X-irradiation compared with sham-irradiated control. The results showed that the number of polyploid cells in EL-4 cells was not changed markedly after X-irradiation with doses of 0.5-6.0 Gy. After RNA interference with p21 gene, the expression of P21 protein of EL-4 cells decreased significantly 24 h and 48 h after 4.0 Gy X-irradiation in transfection of plasmid of pSilencer3.1-H1 neo-p21 compared with transfection of plasmid of pSilencer3.1-H1 nco control. And at the same time, the number of polyploid cells in EL-4 cells was increased significantly in transfection of plasmid of pSilencer3.1-H1 neo-p21 compared with transfection of plasmid of pSilencer3.1-H1 nco control. Conclusions: Uncoupling could be induced by X-irradiation in EL-4 cells following BNAi p21 gene, suggesting that P21 protein may play an important role in uncoupling induced by X-rays. (authors)

  17. Applications of a superconducting solenoidal separator in the experimental investigation of nuclear reactions

    International Nuclear Information System (INIS)

    Hinde, D J; Carter, I P; Dasgupta, M; Simpson, E C; Cook, K J; Kalkal, Sunil; Luong, D H; Williams, E

    2017-01-01

    This paper describes applications of a novel superconducting solenoidal separator, with magnetic fields up to 8 Tesla, for studies of nuclear reactions using the Heavy Ion Accelerator Facility at the Australian National University. (paper)

  18. An analytical and experimental study of the behaviour of redundant controllers applied to a nuclear plant

    International Nuclear Information System (INIS)

    Lawrence, L.A.J.

    1964-02-01

    The behaviour of a number of configurations of redundant controllers is examined and the design problems discussed in relation to the engineering of reliable control rod drive systems for nuclear plant. (author)

  19. Experimental determination of fuel surface temperature in the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Khang, Ngo Phu; Huy, Ngo Quang; An, Tran Khac; Lam, Pham Van [Nuclear Research Inst., Da Lat (Viet Nam)

    1994-10-01

    Measured fuel surface temperatures, obtained at various locations of the core of the Dalat Nuclear Research Reactor under normal operating conditions, are presented, and some thermal characteristics of the reactor are discussed. (author). 2 refs., 11 figs., 2 tabs.

  20. The French experimentation at the underground nuclear testing site in the Sahara desert

    Energy Technology Data Exchange (ETDEWEB)

    Gauvenet, Andre [Commissariat a l' Energie Atomique (France)

    1970-05-01

    The present paper will be essentially an introduction to the technical exposes which will be delivered during the Las Vegas Meeting. The presentation is divided in two parts. The first part summarizes very briefly the experience that has been gained from the underground nuclear shots which took place in the Sahara desert from 1961 to 1966. in the second part, an idea is given of the studies at present carried on in France in the domain of peaceful applications of nuclear explosions.

  1. Analysis of nuclear material flow for experimental DUPIC fuel fabrication process at DFDF

    International Nuclear Information System (INIS)

    Lee, H. H.; Park, J. J.; Shin, J. M.; Lee, J. W.; Yang, M. S.; Baik, S. Y.; Lee, E. P.

    1999-08-01

    This report describes facilities necessary for manufacturing experiment for DUPIC fuel, manufacturing process and equipment. Nuclear material flows among facilities, in PIEF and IMEF, for irradiation test, for post examination of DUPIC fuel, for quality control, for chemical analysis and for treatment of radioactive waste have been analyzed in details. This may be helpful for DUPIC project participants and facility engineers working in related facilities to understand overall flow for nuclear material and radioactive waste. (Author). 14 refs., 15 tabs., 41 figs

  2. Experimental cross-sections for proton-induced nuclear reactions on Mo-nat

    Czech Academy of Sciences Publication Activity Database

    Červenák, Jaroslav; Lebeda, Ondřej

    2016-01-01

    Roč. 380, AUG (2016), s. 32-49 ISSN 0168-583X R&D Projects: GA MŠk(CZ) LM2011019 Institutional support: RVO:61389005 Keywords : cross-sections * excitation functions * proton-induced nuclear reactions * natural molybdenum * Mo-99 * Tc-99m * Tc96m+g * Tc-95m * thick target yields * U-120M cyclotron Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 1.109, year: 2016

  3. Analysis of nuclear material flow for experimental DUPIC fuel fabrication process at DFDF

    Energy Technology Data Exchange (ETDEWEB)

    Lee, H. H.; Park, J. J.; Shin, J. M.; Lee, J. W.; Yang, M. S.; Baik, S. Y.; Lee, E. P

    1999-08-01

    This report describes facilities necessary for manufacturing experiment for DUPIC fuel, manufacturing process and equipment. Nuclear material flows among facilities, in PIEF and IMEF, for irradiation test, for post examination of DUPIC fuel, for quality control, for chemical analysis and for treatment of radioactive waste have been analyzed in details. This may be helpful for DUPIC project participants and facility engineers working in related facilities to understand overall flow for nuclear material and radioactive waste. (Author). 14 refs., 15 tabs., 41 figs.

  4. The French experimentation at the underground nuclear testing site in the Sahara desert

    International Nuclear Information System (INIS)

    Gauvenet, Andre

    1970-01-01

    The present paper will be essentially an introduction to the technical exposes which will be delivered during the Las Vegas Meeting. The presentation is divided in two parts. The first part summarizes very briefly the experience that has been gained from the underground nuclear shots which took place in the Sahara desert from 1961 to 1966. in the second part, an idea is given of the studies at present carried on in France in the domain of peaceful applications of nuclear explosions

  5. Theoretical and experimental study of the dark signal in CMOS image sensors affected by neutron radiation from a nuclear reactor

    Science.gov (United States)

    Xue, Yuanyuan; Wang, Zujun; He, Baoping; Yao, Zhibin; Liu, Minbo; Ma, Wuying; Sheng, Jiangkun; Dong, Guantao; Jin, Junshan

    2017-12-01

    The CMOS image sensors (CISs) are irradiated with neutron from a nuclear reactor. The dark signal in CISs affected by neutron radiation is studied theoretically and experimentally. The Primary knock-on atoms (PKA) energy spectra for 1 MeV incident neutrons are simulated by Geant4. And the theoretical models for the mean dark signal, dark signal non-uniformity (DSNU) and dark signal distribution versus neutron fluence are established. The results are found to be in good agreement with the experimental outputs. Finally, the dark signal in the CISs under the different neutron fluence conditions is estimated. This study provides the theoretical and experimental evidence for the displacement damage effects on the dark signal CISs.

  6. Kinetics of apoptotic markers in exogeneously induced apoptosis of EL4 cells.

    Science.gov (United States)

    Jessel, Robert; Haertel, Steffen; Socaciu, Carmen; Tykhonova, Svetlana; Diehl, Horst A

    2002-01-01

    We investigated the time-dependence of apoptotic events in EL4 cells by monitoring plasma membrane changes in correlation to DNA fragmentation and cell shrinkage. We applied three apoptosis inducers (staurosporine, tubericidine and X-rays) and we looked at various markers to follow the early-to-late apoptotic events: phospholipid translocation (identified through annexin V-fluorescein assay and propidium iodide), lipid package (via merocyanine assay), membrane fluidity and anisotropy (via fluorescent measurements), DNA fragmentation by the fluorescence-labeling test and cell size measurements. The different apoptotic inducers caused different reactions of the cells: staurosporine induced apoptosis most rapidly in a high number of cells, tubercidine triggered apoptosis only in the S phase cells, while X-rays caused a G2/M arrest and subsequently apoptosis. Loss of lipid asymmetry is promptly detectable after one hour of incubation time. The phosphatidylserine translocation, decrease of lipid package and anisotropy, and the increase of membrane fluidity appeared to be based on the same process of lipid asymmetry loss. Therefore, the DNA fragmentation and the cell shrinkage appear to be parallel and independent processes running on different time scales but which are kinetically inter-related. The results indicate different signal steps to apoptosis dependent on inducer characteristics but the kinetics of "early-to-late" apoptosis appears to be a fixed program.

  7. Autophagy contributes to apoptosis in A20 and EL4 lymphoma cells treated with fluvastatin.

    Science.gov (United States)

    Qi, Xu-Feng; Kim, Dong-Heui; Lee, Kyu-Jae; Kim, Cheol-Su; Song, Soon-Bong; Cai, Dong-Qing; Kim, Soo-Ki

    2013-11-08

    Convincing evidence indicates that statins stimulate apoptotic cell death in several types of proliferating tumor cells in a cholesterol-lowering-independent manner. However, the relationship between apoptosis and autophagy in lymphoma cells exposed to statins remains unclear. The objective of this study was to elucidate the potential involvement of autophagy in fluvastatin-induced cell death of lymphoma cells. We found that fluvastatin treatment enhanced the activation of pro-apoptotic members such as caspase-3 and Bax, but suppressed the activation of anti-apoptotic molecule Bcl-2 in lymphoma cells including A20 and EL4 cells. The process was accompanied by increases in numbers of annexin V alone or annexin V/PI double positive cells. Furthermore, both autophagosomes and increases in levels of LC3-II were also observed in fluvastatin-treated lymphoma cells. However, apoptosis in fluvastatin-treated lymphoma cells could be blocked by the addition of 3-methyladenine (3-MA), the specific inhibitor of autophagy. Fluvastatin-induced activation of caspase-3, DNA fragmentation, and activation of LC3-II were blocked by metabolic products of the HMG-CoA reductase reaction, such as mevalonate, farnesyl pyrophosphate (FPP) and geranylgeranyl pyrophosphate (GGPP). These results suggest that autophagy contributes to fluvastatin-induced apoptosis in lymphoma cells, and that these regulating processes require inhibition of metabolic products of the HMG-CoA reductase reaction including mevalonate, FPP and GGPP.

  8. Advancing Explosion Source Theory through Experimentation: Results from Seismic Experiments Since the Moratorium on Nuclear Testing

    Science.gov (United States)

    Bonner, J. L.; Stump, B. W.

    2011-12-01

    On 23 September 1992, the United States conducted the nuclear explosion DIVIDER at the Nevada Test Site (NTS). It would become the last US nuclear test when a moratorium ended testing the following month. Many of the theoretical explosion seismic models used today were developed from observations of hundreds of nuclear tests at NTS and around the world. Since the moratorium, researchers have turned to chemical explosions as a possible surrogate for continued nuclear explosion research. This talk reviews experiments since the moratorium that have used chemical explosions to advance explosion source models. The 1993 Non-Proliferation Experiment examined single-point, fully contained chemical-nuclear equivalence by detonating over a kiloton of chemical explosive at NTS in close proximity to previous nuclear explosion tests. When compared with data from these nearby nuclear explosions, the regional and near-source seismic data were found to be essentially identical after accounting for different yield scaling factors for chemical and nuclear explosions. The relationship between contained chemical explosions and large production mining shots was studied at the Black Thunder coal mine in Wyoming in 1995. The research led to an improved source model for delay-fired mining explosions and a better understanding of mining explosion detection by the International Monitoring System (IMS). The effect of depth was examined in a 1997 Kazakhstan Depth of Burial experiment. Researchers used local and regional seismic observations to conclude that the dominant mechanism for enhanced regional shear waves was local Rg scattering. Travel-time calibration for the IMS was the focus of the 1999 Dead Sea Experiment where a 10-ton shot was recorded as far away as 5000 km. The Arizona Source Phenomenology Experiments provided a comparison of fully- and partially-contained chemical shots with mining explosions, thus quantifying the reduction in seismic amplitudes associated with partial

  9. Numerical and experimental study of hydraulic dashpot used in the shut-off rod drive mechanism of a nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Narendra K., E-mail: nksingh_chikki@yahoo.com [Division of Remote Handling and Robotics, Bhabha Atomic Research Centre, Mumbai 400085 (India); Badodkar, Deepak N. [Division of Remote Handling and Robotics, Bhabha Atomic Research Centre, Mumbai 400085 (India); Homi Bhabha National Institute, Anushaktinagar, Mumbai 400094 (India); Singh, Manjit [Division of Remote Handling and Robotics, Bhabha Atomic Research Centre, Mumbai 400085 (India)

    2014-07-01

    Highlights: • Hydraulic dashpot performance is studied numerically as well as experimentally. • Instantaneous pressure built-up in the dashpot is mainly contributing for damping of freely falling shut-off rod at the end of its travel. • At elevated temperature, dashpot pressure does not reduce in proportion to the reduction in viscosity. • ‘C’ grove in the dashpot shaft flattens the pressure peak and shifts it toward the end of operation. - Abstract: Hydraulic dashpot design for shut-off rod drive mechanism application in a nuclear reactor has been analyzed both numerically and experimentally in this paper. Finite element commercial code COMSOL Multiphysics 4.3 has been used for numerical analysis. Experimental validation has been done at two different cases. Experimental test set-ups and hydraulic dashpot constructions have been described in detail. Various combinations of dashpot oil viscosity and clearance thickness have been analyzed. Important experimental results are also presented and discussed. Pressure distributions in the dashpot chambers obtained from COMSOL are given for both the set-ups. Numerical and experimental results are compared. Dashpot designs have been qualified after detailed analysis and testing on full-scale test stations simulating actual reactor conditions (except radiation)

  10. Numerical and experimental study of hydraulic dashpot used in the shut-off rod drive mechanism of a nuclear reactor

    International Nuclear Information System (INIS)

    Singh, Narendra K.; Badodkar, Deepak N.; Singh, Manjit

    2014-01-01

    Highlights: • Hydraulic dashpot performance is studied numerically as well as experimentally. • Instantaneous pressure built-up in the dashpot is mainly contributing for damping of freely falling shut-off rod at the end of its travel. • At elevated temperature, dashpot pressure does not reduce in proportion to the reduction in viscosity. • ‘C’ grove in the dashpot shaft flattens the pressure peak and shifts it toward the end of operation. - Abstract: Hydraulic dashpot design for shut-off rod drive mechanism application in a nuclear reactor has been analyzed both numerically and experimentally in this paper. Finite element commercial code COMSOL Multiphysics 4.3 has been used for numerical analysis. Experimental validation has been done at two different cases. Experimental test set-ups and hydraulic dashpot constructions have been described in detail. Various combinations of dashpot oil viscosity and clearance thickness have been analyzed. Important experimental results are also presented and discussed. Pressure distributions in the dashpot chambers obtained from COMSOL are given for both the set-ups. Numerical and experimental results are compared. Dashpot designs have been qualified after detailed analysis and testing on full-scale test stations simulating actual reactor conditions (except radiation)

  11. Evaluation of the Cytotoxic Effect of the Brittle Star (Ophiocoma Erinaceus) Dichloromethane Extract and Doxorubicin on EL4 Cell Line.

    Science.gov (United States)

    Afzali, Mahbubeh; Baharara, Javad; Nezhad Shahrokhabadi, Khadijeh; Amini, Elaheh

    2017-01-01

    Leukemia is a blood disease that creates from inhibition of differentiation and increased proliferation rate. The nature has been known as a rich source of medically useful substances. High diversity of bioactive molecules, extracted from marine invertebrates, makes them as ideal candidates for cancer research. The study has been done to investigate cytotoxic effects of dichloromethane brittle star extract and doxorubicin on EL4 cancer cells. Blood cancer EL4 cells were cultured and treated at different concentrations of brittle star ( Ophiocoma erinaceus ) dichloromethane extract at 24, 48 and 72 h. Cell toxicity was studied using MTT assay. Cell morphology was examined using an invert microscope. Further, apoptosis was examined using Annexin V-FITC, propodium iodide, DAPI, and Acridine orange/propodium iodide staining. Eventually, the apoptosis pathways were analyzed using measurement of Caspase-3 and -9 activity. The statistical analysis was performed using SPSS, ANOVA software, and Tukey's test. P EL4 proliferation as IC 50 =32 µg/mL. All experiments related to apoptosis analysis confirmed that dichloromethane brittle star extract and doxorubicin have a cytotoxic effect on EL4 cells inIC 50 concentration. The study showed that dichloromethane brittle star extract is as an adjunct to doxorubicin in treatment of leukemia cells.

  12. Proteomic analysis of mouse thymoma EL4 cells treated with bis (tri-n-butyltin)oxide (TBTO)

    NARCIS (Netherlands)

    Osman, A.M.; Kol, S.; Peijnenburg, A.A.C.M.; Blokland, M.H.; Pennings, J.L.A.; Kleinjans, J.C.S.; Loveren, van H.

    2009-01-01

    Here, we report the results of proteomic analysis of the mouse thymoma EL4 cell line exposed to bis(tri-n-butylin)oxide (TBTO), an immunotoxic organotin compound. The objective of the work was to examine whether TBTO affects the expression of proteins in this cell line and to compare the

  13. Phosphorylation of paxillin via the ERK mitogen-activated protein kinase cascade in EL4 thymoma cells.

    Science.gov (United States)

    Ku, H; Meier, K E

    2000-04-14

    Intracellular signals can regulate cell adhesion via several mechanisms in a process referred to as "inside-out" signaling. In phorbol ester-sensitive EL4 thymoma cells, phorbol-12-myristate 13-acetate (PMA) induces activation of extracellular signal-regulated kinase (ERK) mitogen-activated protein kinases and promotes cell adhesion. In this study, clonal EL4 cell lines with varying abilities to activate ERKs in response to PMA were used to examine signaling events occurring downstream of ERK activation. Paxillin, a multifunctional docking protein involved in cell adhesion, was phosphorylated on serine/threonine residues in response to PMA treatment. This response was correlated with the extent and time course of ERK activation. PMA-induced phosphorylation of paxillin was inhibited by compounds that block the ERK activation pathway in EL4 cells, primary murine thymocytes, and primary murine splenocytes. Paxillin was phosphorylated in vitro by purified active ERK2. Two-dimensional electrophoresis revealed that PMA treatment generated a complex pattern of phosphorylated paxillin species in intact cells, some of which were generated by ERK-mediated phosphorylation in vitro. An ERK pathway inhibitor interfered with PMA-induced adhesion of sensitive EL4 cells to substrate. These findings describe a novel inside-out signaling pathway by which the ERK cascade may regulate events involved in adhesion.

  14. Proteomic analysis of mouse thymoma EL4 cells treated with bis(tri-n-butyltin)oxide (TBTO).

    Science.gov (United States)

    Osman, Ahmed M; van Kol, Sandra; Peijnenburg, Ad; Blokland, Marco; Pennings, Jeroen L A; Kleinjans, Jos C S; van Loveren, Henk

    2009-09-01

    Here, we report the results of proteomic analysis of the mouse thymoma EL4 cell line exposed to bis(tri-n-butylin)oxide (TBTO), an immunotoxic organotin compound. The objective of the work was to examine whether TBTO affects the expression of proteins in this cell line and to compare the differentially expressed proteins with the corresponding mRNA expression data. The identified proteins were quantified using a label-free quantitative method based on counting the observed peptides as an index of protein abundance. The calculation of the ratio of peptides obtained from exposed and control samples allowed us to evaluate the effect of TBTO on protein expression and to compare these results to those obtained in gene expression profiling studies. Correlation of some of the differentially expressed proteins and their corresponding mRNAs was observed. The analysis of the protein ratios revealed that 12 proteins were significantly affected. These proteins included cytoskeleton proteins myosin-9, spectrin beta 2 and plectin 8. The first two proteins were down-regulated 3-fold, whereas the third was up-regulated 2-fold. Ras-related Rab1, a GTP binding protein and T-complex protein-1 subunit alpha, a chaperonin, were decreased 2- and 3.6-fold, respectively. The ribosomal S10 and eukaryotic translation factor (eIf4G1), which are involved in protein synthesis, were down-regulated 2.6- and 3.7-fold, respectively. Also, proteins involved in splicing of pre-mRNA and in transcription, splicing factor arginine/serine-rich 2 and chromodomain-helicase-DNA binding protein 4 (Chd4), were decreased 2.6- and 4.5 times, respectively. Nuclear RNA helicase II was reduced 2.8-fold. Finally, prothymosin-alpha (ProTalpha), an essential protein for cell proliferation, and a protein similar to ProTalpha, (with a molecular weight and a pI (3.54) comparable to that of ProTalpha) were also down-regulated 6-and 8-fold, respectively. We propose that the observed down-regulation of the expression

  15. Experimental study of variations in background radiation and the effect on Nuclear Car Wash sensitivity

    International Nuclear Information System (INIS)

    Church, J; Slaughter, D; Norman, E; Asztalos, S; Biltoft, P

    2007-01-01

    Error rates in a cargo screening system such as the Nuclear Car Wash [1-7] depend on the standard deviation of the background radiation count rate. Because the Nuclear Car Wash is an active interrogation technique, the radiation signal for fissile material must be detected above a background count rate consisting of cosmic, ambient, and neutron-activated radiations. It was suggested previously [1,6] that the Corresponding negative repercussions for the sensitivity of the system were shown. Therefore, to assure the most accurate estimation of the variation, experiments have been performed to quantify components of the actual variance in the background count rate, including variations in generator power, irradiation time, and container contents. The background variance is determined by these experiments to be a factor of 2 smaller than values assumed in previous analyses, resulting in substantially improved projections of system performance for the Nuclear Car Wash

  16. On optimization of an experimental system consisting of beam guidance and nuclear detectors

    International Nuclear Information System (INIS)

    Lehr, H.; Hinderer, G.; Maier, K.H.

    1978-02-01

    This report deals with the optimization of the resolution in nuclear physics experiments with a beam of accelerated particles. The complete system consisting of the beam handling, the nuclear reaction, and the particle detection is described with a linear matrix formalism. This allows to give analytic expressions for the linewidth of any physically interesting quantities, like Q-values of scattering angle in the center of mass system, as a function of beam line-, nuclear reaction-, and spectrometer parameters. From this then general prescriptions for optimizing the resolution by matching the beam handling and the detector system are derived. Explicitly treated are the measurements of Q-values and CM-scattering angle with an energy sensitive detector, a time of flight spectrometer, and a magnetic spectrometer. (orig.) [de

  17. Staurosporine, but not Ro 31-8220, induces interleukin 2 production and synergizes with interleukin 1alpha in EL4 thymoma cells.

    Science.gov (United States)

    Mahon, T M; Matthews, J S; O'Neill, L A

    1997-07-01

    Protein kinase C (PKC) has been implicated in interleukin 1 (IL1) signal transduction in a number of cellular systems, either as a key event in IL1 action or as a negative regulator. Here we have examined the effects of two PKC inhibitors, staurosporine and the more selective agent Ro 31-8220, on IL1 responses in the murine thymoma line EL4.NOB-1. A 1 h pulse of staurosporine was found to strongly potentiate the induction of IL2 by IL1alpha in these cells. In contrast, neither a pulse nor prolonged incubation with Ro 31-8220 affected the response to IL1alpha. Both agents blocked the response to PMA, however. A 1 h pulse of staurosporine was also found to induce IL2 production on its own, activate the transcription factor nuclear factor kappaB (NFkappaB) and increase the expression of a NFkappaB-linked reporter gene. It synergized with IL1alpha in all of these responses. Ro 31-8220 was again without effect, although both staurosporine and Ro 31-8220 blocked the activation of NFkappaB by PMA. Finally, staurosporine caused the translocation of PKC-alpha and -epsilon, and to a lesser extent PKC-beta, but not PKC-θ or -zeta, from the cytosol to the membrane, although a similar effect was observed with Ro 31-8220. The results suggest that PKC is not involved in IL1alpha signalling in EL4 cells. Furthermore, the potentiating effect of staurosporine on IL1alpha action does not involve PKC inhibition, and is likely to be at the level of NFkappaB activation.

  18. Sensitivity study of experimental measures for the nuclear liquid-gas phase transition in the statistical multifragmentation model

    Science.gov (United States)

    Lin, W.; Ren, P.; Zheng, H.; Liu, X.; Huang, M.; Wada, R.; Qu, G.

    2018-05-01

    The experimental measures of the multiplicity derivatives—the moment parameters, the bimodal parameter, the fluctuation of maximum fragment charge number (normalized variance of Zmax, or NVZ), the Fisher exponent (τ ), and the Zipf law parameter (ξ )—are examined to search for the liquid-gas phase transition in nuclear multifragmention processes within the framework of the statistical multifragmentation model (SMM). The sensitivities of these measures are studied. All these measures predict a critical signature at or near to the critical point both for the primary and secondary fragments. Among these measures, the total multiplicity derivative and the NVZ provide accurate measures for the critical point from the final cold fragments as well as the primary fragments. The present study will provide a guide for future experiments and analyses in the study of the nuclear liquid-gas phase transition.

  19. Large scale model experimental analysis of concrete containment of nuclear power plant strengthened with externally wrapped carbon fiber sheets

    International Nuclear Information System (INIS)

    Yang Tao; Chen Xiaobing; Yue Qingrui

    2005-01-01

    Concrete containment of Nuclear Power Station is the last shield structure in case of nuclear leakage during an accident. The experiment model in this paper is a 1/10 large-scale model of a real-sized prestressed reinforced concrete containment. The model containment was loaded by hydraulic pressure which simulated the design pressure during the accident. Hundreds of sensors and advanced data-collect systems were used in the test. The containment was first loaded to the damage pressure then strengthened with externally wrapping Carbon fiber sheet around the outer surface of containment structure. Experimental results indicate that CFRP system can greatly increase the capacity of concrete containment to endure the inner pressure. CFRP system can also effectively confine the deformation and the cracks caused by loading. (authors)

  20. The production of nitric oxide in EL4 lymphoma cells overexpressing growth hormone.

    Science.gov (United States)

    Arnold, Robyn E; Weigent, Douglas A

    2003-01-01

    Growth hormone (GH) is produced by immunocompetent cells and has been implicated in the regulation of a multiplicity of functions in the immune system involved in growth and activation. However, the actions of endogenous or lymphocyte GH and its contribution to immune reactivity when compared with those of serum or exogenous GH are still unclear. In the present study, we overexpressed lymphocyte GH in EL4 lymphoma cells, which lack the GH receptor (GHR), to determine the role of endogenous GH in nitric oxide (NO) production and response to genotoxic stress. Western blot analysis demonstrated that the levels of GH increased approximately 40% in cells overexpressing GH (GHo) when compared with cells with vector alone. The results also show a substantial increase in NO production in cells overexpressing GH that could be blocked by N(G)-monomethyl-L-arginine (L-NMMA), an L-arginine analogue that competitively inhibits all three isoforms of nitric oxide synthase (NOS). No evidence was obtained to support an increase in peroxynitrite in cells overexpressing GH. Overexpression of GH increased NOS activity, inducible nitric oxide synthase (iNOS) promoter activity, and iNOS protein expression, whereas endothelial nitric oxide synthase and neuronal nitric oxide synthase protein levels were essentially unchanged. In addition, cells overexpressing GH showed increased arginine transport ability and intracellular arginase activity when compared with control cells. GH overexpression appeared to protect cells from the toxic effects of the DNA alkylating agent methyl methanesulfonate. This possibility was suggested by maintenance of the mitochondrial transmembrane potential in cells overexpressing GH when compared with control cells that could be blocked by L-NMMA. Taken together, the data support the notion that lymphocyte GH, independently of the GH receptor, may play a key role in the survival of lymphocytes exposed to stressful stimuli via the production of NO.

  1. Experimental nuclear physics at Vanderbilt University. Progress report, August, 1983-August, 1984

    International Nuclear Information System (INIS)

    Hamilton, J.H.

    1984-01-01

    Progress summaries are given in the fields of in-beam gamma ray spectroscopy, nuclei far from stability, nuclear reaction mechanism studies, delta-electron spectroscopy, theoretical studies, and other research and activities. Status of the Joint Institute for Heavy Ion Research is reviewed

  2. Experimental Observations of Nuclear Activity in Deuterated Materials Subjected to a Low-Energy Photon Beam

    Science.gov (United States)

    Steinetz, Bruce M.; Benyo, Theresa L.; Pines, Vladimir; Pines, Marianna; Forsley, Lawrence P.; Westmeyer, Paul A.; Chait, Arnon; Becks, Michael D.; Martin, Richard E.; Hendricks, Robert C.; hide

    2017-01-01

    Exposure of highly deuterated materials to a low-energy (nom. 2 MeV) photon beam resulted in nuclear activity of both the parent metals of hafnium and erbium and a witness material (molybdenum) mixed with the reactants. Gamma spectral analysis of all deuterated materials, ErD2.8+C36D74+Mo and HfD2+C36D74+Mo, showed that nuclear processes had occurred as shown by unique gamma signatures. For the deuterated erbium specimens, posttest gamma spectra showed evidence of radioisotopes of erbium ((163)Er and (171)Er) and of molybdenum ((99)Mo and (101)Mo) and by beta decay, technetium (99mTc and 101Tc). For the deuterated hafnium specimens, posttest gamma spectra showed evidence of radioisotopes of hafnium (180mHf and 181Hf) and molybdenum ((99)Mo and (101)Mo), and by beta decay, technetium ((99m)Tc and (101)Tc). In contrast, when either the hydrogenated or non-gas-loaded erbium or hafnium materials were exposed to the gamma flux, the gamma spectra revealed no new isotopes. Neutron activation materials showed evidence of thermal and epithermal neutrons. CR-39 solid-state nuclear track detectors showed evidence of fast neutrons with energies between 1.4 and 2.5 MeV and several instances of triple tracks, indicating (is) greater than 10 MeV neutrons. Further study is required to determine the mechanism causing the nuclear activity.

  3. Hazards Analysis for the Spent Nuclear Fuel L-Experimental Facility

    International Nuclear Information System (INIS)

    Blanchard, A.

    1999-01-01

    The purpose of this Hazard Analysis (HA) is to identify and assess potential hazards associated with the operations of the Spent Nuclear Fuels (SNF) Treatment and Storage Facility LEF. Additionally, this HA will be used for identifying and assessing potential hazards and specifying functional attributes of SSCs for the LEF project

  4. Experimental methods for burn-up determination in nuclear fuels, 1

    International Nuclear Information System (INIS)

    Taddei, J.F. de A.C.; Rodrigues, C.

    1977-01-01

    A method is presented that allows the calculation of the total percentage of atoms having undergone fission ('burn up') in nuclear fuels, from the measurement of absolute amounts of fission product neodymium-148 and of uranium and plutoniun present in the spent fuel, the fission yield of neodymium-148 being known. These measurements are performed through the mass spectrometry- isotope dilution technique [pt

  5. Simulation and Experimental Validation of Electromagnetic Signatures for Monitoring of Nuclear Material Storage Containers

    International Nuclear Information System (INIS)

    Aker, Pamela M.; Bunch, Kyle J.; Jones, Anthony M.

    2013-01-01

    Previous research at the Pacific Northwest National Laboratory (PNNL) has demonstrated that the low frequency electromagnetic (EM) response of a sealed metallic container interrogated with an encircling coil is a strong function of its contents and can be used to form a distinct signature which can confirm the presence of specific components without revealing hidden geometry or classified design information. Finite element simulations have recently been performed to further investigate this response for a variety of configurations composed of an encircling coil and a typical nuclear material storage container. Excellent agreement was obtained between simulated and measured impedance signatures of electrically conducting spheres placed inside an AT-400R nuclear container. Simulations were used to determine the effects of excitation frequency and the geometry of the encircling coil, nuclear container, and internal contents. The results show that it is possible to use electromagnetic models to evaluate the application of the EM signature technique to proposed versions of nuclear weapons containers which can accommodate restrictions imposed by international arms control and treaty verification legislation

  6. Irradiation and contamination owed to nuclear weapons experimentations on the Kazakhstan Semipalatinsk polygon

    International Nuclear Information System (INIS)

    Chenal, C.

    1996-01-01

    Semipalatinsk in Kazakhstan was one of the nuclear weapons polygon for atmospheric, excavation and underground tests. After a description of the actual state of the polygon, a dosimetric approach inside and outside the polygon is presented from 1949 to 1989. (A.B.). 5 refs., 3 figs., 5 tabs

  7. Experimental study on accelerator driven subcritical reactor. JAERI's nuclear research promotion program, H12-031 (Contract research)

    International Nuclear Information System (INIS)

    Shiroya, Seiji; Misawa, Tsuyoshi; Unesaki, Hironobu

    2004-03-01

    In view of the future plan of Research Reactor Institute, Kyoto University (KURRI), the present study consisted of 1) the transmission experiments of high energy neutrons through materials, 2) experimental simulation of ADSR using the Kyoto University Critical Assembly (KUCA), and 3) conceptual neutronics design study on Kyoto University Reactor (KUR) type ADSR using the MCNPX code. The purpose of the present study was not only to obtain the knowledge usable for the realization of ADSR as a new neutron source for research but also to select technical issues in the field of reactor physics for the development of ADSR in general. Through the present study, valuable knowledge on the basic nuclear characteristics of ADSR was obtained both theoretically and experimentally. This kind of knowledge is indispensable to promote the study on ADSR further. If one dare say the main part of knowledge in short words, the basic nuclear characteristics of ADSR is overwhelmed by the characteristics of the subcritical reactor as expected. For the realization of ADSR in the future, it is considered to be necessary to accumulate results of research steadily. For this purpose, it is inevitable 1) to compile the more precise nuclear data for the wide energy range, 2) to establish experimental techniques for reactor physics study on ADSR including subcriticality measurement and absolute neutron flux measurement from the low energy region to the high energy region, and 3) to develop neutronics calculation tools which facilitate to take into account the neutron generation process by the spallation reaction and the delayed neutron behavior. (author)

  8. Selective up-regulation of protein kinase C eta in phorbol ester-sensitive versus -resistant EL4 mouse thymoma cells.

    Science.gov (United States)

    Resnick, M S; Luo, X; Vinton, E G; Sando, J J

    1997-06-01

    Stimulation of sensitive EL4 mouse thymoma cells (s-EL4) with phorbol esters results in production of interleukin 2 (IL-2), adherence to a plastic substrate, and growth inhibition, whereas a phorbol ester-resistant variant (r-EL4) fails to respond. Previous studies revealed substantially decreased expression of protein kinase C (PKC) epsilon in the r-EL4 versus s-EL4 cells. This work has been extended to examine the more recently described PKC isozymes. Western and Northern analyses revealed a marked decrease in PKC eta and theta in r-EL4 as compared to s-EL4 cells. Treatment of these lines with phorbol ester for 24 h resulted in down-regulation of all PKC isozymes examined except PKC eta, which was up-regulated in the s-EL4 cells at the time of maximal IL-2 production. Two newly isolated EL4 clones, resistant to phorbol ester-induced growth inhibition but still exhibiting the phorbol ester-induced adherence and IL-2 production, both expressed PKC eta and theta. Collectively, these observations suggest a dissociation of growth inhibition from adherence and IL-2 production pathways and a potential role for PKC eta in the latter.

  9. Application of electronic paramagnetic, nuclear magnetic, γ-nuclear magnetic resonance, and defibrillation in experimental biology and medecine

    Science.gov (United States)

    Piruzyan, L. A.

    2005-08-01

    Nowadays an attention is paid to pathbreaking approaches to the therapy of different pathologies with EPR, NMR and NGR dialysis and mechanisms of physical factors influence in prophylactics and therapy of a number of diseases. Any pathology is evidently begins its development in atomic-molecular levels earlier then any morphologic alterations in tissues can be detected. We have studied the alterations of FR content in liver, spleen and brain in hypoxia and hyperoxia conditions. Under hypoxia and hyperoxia the FR concentrations are equal in all organs and tissues. However this ratio is different for some forms of leucosis. For different leucosis types gas mixtures the most adequate for the current pathology should be developed. Then we represent the method of biologic objects treatment with the energy of super-high frequency field (SIT) and the instrument for its performance. The study of magnetic heterogeneity of biologic systems proposes the new approach and a set of methods for medical and scientific purpose. Application of combined with chemotherapy extraction of anionic and cationic radicals from bloodstream using EPRD, NMRD and NGRD influence and also the single ions separate extraction using NGRD are able to detect and perhaps to cure their appearance in a period before neoformation. These studies should be carried out experimentally and clinically.

  10. Airborne release fractions/rates and respirable fractions for nonreactor nuclear facilities. Volume 1, Analysis of experimental data

    International Nuclear Information System (INIS)

    1994-12-01

    This handbook contains (1) a systematic compilation of airborne release and respirable fraction experimental data for nonreactor nuclear facilities, (2) assessments of the data, and (3) values derived from assessing the data that may be used in safety analyses when the data are applicable. To assist in consistent and effective use of this information, the handbook provides: identification of a consequence determination methodology in which the information can be used; discussion of the applicability of the information and its general technical limits; identification of specific accident phenomena of interest for which the information is applicable; and examples of use of the consequence determination methodology and airborne release and respirable fraction information

  11. Application of the failure modes and effects analysis technique to the emergency cooling system of an experimental nuclear power plant

    International Nuclear Information System (INIS)

    Conceicao Junior, Osmar; Silva, Antonio Teixeira e

    2009-01-01

    This study consists on the application of the failure modes and effects analysis (FMEA), a hazard identification and a risk assessment technique, to the emergency cooling system (ECS), of an experimental nuclear power plant. The choice of this technique was due to its detailed analysis of each component of the system, enabling the identification of all possible ways of failure and its related consequences (in order of importance), allowing the designer to improve the system, maximizing its security and reliability. Through the application of this methodology, it could be observed that the ECS is an intrinsically safe system, in spite of the modifications proposed. (author)

  12. Application of the failure modes and effects analysis technique to theemergency cooling system of an experimental nuclear power plant

    International Nuclear Information System (INIS)

    Conceicao Junior, Osmar

    2009-01-01

    This study consists on the application of the Failure Modes and EffectsAnalysis (FMEA), a hazard identification and a risk assessment technique, tothe Emergency Cooling System (ECS) of an experimental nuclear power plant,which is responsible for mitigating the consequences of an eventual loss ofcoolant accident on the Pressurized Water Reactor (PWR). Such analysisintends to identify possible weaknesses on the design of the system andpropose some improvements in order to maximize its reliability. To achievethis goal a detailed study of the system was carried on (through itstechnical documentation), the correspondent reliability block diagram wasobtained, the FMEA analysis was executed and, finally, some suggestions werepresented. (author)

  13. Experimental and analytical studies for a BWR nuclear reactor building evaluation of soil-structure interaction behavior

    International Nuclear Information System (INIS)

    Mizuno, N.; Tsushima, Y.

    1975-01-01

    The purpose of this paper is to evaluate the spatial characteristics of dynamic properties, especially soil-structure interaction behavior, or the BWR nuclear reactor building by experimental and analytical studies. An analytical method (SMIRT-1 Paper K 2/4) for estimating the damping effects is reported. The complex damping is used, because the so-called structural damping may be more suitable for estimating the damping effects of an elastic structure. H. Tajimi's theory is used for estimating the dynamical soil-foundation stiffness with the dissipation of vibrational energy on the elastic half-space soil. An approximate explanation is presented in regard to the more developmental mathematical method for estimating the damping effects than the above-mentioned previous method, which is 'Modes Superposition Method for Multi-Degrees of Freedom System' with the constant complex stiffness showing the structural damping effects and the dynamical soil-foundation stiffness approximated by the linear or quadratic functions of the eigenvalues. Next, an approximate explanation is presented in regard to the experimental results of the No.1 reactor building (BWR) of Hamaoka Nuclear Power Station, The Chubu Electric Power Co., Ltd. The regression analyses of the experimental resonance curves by one degree system show that the critical damping ratio is larger than the 0.10 used in the design for the fundamental natural period. It is attempted to simulate the experimental results by the above-mentioned method. The simulated model is a fourty-eight degrees of freedom spring mass system because of the eight masses for the eight floors including the base foundation and the six degrees of freedom for a mass

  14. The experimental reactor Osiris and the nuclear fuel technology for the P.W.R. reactors

    International Nuclear Information System (INIS)

    Lestiboudois, G.; Contenson, G. de; Genthon, J.P.; Molvault, M.; Roche, M.

    1977-01-01

    The possibility of employing research reactors to study and to improve the nuclear fuel of the power reactors is presented. Measurements of temperature, pressure, stresses, thermal balance, gamma spectrometry and neutron radiography, allow the study of fuel densification, the influence of the initial filling pressure on the fission gas release and the gadolinium efficiency evolution. The solutions of the problems of failed element detection, power increase, remote handling, are presented [fr

  15. The role of nuclear emulsions in the institutionalization of research in experimental physics in Brazil

    International Nuclear Information System (INIS)

    Vieira, Cassio Leite; Videira, Antonio A.P.

    2011-01-01

    In this paper, we describe and analyze the introduction and the use of the nuclear emulsions technique in Brazil. Even though consistent researches in cosmic ray physics had been done since the forties of the last century in this country, physicists here only began using this technique after Cesar Lattes' works in Bristol (England) and Berkeley (US). Despite being the implantation of the technique in this country posterior to the origin of the method itself dated from late 1900s, Brazilian scientists were quickly familiarized with it and adopted it not only in cosmic rays, but also in particle physics and nuclear physics, employing it until recently. In our work, we will be concerned with the reasons of this longevity. In other words, why were the nuclear emulsions technique employed for so many years in Brazil, even after its vanishing in physics researches centers in the world? We advance here that the answer to this question involves the institutionalization of science in Brazil mainly physics and economical, social, and geographic reasons. (author)

  16. Experimental and analytical studies for a BWR nuclear reactor building. Evaluation of soil-structure interaction behaviour

    International Nuclear Information System (INIS)

    Mizuno, N.; Tsushima, Y.

    1975-01-01

    This paper evaluates the spatial characteristics of dynamic properties, especially soil-structure interaction behaviour, of the BWR nuclear building by experimental and analytical studies. It is well known that the damping effects in soil-structure interaction are remarkable on the building with short periods by the dissipation of vibrational energy to the soil. The authors have previously reported an analytical method for estimating the damping effects the properties of which are characterized as follows: 1) The complex damping is used, because the so-called structural damping may be more suitable for estimating the damping effects of an elastic structure. 2) H. Tajimi's theory is used for estimating the dynamical soil-foundation stiffness with the dissipation of vibrational energy on the elastic half-space soil. In this paper, an approximate explanation is presented in regard to the more developmental mathematical method for estimating the damping effects than the above-mentioned previous method, which is 'Modes Superposition Method for Multi-Degrees of Freedom System' with the constant complex stiffness showing the structural damping effects and the dynamical soil-foundation stiffness approximated by the linear or quadratic functions of the eigenvalues. An approximate explanation is presented in regard to the experimental results of the No. 1 reactor building (BWR) of Hamaoka Nuclear Power Station, The Chubu Electric Power Co., Ltd. (Auth.)

  17. Experimental evaluation of different mixing promoter for nuclear fuel element by means of a new thermal tracing technique

    International Nuclear Information System (INIS)

    Silin, Nicolas; Juanico, Luis; Delmastro, Dario

    2004-01-01

    In this work a new experimental method is used to experimentally evaluate the performance of different appendages promoting the turbulent mixing between the coupled subchannels of nuclear fuel elements.The method used will be introduced in another presentation and consists in the generation and measurement of small thermal traces in the refrigerating water flow between the fuel rods.Because it is suitable for heterogeneous and compact subchannels (as Argentinean fuels) with high water flows in simple and affordable tests at atmospheric pressure, this new method is specially well suited for the design of fuel elements, while it offers advantages over other methods of mixing measurement.The experiments carried out on a small test section proved that the buttons brazed to the fuel rods (similar to the 'turbulence promoters' of the Canflex fuel) had an excellent thermohydraulic performance as compared to different mixing vane designs studied.The thermal traces method developed has shown its potential as a thermohydraulic design tool for the development of advanced nuclear fuels, that eventually incorporate mixing promoter elements. In the case of CARA, and as it includes spacer grids, it could be possible to use them to incorporate these elements without the need of brazing them to the rods (as is the case in Canflex), and therefore without penalizing its integrity [es

  18. Program for upgrading nuclear materials protection, control, and accounting at all facilities within the All-Russian Institute of Experimental Physics (VNIIEF)

    International Nuclear Information System (INIS)

    Yuferev, V.; Zhikharev, S.; Yakimov, Y.

    1998-01-01

    As part of the Department of Energy-Russian program for strengthening nuclear material protection, control, and accounting (MPC and A), plans have now been formulated to install an integrated MPC and A system at all facilities containing large quantities of weapons-usable nuclear material within the All-Russian Institute of Experimental Physics (VNIIEF, Arzamas-16) complex. In addition to storage facilities, the complex houses a number of critical facilities used to conduct nuclear physics research and facilities for developing procedures for disassembly of nuclear weapons

  19. The fuel element of the first charge for EL 4; presentation, main problems arising in the research, production problems; L'element combustible du 1. jeu de EL 4; presentation, problemes essentiels poses par l'etude, problemes de fabrication

    Energy Technology Data Exchange (ETDEWEB)

    Ringot, C; Bailly, H; Bujas, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The fuel element making up the first charge for EL-4 is made of slightly enriched uranium oxide canned in stainless steel. This fuel element makes it possible to operate the reactor in the safest conditions awaiting the development of the fuel which will be finally adopted; this will have a low absorption can: beryllium, or a zirconium copper alloy. The 500 mm assembly is made up of 19 small rods placed on 3 rings, inside a graphite jacket. The solution adopted was a solution using completely independent small rods. This report deals with possible problems resulting from their study and production. (authors) [French] L'element combustible du 1er jeu EL-4 est un element combustible a oxyde d'uranium legerement enrichi gaine d'acier inoxydable. C'est un element combustible permettant de faire fonctionner le reacteur EL 4 dans des conditions aussi sures que possible avant de mettre au point le combustible definitif qui sera a gaine peu absorbante: beryllium, ou alliage zirconium-cuivre. L'assemblage de longueur 500 mm est constitue de 19 crayons places sur 3 couronnes, a l'interieur d'une chemise de graphite. La solution adoptee a ete une solution a crayons independants les uns des autres. Ce rapport traite des problemes eventuels poses par leur etude et leur fabrication. (auteurs)

  20. Estimation of covariance matrix on the experimental data for nuclear data evaluation

    International Nuclear Information System (INIS)

    Murata, T.

    1985-01-01

    In order to evaluate fission and capture cross sections of some U and Pu isotopes for JENDL-3, we have a plan for evaluating them simultaneously with a least-squares method. For the simultaneous evaluation, the covariance matrix is required for each experimental data set. In the present work, we have studied the procedures for deriving the covariance matrix from the error data given in the experimental papers. The covariance matrices were obtained using the partial errors and estimated correlation coefficients between the same type partial errors for different neutron energy. Some examples of the covariance matrix estimation are explained and the preliminary results of the simultaneous evaluation are presented. (author)

  1. Construction and tests of a gamma device for experimental measurements of burnup of nuclear reactor fuel

    International Nuclear Information System (INIS)

    Brandao Junior, F.A.

    1982-01-01

    The gamma-scanning method is an important tool for the measurement of burnup of nuclear reactor fuel. The adequate knowledge of burnup allows for a better inventory of 'sensitive' fissile materials, better fuel management and provides insight on fuel behaviour and safety margins. This paper is related to the description, construction and operation of a first gamma scanning device, tested by irradiation of prototype PWR fuel pins, 14 cm long, in a Triga Mark-I reactor at very low power. Despite the limitations imposed by the low burnup, the experiment permitted a good checking of the main physical concepts and devices involved in the method. (Author) [pt

  2. Experimental tests of recent nuclear models with the (n,γ) reaction

    International Nuclear Information System (INIS)

    Casten, R.F.

    1978-01-01

    The nonselectivity of the (n,γ) reaction provides a powerful tool for the study of those nuclear models of broad applicability whose characteristic excitations span a wide range of degrees of freedom. Several recent examples of this are discussed with particular emphasis on the recent discovery of the 0(6) limit of the interacting boson model and of a new interpretation of the Pt--0s transition region which consequently emerges. Other topics considered include recent extensions of the Nilsson model to new regions of nucleus, excitation energy and complexity of states. 43 references

  3. Status of experimental data of proton-induced reactions for intermediate-energy nuclear data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, Yukinobu; Kawano, Toshihiko [Kyushu Univ., Fukuoka (Japan); Yamano, Naoki; Fukahori, Tokio

    1998-11-01

    The present status of experimental data of proton-induced reactions is reviewed, with particular attention to total reaction cross section, elastic and inelastic scattering cross section, double-differential particle production cross section, isotope production cross section, and activation cross section. (author)

  4. Assessment of theoretical and experimental results in the calculation of atmospheric dilution factors in the Atucha I nuclear power plant

    International Nuclear Information System (INIS)

    Quintana, E.E.; Tossi, M.H.; Telleria, D.M.

    1990-01-01

    Collective doses produced during the normal working of the Atucha I Nuclear Power Plant are calculated using annual atmospheric factors. This work studies the behaviour of the dilution factors in different periods of the year in order to fit the calculated dose model applying factors from seasonal, monthly or weekly periods. The Radiation Protection Group of the C.N.E.A. have carried out continuous environmental monitoring in the surroundings of the Atucha I Nuclear Power Plant. These studies include the measurement of air tritium concentration, radionuclide that is found principally as tritiated water vapour. This isotope, normally released by the nuclear power plant was used as a tracer to assess the atmospheric dilution factors. Factors were calculated by two methods: an experimental one, based on environmental measurements of the tritium concentration in the surroundings of the nuclear power plant and another one by applying a theoretical model based on information from the micrometeorological tower located in the mentioned place. To carry out the environmental monitoring, four monitoring stations in the surroundings of the power plant were chosen. Three of them are approximately one kilometer from the plant and the fourth is 7.5 km away, near the city of Lima. To condense and collect the atmospheric water vapour, an overcooling system was used. The measurement was performed by liquid scintillation counting, previous alkaline electrolytical enrichment of the samples. The theoretical model uses hourly values of direction and wind intensity, as well as the atmospheric dispersive properties. Values obtained during the period 1976 to 1988 allowed, applying statistical tests, to validate the theoretical model and to observe seasonal variation of the dilution factors throughout the same year and between different years. Finally, results and graphics are presented showing that the behaviour of the dilution factors in different periods of the year. It is recommended to

  5. Expression of Caspase-3, P53 in EL-4 cells induced by ionizing radiation and its biological implications

    International Nuclear Information System (INIS)

    Ju Guizhi; Shen Bo; Sun Shilong; Yan Fengqin; Fu Shibo; Li Pengwu

    2006-01-01

    Objective: To investigate the effect of ionizing radiation on the expressions of Caspase-3 and P53 proteins in EL-4 cells and its implications in the induction of apoptosis and polyploid cells. Methods: EL- 4 cells were irradiated with 4.0 Gy X-rays (180 kV, 15 mA, 0.287 Gy/min). Fluorescent staining and flow cytometry analysis were used to measure protein expression, apoptosis and polyploid cells. Results: It was found that the expression of Caspase-3 protein was increased significantly at 8 h and 12 h after the irradiation compared with sham-irradiated control (P<0.05), and the expression of P53 protein was also increased significantly at 2,4,8,12 and 24 h after the irradiation compared with sham-irradiated control (P<0.05 or P<0.01). The results showed that apoptosis of EL-4 cells was increased significantly at 2,4,8,12,24,48, and 72 h after 4.0 Gy irradiation compared with sham-irradiated control (P<0.05 or P<0.01 or P<0.001). However, no significant change in the number of polyploidy cells was found during the period from 2 to 48 h after the irradiation with 4.0 Gy X-rays. Conclusions: It is indicated that the expressions of Caspase-3 and P53 protein in EL-4 cells can be induced by ionizing radiation, and play an important role in the induction of apoptosis; the molecular pathway for polyploid formation might be P53-independent. (authors)

  6. RRR-alpha-tocopheryl succinate inhibits EL4 thymic lymphoma cell growth by inducing apoptosis and DNA synthesis arrest.

    Science.gov (United States)

    Yu, W; Sanders, B G; Kline, K

    1997-01-01

    RRR-alpha-tocopheryl succinate (vitamin E succinate, VES) treatment of murine EL4 T lymphoma cells induced the cells to undergo apoptosis. After 48 hours of VES treatment at 20 micrograms/ml, 95% of cells were apoptotic. Evidence for the induction of apoptosis by VES treatments is based on staining of DNA for detection of chromatin condensation/fragmentation, two-color flow-cytometric analyses of DNA content, and end-labeled DNA and electrophoretic analyses for detection of DNA ladder formation. VES-treated EL4 cells were blocked in the G1 cell cycle phase; however, apoptotic cells came from all cell cycle phases. Analyses of mRNA expression of genes involved in apoptosis revealed decreased c-myc and increased bcl-2, c-fos, and c-jun mRNAs within three to six hours after treatment. Western analyses showed increased c-Jun, c-Fos, and Bcl-2 protein levels. Electrophoretic mobility shift assays showed increased AP-1 binding at 6, 12, and 24 hours after treatment and decreased c-Myc binding after 12 and 24 hours of VES treatment. Treatments of EL4 cells with VES+RRR-alpha-to-copherol reduced apoptosis without effecting DNA synthesis arrest. Treatments of EL4 cells with VES+rac-6-hydroxyl-2, 5,7,8-tetramethyl-chroman-2-carboxylic acid, butylated hydroxytoluene, or butylated hydroxyanisole had no effect on apoptosis or DNA synthesis arrest caused by VES treatments. Analyses of bcl-2, c-myc, c-jun, and c-fos mRNA levels in cells receiving VES + RRR-alpha-tocopherol treatments showed no change from cells receiving VES treatments alone, implying that these changes are correlated with VES treatments but are not causal for apoptosis. However, treatments with VES + RRR-alpha-tocopherol decreased AP-1 binding to consensus DNA oligomer, suggesting AP-1 involvement in apoptosis induced by VES treatments.

  7. Differential Expression of FAK and Pyk2 in Metastatic and Non-metastatic EL4 Lymphoma Cell Lines

    OpenAIRE

    Zhang, Zhihong; Knoepp, Stewart M.; Ku, Hsun; Sansbury, Heather M.; Xie, Yuhuan; Chahal, Manpreet S.; Tomlinson, Stephen; Meier, Kathryn E.

    2011-01-01

    The murine EL4 lymphoma cell line exists in variants that are either sensitive or resistant to phorbol 12-myristate 13-acetate (PMA). In sensitive cells, PMA causes Erk MAPK activation and Erk-mediated growth arrest. In resistant cells, PMA induces a low level of Erk activation, without growth arrest. A relatively unexplored aspect of the phenotypes is that resistant cells are more adherent to culture substrate than are sensitive cells. In this study, the roles of the protein tyrosine kinases...

  8. Procedure and information displays in advanced nuclear control rooms: experimental evaluation of an integrated design.

    Science.gov (United States)

    Chen, Yue; Gao, Qin; Song, Fei; Li, Zhizhong; Wang, Yufan

    2017-08-01

    In the main control rooms of nuclear power plants, operators frequently have to switch between procedure displays and system information displays. In this study, we proposed an operation-unit-based integrated design, which combines the two displays to facilitate the synthesis of information. We grouped actions that complete a single goal into operation units and showed these operation units on the displays of system states. In addition, we used different levels of visual salience to highlight the current unit and provided a list of execution history records. A laboratory experiment, with 42 students performing a simulated procedure to deal with unexpected high pressuriser level, was conducted to compare this design against an action-based integrated design and the existing separated-displays design. The results indicate that our operation-unit-based integrated design yields the best performance in terms of time and completion rate and helped more participants to detect unexpected system failures. Practitioner Summary: In current nuclear control rooms, operators frequently have to switch between procedure and system information displays. We developed an integrated design that incorporates procedure information into system displays. A laboratory study showed that the proposed design significantly improved participants' performance and increased the probability of detecting unexpected system failures.

  9. Measuring nuclear-spin-dependent parity violation with molecules: Experimental methods and analysis of systematic errors

    Science.gov (United States)

    Altuntaş, Emine; Ammon, Jeffrey; Cahn, Sidney B.; DeMille, David

    2018-04-01

    Nuclear-spin-dependent parity violation (NSD-PV) effects in atoms and molecules arise from Z0 boson exchange between electrons and the nucleus and from the magnetic interaction between electrons and the parity-violating nuclear anapole moment. It has been proposed to study NSD-PV effects using an enhancement of the observable effect in diatomic molecules [D. DeMille et al., Phys. Rev. Lett. 100, 023003 (2008), 10.1103/PhysRevLett.100.023003]. Here we demonstrate highly sensitive measurements of this type, using the test system 138Ba19F. We show that systematic errors associated with our technique can be suppressed to at least the level of the present statistical sensitivity. With ˜170 h of data, we measure the matrix element W of the NSD-PV interaction with uncertainty δ W /(2 π )<0.7 Hz for each of two configurations where W must have different signs. This sensitivity would be sufficient to measure NSD-PV effects of the size anticipated across a wide range of nuclei.

  10. Transfer-induced fission in inverse kinematics: Impact on experimental and evaluated nuclear data bases

    Energy Technology Data Exchange (ETDEWEB)

    Farget, F.; Schmidt, K.H.; Clement, E.; Delaune, O.; Derkx, X.; Dijon, A.; Golabek, C.; Lemasson, A.; Roger, T.; Schmitt, C. [CEA/DSM-CNRS/IN2P3, GANIL, Caen (France); Caamano, M.; Ramos, D.; Benlliure, J.; Cortina, D.; Fernandez-Dominguez, B.; Paradela, C. [Universidade de Santiago de Compostela, Santiago de Compostela (Spain); Rodriguez-Tajes, C. [CEA/DSM-CNRS/IN2P3, GANIL, Caen (France); Universidade de Santiago de Compostela, Santiago de Compostela (Spain); Audouin, L. [Universite Paris-Sud 11, CNRS/IN2P3, Institut de Physique Nucleaire, Orsay (France); Casarejos, E. [Universidade de Vigo, Vigo (Spain); Dore, D.; Salsac, M.D. [Centre de Saclay, CEA, Irfu, Gif-sur-Yvette (France); Gaudefroy, L. [CEA DAM Ile-de-France, BP 12, Bruyeres-le-Chatel (France); Heinz, A. [Chalmers Tekniska Hoegskola, Fundamental Fysik, Goeteborg (Sweden); Jurado, B. [Universite Bordeaux, CENBG, UMR 5797 CNRS/IN2P3, Gradignan (France)

    2015-12-15

    Inverse kinematics is a new tool to study nuclear fission. Its main advantage is the possibility to measure with an unmatched resolution the atomic number of fission fragments, leading to new observables in the properties of fission-fragment distributions. In addition to the resolution improvement, the study of fission based on nuclear collisions in inverse kinematics beneficiates from a larger view with respect to the neutron-induced fission, as in a single experiment the number of fissioning systems and the excitation energy range are widden. With the use of spectrometers, mass and kinetic-energy distributions may now be investigated as a function of the proton and neutron number sharing. The production of fissioning nuclei in transfer reactions allows studying the isotopic yields of fission fragments as a function of the excitation energy. The higher excitation energy resulting in the fusion reaction leading to the compound nucleus {sup 250}Cf at an excitation energy of 45MeV is also presented. With the use of inverse kinematics, the charge polarisation of fragments at scission is now revealed with high precision, and it is shown that it cannot be neglected, even at higher excitation energies. In addition, the kinematical properties of the fragments inform on the deformation configuration at scission. (orig.)

  11. Basic principles of accounting and control of nuclear materials in the BOR-60 experimental fast reactor

    International Nuclear Information System (INIS)

    Gryazev, V.M.; Gadzhiev, G.I.; Alekseev, I.N.

    1979-01-01

    Under a contract with the International Atomic Energy Agency, the V.I. Lenin Atomic Reactor Research Institute is currently carrying out a study of ways of organizing a nuclear materials accounting and control system for the BOR-60 fast reactor. Some results of this study are presented in the paper. The special physical and technological features of fast reactors create additional difficulties in safeguards systems and give rise to a number of new possibilities for the illicit removal of nuclear materials. These questions are discussed with reference to the BOR-60 reactor but the conclusions are probably applicable to all fast reactors. The proposed accounting and control system is based on non-destructive measurements of the amount of fissile materials in the operating fuel assemblies and screened bundles of the reactor, on the independent control of the principal facility parameters (a list of which is given) and on an automated information collection and evaluation system. Visual means of inspection can be very effective in fast reactor safeguards systems, especially for controlling storage, but they are not used with the BOR-60 reactor. (author)

  12. Response tree evaluation: experimental assessment of an expert system for nuclear reactor operators

    International Nuclear Information System (INIS)

    Nelson, W.R.; Blackman, H.S.

    1985-09-01

    The United States Nuclear Regulatory Commission (USNRC) sponsored a project performed by EG and G Idaho, Inc., at the Idaho National Engineering Laboratory (INEL) to evaluate different display concepts for use in nuclear reactor control rooms. Included in this project was the evaluation of the response tree computer-based decision aid and its associated displays. The response tree evaluation task was deisgned to (1) assess the merit of the response tree decision aid and (2) develop a technical basis for recommendations, guidelines, and criteria for the design and evaluation of computerized decision aids for use in reactor control rooms. Two major experiments have been conducted to evaluate the response tree system. This report emphasizes the conduct and results of the second experiment. An enhanced version of the response tree system, known as the automated response tree system, was used in a controlled experiment using trained reactor operators as test subjects. This report discusses the automated response tree system, the design of the evaluation experiment, and the quantitative results of the experiment. The results of the experiment are compared to the results of the previous experiment to provide an integrated perspective of the response tree evaluation project. In addition, a subjective assessment of the results addresses the implications for the use of advanced, ''intelligent'' decision aids in the reactor control room

  13. Experimental Observation of Nuclear Reactions in Palladium and Uranium - Possible Explanation by Hydrex Mode

    International Nuclear Information System (INIS)

    Dufour, J.; Murat, D.; Dufour, X.; Foos, J.

    2001-01-01

    Experiments with uranium are presented that show a highly exothermal reaction, which can only be of nuclear origin. One striking point of these results is that they clearly show that what is being observed is not some kind of fusion reaction of the deuterium present (only exceedingly small amounts of it are present). This is a strong indication that hydrogen can trigger nuclear reactions that seem to involve the nuclei of the lattice (which would yield a fission-like pattern of products). Confronted with a situation where some experiments in the field yield a fusion-like pattern of products (CF experiments) and others a fissionlike one (LENR experiments), one can reasonably wonder whether one is not observing two aspects of the same phenomenon. Thus, it is proposed to describe CF and LENR reactions as essentially the same phenomenon based on the possible existence of a still hypothetical proton/electron resonance, which would catalyze fissionlike reactions with a neutron sink. Finally, a series of experiments is proposed to assess this hypothesis

  14. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  15. Effect of ionizing radiation in combination with 5-flurouracil on cell cycle uncoupling of EL-4 cell line

    International Nuclear Information System (INIS)

    Liu Yang; Sun Yanhong; Zhang Xuan; Gong Shouliang; Zhang Wei; Li Song

    2009-01-01

    Objective: To observe the dose-and time-effect of ionizing radiation in combination with 5-flurouracil(5-FU) on the cell cycle uncoupling of EL-4 cell line. Methods: EL-4 cells were collected after irradiation with 0,1.0,2.0 and 4.0 Gy X-irradiation and treatment with 5-FU(0.001,0.010,0.100 and 1.000 mg·L -1 ) for 0,4,8,16,24 and 48 h.The regularity in the polyloid cells was analyzed by flow cytometry(FCM) following staining cells with propidium iodide(PI). Results: As compared with sham-irradiation group,the percentage of diploid EL-4 cells increased significantly at 8-24 h and returned to normal level at 48 h after irradiation with 2.0 Gy X-rays(P -1 group, the percentage of diploid cells decreased obviously at 16-48 h after treatment with 0.100 mg·L -1 5-FU(P -1 group, the percentage of diploid cells decreased significantly 16 h after treatment with different doses 5-FU(P -1 ; the percentage of octoploid cells increased significantly after treatment with 0.010 and 0.100 mg·L -1 5-Fu(P -1 5-FU. (authors)

  16. Differential Expression of Ccn4 and Other Genes Between Metastatic and Non-metastatic EL4 Mouse Lymphoma Cells.

    Science.gov (United States)

    Chahal, Manpreet S; Ku, H Teresa; Zhang, Zhihong; Legaspi, Christian M; Luo, Angela; Hopkins, Mandi M; Meier, Kathryn E

    Previous work characterized variants of the EL4 murine lymphoma cell line. Some are non-metastatic, and others metastatic, in syngenic mice. In addition, metastatic EL4 cells were stably transfected with phospholipase D2 (PLD2), which further enhanced metastasis. Microarray analyses of mRNA expression was performed for non-metastatic, metastatic, and PLD2-expressing metastatic EL4 cells. Many differences were observed between non-metastatic and metastatic cell lines. One of the most striking new findings was up-regulation of mRNA for the matricellular protein WNT1-inducible signaling pathway protein 1 (CCN4) in metastatic cells; increased protein expression was verified by immunoblotting and immunocytochemistry. Other differentially expressed genes included those for reproductive homeobox 5 (Rhox5; increased in metastatic) and cystatin 7 (Cst7; decreased in metastatic). Differences between PLD2-expressing and parental cell lines were limited but included the signaling proteins Ras guanyl releasing protein 1 (RGS18; increased with PLD2) and suppressor of cytokine signaling 2 (SOCS2; decreased with PLD2). The results provide insights into signaling pathways potentially involved in conferring metastatic ability on lymphoma cells. Copyright© 2016, International Institute of Anticancer Research (Dr. John G. Delinasios), All rights reserved.

  17. Experimental evaluation of feedforward control for the trajectory tracking of power in nuclear reactors

    International Nuclear Information System (INIS)

    Lau, S.H.; Bernard, J.A.; Lanning, D.D.

    1991-01-01

    This paper reports on an experimental comparison of feedforward control techniques for the trajectory-tracking of neutronic power was performed on the 5-MWt MIT Research Reactor. Included in the comparison were pure feedforward control in which the actuator signal is found solely by processing a demanded output through a system model, hybrid feedforward/feedback control in which the actuator signal is obtained by summing feedforward and feedback components, and period-generated control in which feedback is used to update the demand trajectory prior to its being processed through the system model for calculation of the actuator signal. This latter approach was found to be the most effective. In addition to the experimental results, discussions are given of both the rationale for model-based, feedforward control and the designs of the various controllers

  18. Role of deep inelastic processes in nuclear physics: experimental and theoretical aspects of deep inelastic reactions

    International Nuclear Information System (INIS)

    Moretto, L.G.

    1979-03-01

    The collective modes excited in deep-inelastic reactions and their natural hierarchy provided by their characteristic relaxation times is described. The relaxation of the mass asymmetry mode is discussed in terms of a diffusion process. Charge distributions and angular distributions as a function of Z calculated with this model are in good agreement with experimental data. This diffusion model also treats the transfer of energy and angular momentum in terms of particle transfer, and is successfully compared with experimental γ-ray multiplicities as a function of both Q-value and mass asymmetry. The angular momentum transfer is again considered in connection with the sequential fission of heavy, deep-inelastic fragments and the excitation of collective modes in the exit channel is considered. The role of the giant E1 mode in the equilibration of the neutron-to-proton ratio is discussed. 39 references

  19. Experimental investigations on the transient behaviour of nuclear heat plants with natural convection

    International Nuclear Information System (INIS)

    Adam, E.; Sydow, J.; Wolff, J.

    1988-01-01

    Apart from the theoretical approach, practical experiments concerning the transient behaviour of the primary loop of reactors with natural coolant convection are necessary in order to evaluate the safety systems of reactors providing heat for industrial and communal consumers. The article presents experiments concerning the transient behaviour of the experimental plant DANTON, which models the reactor AST-500, and gives a preview of further research. (orig.) [de

  20. Transforming growth factor-beta 1 (TGF-beta1) promotes IL-2 mRNA expression through the up-regulation of NF-kappaB, AP-1 and NF-AT in EL4 cells.

    Science.gov (United States)

    Han, S H; Yea, S S; Jeon, Y J; Yang, K H; Kaminski, N E

    1998-12-01

    Transforming growth factor beta1 (TGF-beta1) has been previously shown to modulate interleukin 2 (IL-2) secretion by activated T-cells. In the present studies, we determined that TGF-beta1 induced IL-2 mRNA expression in the murine T-cell line EL4, in the absence of other stimuli. IL-2 mRNA expression was significantly induced by TGF-beta1 (0.1-1 ng/ml) over a relatively narrow concentration range, which led to the induction of IL-2 secretion. Under identical condition, we examined the effect of TGF-beta1 on the activity of nuclear factor AT (NF-AT), nuclear factor kappaB (NF-kappaB), activator protein-1 (AP-1) and octamer, all of which contribute to the regulation of IL-2 gene expression. Electrophoretic mobility shift assays showed that TGF-beta1 markedly increased NF-AT, NF-kappaB and AP-1 binding to their respective cognate DNA binding sites, whereas octamer binding remained constant, as compared with untreated cells. Employing a reporter gene expression system with p(NF-kappaB)3-CAT, p(NF-AT)3-CAT and p(AP-1)3-CAT, TGF-beta1 treatment of transfected EL4 cells induced a dose-related increase in chloramphenicol acetyltransferase activity that correlated well with the DNA binding profile found in the electrophoretic mobility shift assay studies. These results show that TGF-beta1, in the absence of any additional stimuli, up-regulates the activity of key transcription factors involved in IL-2 gene expression, including NF-AT, NF-kappaB and AP-1, to help promote IL-2 mRNA expression by EL4 cells.

  1. Tests of experimental fuel elements by the method of nuclear-thermal pulse loadings in 'HYDRA' reactor

    International Nuclear Information System (INIS)

    Nastoyashchaya, O.V.; Lebedev, Yu. M.; Chechurov, A.M.; Khvostionov, Ye

    1997-01-01

    The results of tests of experimental fuel elements with uranium dioxide fuel composition embedded in Al and Zr matrix with the enrichment from 90% to 36% in respect to U-235 performed at the pulse 'HYDRA' reactor are presented in this paper. Testing is performed in the frame-work of extensive research program studying the behavior of fuel elements (FE) of research and mini nuclear power systems in case of practically immediate energy release in the fuel taking place during the RIA-type accidents. Duration of the neutron pulse when testing in 'HYDRA' reactor is from 7 to 20 ms. The methods of diagnostics of the state of FE prior to and after testing in the reactor are developed and verified. Mathematical model describing temperature fields inside the FE in the process of testing. and accounting for non-uniformity of fuel composition has been developed in order to summarize experimental results. Experimental data on the limiting values of the energy density leading to deformation and degradation of FE depending on the type of fuel composition have been obtained and the mechanisms for the development of these processes have been determined. The nature of physical-chemical processes taking place in the fuel composition and fuel cladding depending on material composition under different levels of energy deposition is demonstrated. The data on hydrogen generation and radioactive product release out of fuel after failure of FE are presented. (author)

  2. Algoritmo para el 4ap haciendo uso de la metaheuristica sistema hormiga

    Directory of Open Access Journals (Sweden)

    Manuel Vicente Centeno Romero

    2008-07-01

    Full Text Available La metaheurística sistema hormiga consiste en la analogía entre el procedimiento que utilizan las hormigas reales para la búsqueda de alimentos, encontrando la ruta más corta, y los problemas de optimización combinatoria para encontrar la mejor solución. Entre estos problemas se encuentra el de asignación multidimensional (mAP, el cual es un problema NP-difícil para m > 2. En la actualidad no se ha desarrollado trabajo alguno sobre el 4AP (mAP con m=4, tampoco existe publicación sobre la aplicación del sistema hormiga para el mAP. En este trabajo se desarrolló un software que hace uso de la metaheurística sistema hormiga para encontrar la mejor solución o aproximada al 4AP, con problemas generados aleatoriamente. Se implementó una metodología híbrida entre la metodología de Investigación de Operaciones descrita por Taha (1991 y la ingeniería de software (1990. El número de asignaciones tomadas en cuenta para verificar qué tan buenas son las soluciones arrojadas por el software, varía desde n=2 hasta n=25, obteniéndose soluciones exactas para 2 £ n £ 6, ya que al compararse dichas soluciones con las dadas por XPRESS (software de programación lineal que se usa para resolver modelos matemáticos se observa la igualdad en los resultados. Para n _ 7, XPRESS (la versión utilizada no ofrece respuesta alguna, pero el software desarrollado arroja buenos resultados en un tiempo computacional razonable, considerando el número de asignaciones que se procesan en cada n. The metaheuristic ant system consists on the analogy among the procedure used by the real ants for searching food, for finding the shortest route; and the problems of combinatoria optimization to find the best solution. Among these problems we can find the multidimensional assignment problem (mAP, which is a NP-difficult problem for m > 2. At the present time, there isn‘t any work that has been developed, on this topic about the 4AP (mAP with m=4, neither

  3. Nuclear constants for activation analysis of some nuclides and comparison with experimentally measured values

    International Nuclear Information System (INIS)

    Jacimovic, R.; Trkov, A.; Smodis, B.

    1995-01-01

    Neutron activation analysis requires a knowledge of the values for the Westcott g factors, the resonance integral I 0 and 2200 ms -1 cross section σ 0 for the (n, γ) reaction, Q 0 defined as the ratio I 0 /σ 0 and the effective resonance energy E-bar r . The required constants can be calculated from the JEF 2.2 evaluated nuclear data files. A sensitivity study was carried out to investigate the influence of the spectral parameter α on E-bar r . The sensitivity of I 0 to temperature due to Doppler broadening was also investigated. The results obtained were compared to those reported in the literature. Further, the calculated parameters were then applied to the analysis of a number of standard samples. (author)

  4. Experimental study of radioactive aerosols in the vicinity of the Chernobyl Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Boulyga, S.F.; Lomonosova, E.M.; Zhuk, I.V.; Yaroshevich, O.I.; Kudrjashov, V.P.; Mironov, V.P

    1999-12-01

    Study of radioactive aerosols in the relocation zone and in the populated areas have been carried out for a number of years. The experiments on modelling resuspension were performed while conducting agricultural work. Nuclear track radiography and alpha spectrometry with radiochemical extraction of plutonium were used as analytical methods for the determination of the transuranium elements contents. The distributions of radioactive particles were obtained as to activity and sizes. Specific activity of 'hot particles' increases with decreasing diameter. In aerosols selected at a distance of more than 10 km from the Chernobyl NPP pure fuel particles with sizes of more than 5 {mu}m were not found. The activity of the finely dispersed fraction of aerosols, which is more dangerous when inhaled by the organism, is comparable with a total activity of large particles.

  5. Experimental study of radioactive aerosols in the vicinity of the Chernobyl Nuclear Power Plant

    International Nuclear Information System (INIS)

    Boulyga, S.F.; Lomonosova, E.M.; Zhuk, I.V.; Yaroshevich, O.I.; Kudrjashov, V.P.; Mironov, V.P.

    1999-01-01

    Study of radioactive aerosols in the relocation zone and in the populated areas have been carried out for a number of years. The experiments on modelling resuspension were performed while conducting agricultural work. Nuclear track radiography and alpha spectrometry with radiochemical extraction of plutonium were used as analytical methods for the determination of the transuranium elements contents. The distributions of radioactive particles were obtained as to activity and sizes. Specific activity of 'hot particles' increases with decreasing diameter. In aerosols selected at a distance of more than 10 km from the Chernobyl NPP pure fuel particles with sizes of more than 5 μm were not found. The activity of the finely dispersed fraction of aerosols, which is more dangerous when inhaled by the organism, is comparable with a total activity of large particles

  6. Experimental investigations into sample preparation of Alzheimer tissue specimens for nuclear microprobe analysis

    Energy Technology Data Exchange (ETDEWEB)

    Pinheiro, T [CEC-JRC, Central Bureau for Nuclear Measurements, Geel (Belgium); Tapper, U A.S. [Dept. of Nuclear Physics, Lund Inst. of Science and Tech. (Sweden); Sturesson, K; Brun, A [Div. of Neuropathology, Dept. of Pathology, Lund University Hospital (Sweden)

    1991-03-01

    Nuclear microprobe analysis was applied to the study of elemental distribution in brains sections of patients with a diagnosis of Alzheimer's disease. Stained and nonstained cryosections were studied. The work carried out shows that serious elemental losses follow the sample staining procedure. Major losses occurred in a simple rinse of the tissue section, probably reducing most of the in-vivo gradients, which show that generally very little information can be gained from stained sections. However, in many cases stained sections are compulsory because of the requirement to recognize the area which is to be studied. All the elemental maps obtained for the neurofibrillary deposits indicate a localized concentration for Si and probably also Al, associated with the senile plaque core. Neither of these elements were found in the staining solutions used. The validity of the results is discussed as well as the possible link of Al and/or Si in the development of Alzheimer's desease. (orig.).

  7. Experimental studies of computerized procedures and team size in nuclear power plant operations

    International Nuclear Information System (INIS)

    Huang, F.-H.; Hwang, S.-L.

    2009-01-01

    The operation of a nuclear power plant is so complex that it requires teamwork. To support team performance, a system need to provide all team members integrated information displays as well as decision aids (e.g., computerized procedures). Two experiments were conducted to investigate the effects of computerized procedures and team size on operating performance. Forty-five participants were involved in the experiments. Each participant executed decision and action tasks to deal with alarm signals, while detecting occasional system errors in the interface. Results showed that effects of computerized procedures were significant on various performance indicators, such as operation time, operation errors, and learning effect, and that two operators would be a satisfactory size in the teamwork system providing computerized procedures

  8. Description of an aircraft lightning and simulated nuclear electromagnetic pulse (NEMP) threat based on experimental data

    Science.gov (United States)

    Rustan, Pedro L., Jr.

    1987-01-01

    Lightning data obtained by measuring the surface electromagnetic fields on a CV-580 research aircraft during 48 lightning strikes between 1500 and 18,000 feet in central Florida during the summers of 1984 and 1985, and nuclear electromagnetic pulse (NEMP) data obtained by surface electromagnetic field measurements using a 1:74 CV-580 scale model, are presented. From one lightning event, maximum values of 3750 T/s for the time rate of change of the surface magnetic flux density, and 4.7 kA for the peak current, were obtained. From the simulated NEMP test, maximum values of 40,000 T/s for the time rate of change of the surface magnetic flux density, and 90 A/sq m for the total normal current density, were found. The data have application to the development of a military aircraft lightning/NEMP standard.

  9. New trends in nuclear fuel experimental irradiation. Modern control and acquisition of the irradiation data

    International Nuclear Information System (INIS)

    Preda, M.; Ciocanescu, M.; Ana, E.M.

    2010-01-01

    With the irradiation devices used in the irradiation tests, the following experiments have been performed in TRIGA-SCN reactor: a) In capsule-type irradiation devices: - fission gases composition determination; - dimensional measurements; - fission gases pressure measurement; - power pre-ramp and ramp; - power cycling; - structural materials testing. b) In loop-type irradiation device: - power ramp; - multiple power ramps; - overpower. Aiming to develop irradiation tests for advanced nuclear fuel elements, it is mandatory to increase the maximum neutron flux in the core with about 20%. This will lead to reactor power increase up to 21 MW. This objective can be reached through: - increasing the number of fuel clusters in the reactor core; - using the 6x6 fuel cluster to replace the present 5x5 clusters; - relocation of the control rods. In this context, the new control system and the data acquisition system operates online and allows real-time data evaluation. (author)

  10. The use of experimental data in an MTR-type nuclear reactor safety analysis

    Science.gov (United States)

    Day, Simon E.

    Reactivity initiated accidents (RIAs) are a category of events required for research reactor safety analysis. A subset of this is unprotected RIAs in which mechanical systems or human intervention are not credited in the response of the system. Light-water cooled and moderated MTR-type ( i.e., aluminum-clad uranium plate fuel) reactors are self-limiting up to some reactivity insertion limit beyond which fuel damage occurs. This characteristic was studied in the Borax and Spert reactor tests of the 1950s and 1960s in the USA. This thesis considers the use of this experimental data in generic MTR-type reactor safety analysis. The approach presented herein is based on fundamental phenomenological understanding and uses correlations in the reactor test data with suitable account taken for differences in important system parameters. Specifically, a semi-empirical approach is used to quantify the relationship between the power, energy and temperature rise response of the system as well as parametric dependencies on void coefficient and the degree of subcooling. Secondary effects including the dependence on coolant flow are also examined. A rigorous curve fitting approach and error assessment is used to quantify the trends in the experimental data. In addition to the initial power burst stage of an unprotected transient, the longer term stability of the system is considered with a stylized treatment of characteristic power/temperature oscillations (chugging). A bridge from the HEU-based experimental data to the LEU fuel cycle is assessed and outlined based on existing simulation results presented in the literature. A cell-model based parametric study is included. The results are used to construct a practical safety analysis methodology for determining reactivity insertion safety limits for a light-water moderated and cooled MTR-type core.

  11. The use of experimental data in an MTR-type nuclear reactor safety analysis

    International Nuclear Information System (INIS)

    Day, S.E.

    2006-01-01

    Reactivity initiated accidents (RIAs) are a category of events required for research reactor safety analysis. A subset of this is unprotected RIAs in which mechanical systems or human intervention are not credited in the response of the system. Light-water cooled and moderated MTR-type (i.e., aluminum-clad uranium plate fuel) reactors are self-limiting up to some reactivity insertion limit beyond which fuel damage occurs. This characteristic was studied in the Borax and Spert reactor tests of the 1950s and 1960s in the USA. This thesis considers the use of this experimental data in generic MTR-type reactor safety analysis. The approach presented herein is based on fundamental phenomenological understanding and uses correlations in the reactor test data with suitable account taken for differences in important system parameters. Specifically, a semi-empirical approach is used to quantify the relationship between the power, energy and temperature rise response of the system as well as parametric dependencies on void coefficient and the degree of subcooling. Secondary effects including the dependence on coolant flow are also examined. A rigorous curve fitting approach and error assessment is used to quantify the trends in the experimental data. In addition to the initial power burst stage of an unprotected transient, the longer term stability of the system is considered with a stylized treatment of characteristic power/temperature oscillations (chugging). A bridge from the HEU-based experimental data to the LEU fuel cycle is assessed and outlined based on existing simulation results presented in the literature. A cell-model based parametric study is included. The results are used to construct a practical safety analysis methodology for determining reactivity insertion safety limits for a light-water moderated and cooled MTR-type core. (author)

  12. The use of experimental data in an MTR-type nuclear reactor safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Day, S.E

    2006-07-01

    Reactivity initiated accidents (RIAs) are a category of events required for research reactor safety analysis. A subset of this is unprotected RIAs in which mechanical systems or human intervention are not credited in the response of the system. Light-water cooled and moderated MTR-type (i.e., aluminum-clad uranium plate fuel) reactors are self-limiting up to some reactivity insertion limit beyond which fuel damage occurs. This characteristic was studied in the Borax and Spert reactor tests of the 1950s and 1960s in the USA. This thesis considers the use of this experimental data in generic MTR-type reactor safety analysis. The approach presented herein is based on fundamental phenomenological understanding and uses correlations in the reactor test data with suitable account taken for differences in important system parameters. Specifically, a semi-empirical approach is used to quantify the relationship between the power, energy and temperature rise response of the system as well as parametric dependencies on void coefficient and the degree of subcooling. Secondary effects including the dependence on coolant flow are also examined. A rigorous curve fitting approach and error assessment is used to quantify the trends in the experimental data. In addition to the initial power burst stage of an unprotected transient, the longer term stability of the system is considered with a stylized treatment of characteristic power/temperature oscillations (chugging). A bridge from the HEU-based experimental data to the LEU fuel cycle is assessed and outlined based on existing simulation results presented in the literature. A cell-model based parametric study is included. The results are used to construct a practical safety analysis methodology for determining reactivity insertion safety limits for a light-water moderated and cooled MTR-type core. (author)

  13. Clustering of experimental data and its application to nuclear data evaluation

    International Nuclear Information System (INIS)

    Abboud, A.; Rashed, R.; Ibrahim, M.

    1997-01-01

    A semi-automatic pre-processing technique has been proposed by Iwasaki to classify the experimental data for a reaction into one or a small number of large data groups, called main cluster(s), and to eliminate some data which deviate from the main body of the data. The classifying method is based on a technique like pattern clustering in the information processing domain. Test of the data clustering formed reasonable main clusters for three activation cross-sections. This technique is a helpful tool in the neutron cross-section evaluation. (author). 4 refs, 1 fig., 3 tabs

  14. Clustering of experimental data and its application to nuclear data evaluation

    International Nuclear Information System (INIS)

    Abboud, A.; Rashed, R.; Ibrahim, M.

    1998-01-01

    A semi-automatic pre-processing technique has been proposed by Iwasaki to classify the experimental data for a reaction into one or a small number of large data groups, called main cluster (s), and to eliminate some data which deviates from the main body of the data. The classifying method is based on technique like pattern clustering in the information processing domain. Test of the data clustering formed reasonable main clusters for three activation cross-sections. This technique is a helpful tool in the neutron cross-section evaluation

  15. Measurement with SR-0 experimental modules of the SPHINX nuclear transmutation system. Variants 2008

    International Nuclear Information System (INIS)

    Rypar, Vojtech; Juricek, Vlastimil; Svadlenkova, Marie; Heraltova, Lenka; Viererbl, Ladislav; Lahodova, Zdena

    2008-12-01

    Experiments were performed with two LR-0 rector core arrangements and 3 variants of SR-0 insertion modules with a view to establishing the critical parameters of the reactor cores for the 3 module variants comprising different materials and different numbers of LR-0 fuel pins. The effect of the materials on the photon dose distribution and, on the axial and radial neutron field distributions (via 140 Ba and 140 La activities) was examined and the reaction rate distribution of activation foils inside the experimental module was measured

  16. Direct nuclear reactions with polarized protons: an experimental study of Ge and Se

    International Nuclear Information System (INIS)

    Moonen, W.H.L.

    1986-01-01

    The present investigation, is concerned with excited states of some transitional nuclides, which, through the experimental improvements, became accessible for polarized proton experiments. The aim was to see how nuclei behave when they have a proton and/or neutron number inbetween 28 and 50. Another aim was the completion of the picture of even-even nuclei in general where the research started with the nuclei Fe (Z=26) and Ni (Z=28). Therefore some nuclei were chosen which follow this series: Ge, Z=32, N=38,40,42,44; Se, Z=34, N=42,44,46. (Auth.)

  17. Experimental determination of an ionisation detector for measuring the nuclear lifetime

    International Nuclear Information System (INIS)

    Tisserant, S.

    1982-06-01

    The proton or neutron decay signature needs a good measurement of the varied produced particle energy, together with a good identification of them. The lack of experimental data on electron and charged pion of low energy led to experiment two series of tests. This thesis study precise, from these tests, the performances of the detector that will be installed at Modane. Prototype performances are first studied, concerning the particle energy measurement (electron and charged pions) and their identification. To extrapolate these results to the final detector, simulation programs will be used. The application of such a program that Electron-Gamma-Shower to energies below 500 MeV/c 2 for electromagnetic showers will be verified. For the pions, a simulation program of pion-nucleus interactions at low energy will be checked out from the experimental test data. Scattering effects, charge exchange and absorption are particularly concerned. These simulations reproduce the prototype results; they will be applied to the expected decay modes of proton and neutron. It will be shown that a fine grain detector. Shows a comparable sensitivty for every mode without final neutrino. Triggering probability and decay sign probability will be studied particularly [fr

  18. Experimental studies on tungsten-armour impact on nuclear responses of solid breeding blanket

    International Nuclear Information System (INIS)

    Sato, Satoshi; Nakao, Makoto; Verzilov, Yury; Ochiai, Kentaro; Wada, Masayuki; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori; Nishitani, Takeo

    2005-01-01

    In order to experimentally evaluate the tungsten armour impact on tritium production of the solid breeding blanket being developed by JAERI for tokamak-type DEMO reactors, neutronics integral experiments have been performed using DT neutrons at the Fusion Neutron Source facility of JAERI. Solid breeding blanket mockups relevant to the DEMO blanket have been applied in this study. The mockups are made of a set of layers consisting of 0-25.2 mm thick tungsten, 16 mm thick F82H, 12 mm thick Li 2 TiO 3 and 100-200 mm thick beryllium with a cross-section of 660 x 660 mm in maximum. Pellets of Li 2 CO 3 are embedded in the Li 2 TiO 3 layers to measure the tritium production rate. By installing the 5 mm, 12.6 mm and 25.2 mm thick tungsten armours, the sum of the integrated tritium productions at the pellets are reduced by about 2.1%, 2.5% and 6.1% relative to the case without the armour, respectively. Numerical calculations have been conducted using the Monte Carlo code. In the case of the mockups with the tungsten armour, calculation results for the sum of the integrated tritium productions agree well with the experimental data within 4% and 19% in the experiments without and with a neutron reflector, respectively

  19. Experimental studies on tungsten-armour impact on nuclear responses of solid breeding blanket

    Science.gov (United States)

    Sato, Satoshi; Nakao, Makoto; Verzilov, Yury; Ochiai, Kentaro; Wada, Masayuki; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori; Nishitani, Takeo

    2005-07-01

    In order to experimentally evaluate the tungsten armour impact on tritium production of the solid breeding blanket being developed by JAERI for tokamak-type DEMO reactors, neutronics integral experiments have been performed using DT neutrons at the Fusion Neutron Source facility of JAERI. Solid breeding blanket mockups relevant to the DEMO blanket have been applied in this study. The mockups are made of a set of layers consisting of 0-25.2 mm thick tungsten, 16 mm thick F82H, 12 mm thick Li2TiO3 and 100-200 mm thick beryllium with a cross-section of 660 × 660 mm in maximum. Pellets of Li2CO3 are embedded in the Li2TiO3 layers to measure the tritium production rate. By installing the 5 mm, 12.6 mm and 25.2 mm thick tungsten armours, the sum of the integrated tritium productions at the pellets are reduced by about 2.1%, 2.5% and 6.1% relative to the case without the armour, respectively. Numerical calculations have been conducted using the Monte Carlo code. In the case of the mockups with the tungsten armour, calculation results for the sum of the integrated tritium productions agree well with the experimental data within 4% and 19% in the experiments without and with a neutron reflector, respectively.

  20. Theoretical-experimental assessment of the variables affecting fretting of Atucha I nuclear power plant utility steam generators tubes

    International Nuclear Information System (INIS)

    Kulichevsky, Raul M.

    1995-01-01

    Fretting wear of Steam Generator tubes caused by flow induced vibrations generates uncertainty on their integrity. The knowledge of the controlling variables of the wear process may give a criterion to evaluate the tubes residual life. Information on vibratory response and dynamic interaction between tubes and their supports are prerequisites for understanding the relationship between fretting wear and tube vibration. Experimental results of the vibratory response of an Atucha-I nuclear power plant type U-tube, the influence of tube/support clearance on this response and a study of tube/support dynamic interaction, which allow the verification of a finite element model of this type of tubes, are presented in this work. Also wear results for the Incoloy 800/DIN 1.4550 austenitic stainless steel pair of materials and a first evaluation of the wear constant of this pair are presented. (author)

  1. The experimental study of pollution meteorology and diffusion feature in the site of Tianwan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Hu Erbang; Yao Rentai; Xin Cuntian; Chen Jiayi

    2003-01-01

    The experimental observation and study of pollution meteorology and diffusion feature in site of Tianwan nuclear power plant is described. Four sets of (10, 30, 70, 100 m) sensors set on a 100-m-height tower to measure wind speed, wind direction and temperature were used to obtain hourly meteorological information during 1997-08 to 1999-08. The feature of middle scale wind field and the example and frequency of sea and land breezes are analyzed. The observation and formula of the internal boundary layer are completed. A simulation tests were done in a wind tunnel. In order to obtain the diffusion parameter the turbulence observation on two height of 100 m-height tower and 10 sets of SF 6 tracer experiments were done in summer, 1997. Based on above measured data the annual atmospheric dispersion factor and the accident probability dispersion factor at the boundary of an area of no residences were estimated. (authors)

  2. Comprehensive safety analysis code system for nuclear fusion reactors II: Thermal analysis during plasma disruptions for international thermonuclear experimental reactor

    International Nuclear Information System (INIS)

    Honda, T.; Maki, K.; Okazaki, T.

    1994-01-01

    Thermal characteristics of a fusion reactor [International Thermonuclear Experimental Reactor (ITER) Conceptual Design Activity] during plasma disruptions have been analyzed by using a comprehensive safety analysis code for nuclear fusion reactors. The erosion depth due to disruptions for the armor of the first wall depends on the current quench time of disruptions occurring in normal operation. If it is possible to extend the time up to ∼50 ms, the erosion depth is considerably reduced. On the other hand, the erosion depth of the divertor is ∼570 μm for only one disruption, which is determined only by the thermal flux during the thermal quench. This means that the divertor plate should be exchanged after about nine disruptions. Counter-measures are necessary for the divertor to relieve disruption influences. As other scenarios of disruptions, beta-limit disruptions and vertical displacement events were also investigated quantitatively. 13 refs., 5 figs

  3. Overview of experimental results obtained under the Prestressed Concrete Nuclear Pressure Vessel Development Program at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Naus, D.J.

    1978-01-01

    Under the Prestressed Concrete Nuclear Pressure Vessel Development Program at the Oak Ridge National Laboratory, various aspects of Prestressed Concrete Pressure Vessels (PCPVs) are investigated and evaluated with respect to reliability, structural performance, constructability, and economy. Based upon identified needs, analytical and experimental investigations are conducted. Areas of interest include finite-element analysis development, materials and structural behavior tests, instrumentation evaluation and development, and structural model tests. Studies have been recently completed in the following areas: concrete embedment instrumentation systems for PCPVs, grouted-nongrouted prestressing systems, acoustic emission as a technique for structural integrity monitoring, and model tests of steam-generator cavity closure plugs for a Gas-Cooled Fast Reactor (GCFR). An overview of results is presented

  4. An option for the Brazilian nuclear project: necessity of fast breeder reactors and core design for an experimental fast reactor

    International Nuclear Information System (INIS)

    Ishiguro, Y.

    1983-01-01

    In order to assure the continued utilization of fission energy, development of fast breeder reactors (FBRs) is a necessity. Binary fueled LMFBRs are proposed as the best type for future Brazilian nuclear systems. The inherent safety characteristics are superior to current FBRs and an efficient utilization of the abundant thorium is possible. A first step and a basic tool for the development of FBR technologies is the construction and operation of an experimental fast reactor (EFR). A series of core designs for a 90 MW EFR is studied and possible options and the magnitudes of principal parameters are identified. Flexible modifications of the core and sufficiently high fast fluxes for fuel and materials irradiations appear possible. (Author) [pt

  5. Experimental observations to the electrical field for electrorefining of spent nuclear fuel in the Mark-IV electrorefiner

    International Nuclear Information System (INIS)

    Li, S. X.

    1998-01-01

    Experimental results from the pilot scale electrorefiner (Mark-IV ER) treating spent nuclear fuel are reported in this article. The electrorefining processes were carried out in a LiCl-KCl-UCl 3 electrolyte. It has been noted that spool of molten cadmium below the electrolyte plays an important role in the electrorefining operations. In addition, formations of electrical shorting path between anode baskets and the electrorefiner vessel were observed, which lessened the uranium dissolution process from anode baskets, however appeared to improve the morphology of cathode deposit. The FIDAP simulation code was used to calculate the electrical potential field distributions and the potential gradient near the cathode. The effect of the electrical shorting between anode baskets and electrorefiner vessel on the morphology of cathode products is discussed

  6. Experimental investigation and modelling of tritium washout by precipitation in the area of the nuclear power plant of Paks, Hungary

    International Nuclear Information System (INIS)

    Koello, Z.; Palcsu, L.; Major, Z.; Papp, L.; Molnar, M.; Ranga, T.; Dombovari, P.; Manga, L.

    2011-01-01

    Tritium occurs in nature in trace amounts, but its concentration is changing due to natural and artificial sources. Studies focusing on natural tritium have to take into account the effect of artificial sources. Also, the impact of tritium is an important issue in environmental protection, e.g. in connection with the emissions from nuclear power plants. The present work focuses on the rain washout of tritium emitted from the Paks nuclear power plant in Hungary. Rainwater collectors were placed around the plant and after a period of precipitation, rainwater was collected and analysed for tritium content. Samples were analysed using low-level liquid scintillation counting, with some also subject to the more accurate 3 He ingrowth method. The results clearly show the trace of the tritium plume emitted from the plant; however, values are only about one order of magnitude higher than environmental background levels. A washout model was devised to estimate the distribution of tritium around the plant. The model gives slightly higher concentrations than those measured in the field, but in general the agreement is satisfactory. The modelled values demonstrate that the effect of the plant on rainwater tritium levels is negligible over a distance of some kilometres. - Research highlights: →The rainwater around a nuclear power plant was collected with a special rainwater collector →The rainwater after a rain event was analysed for tritium with LSC and with the helium ingrowth method. →The trace of the tritium plume is clearly detectable in the rainwater. →The agreement between a reversible washout model and experimental data is satisfactory. →According to the model the tritium plume is hardly detectable over some kilometers from the plant

  7. Experimental investigation and modelling of tritium washout by precipitation in the area of the nuclear power plant of Paks, Hungary

    Energy Technology Data Exchange (ETDEWEB)

    Koello, Z., E-mail: kolloz42@gmail.co [Hertelendi Laboratory of Environmental Studies, Institute of Nuclear Research of the Hungarian Academy of Sciences, Bem ter 18/c, Debrecen 4026 (Hungary); Palcsu, L.; Major, Z.; Papp, L.; Molnar, M. [Hertelendi Laboratory of Environmental Studies, Institute of Nuclear Research of the Hungarian Academy of Sciences, Bem ter 18/c, Debrecen 4026 (Hungary); Ranga, T.; Dombovari, P.; Manga, L. [Department of Radiation Protection, Nuclear Power Plant of Paks, Paks (Hungary)

    2011-01-15

    Tritium occurs in nature in trace amounts, but its concentration is changing due to natural and artificial sources. Studies focusing on natural tritium have to take into account the effect of artificial sources. Also, the impact of tritium is an important issue in environmental protection, e.g. in connection with the emissions from nuclear power plants. The present work focuses on the rain washout of tritium emitted from the Paks nuclear power plant in Hungary. Rainwater collectors were placed around the plant and after a period of precipitation, rainwater was collected and analysed for tritium content. Samples were analysed using low-level liquid scintillation counting, with some also subject to the more accurate {sup 3}He ingrowth method. The results clearly show the trace of the tritium plume emitted from the plant; however, values are only about one order of magnitude higher than environmental background levels. A washout model was devised to estimate the distribution of tritium around the plant. The model gives slightly higher concentrations than those measured in the field, but in general the agreement is satisfactory. The modelled values demonstrate that the effect of the plant on rainwater tritium levels is negligible over a distance of some kilometres. - Research highlights: {yields}The rainwater around a nuclear power plant was collected with a special rainwater collector {yields}The rainwater after a rain event was analysed for tritium with LSC and with the helium ingrowth method. {yields}The trace of the tritium plume is clearly detectable in the rainwater. {yields}The agreement between a reversible washout model and experimental data is satisfactory. {yields}According to the model the tritium plume is hardly detectable over some kilometers from the plant

  8. Proposal of experimental facilities for studies of nuclear data and radiation engineering in the Intense Proton Accelerator Project

    CERN Document Server

    Baba, M; Nagai, Y; Ishibashi, K

    2003-01-01

    A proposal is given on the facilities and experiments in the Intense Proton Accelerator Project (J-PARC) relevant to the nuclear data and radiation engineering, nuclear astrophysics, nuclear transmutation, accelerator technology and space technology and so on. (3 refs).

  9. Experimental investigations of radiological and nuclear functional diagnosis of the ureter

    International Nuclear Information System (INIS)

    Wolf, M.

    1980-01-01

    A new nuclear method for reflux and motility investigations of the ureter is described, and its diagnostic potential is determined in model experiments. Thresholds of visualisation of a urine spindle are considered. The following results were obtained in animal experiments: 1) If investigations are repeated under identical conditions, there are considerable variations of refluxivity. 2) With IMCU (Isotope Micturition Cystoureterogram), the number of refluxes detected is about the same as with MCU (Micturition Cystoureterogram); this applies in particular to refluxes of the 3rd and 4th degree. 3) UKG is equal to AUR in judging the direction, time, velocity and frequency of discharge of a spindle while thickness and initial conus lenght of a spindle are better seen in AUR. 4) Inconstant depots of residual urine can be detected by UKG an AUR alike. The radiological observations made in the animal experiment are compared with the relevant literature, and possible error sources in the evaluation are indicated. Finally, the application of IMCU and UKG in humans is described. IMCU is recommended especially for pardiatric applications as the observation time is long and radiation exposure low. In renal function studies, the UKG supplies extensive information on functional data of the ureter which until now could be obtained only with the aid of contrast media. (orig./MG) [de

  10. An experimental and analytical investigation of water chillers of nuclear power plant

    International Nuclear Information System (INIS)

    Wang Chunming

    2005-01-01

    Water chillers are important components of the electric building chilled water system of Nuclear Power Plant. In this article, we describe the seismic qualification methodology. A united method of seismic analysis and experiment testing were applied. Since the seismic classification of the evaporator, condenser and oil separator is 1F, the function criteria are necessary to be satisfied. The functional and performance of the control panel were qualified by seismic test. In order to get the seismic time histories of the base of the motor, compressor and control panel, we did time histories analysis for the whole chillers using the seismic acceleration time history of the building floor on which the water chillers was located. Then, these curves were translated into required response spectrum (RRS), which were used by the seismic test of water chillers compressor sets. All passive components, such as evaporator, condenser, oil separator and support, were qualified by seismic stress analysis method. These components were verified to satisfy the standard when they were subjected to the seismic, gravitational, operational pressure and nozzle loads. The Chillers' components were qualified to the specification and the standard. The motor-compressor set and control panel were qualified to the functional and performance criteria. The applied of this methodology adequately qualified the function of the water chillers compressor sets , especially after the aging test. (authors)

  11. Experimental study on seismic behaviors of two-storied sophisticated model for nuclear reactor building

    Energy Technology Data Exchange (ETDEWEB)

    Higashiura, Akira; Sato, Kazuhide; Muramoto, Michiya; Yanagase, Takahito; Watanabe, Satoshi

    1987-03-01

    In this paper, by pseudo dynamic test using substructuring technique and lateral static loading test, authors wish to introduce the investigation on the seismic behaviors of nuclear reactor building. The results obtained by those test are as follows. 1) The maximum response displacements obtained by pseudo dynamic test are equivalent to those by dynamic analytical procedures using the approximate earthquake ground motion. 2) In the finally stage of pseudo dynamic test, the natural period of the system is increased about three times as long as that in elastic region. 3) Some shear cracks is observed on the web portion of the box and the truncated conical wall at the end of pseudo dynamic test. 4) Maximum shear forces in the test specimen obtained by pseudo dynamic test are about one third of the ultimate shear strength of it obtained by static loading test. 5) At the ultimate strength of the test specimen on static loading test, a lot of shear cracks and crush of concrete are observed on web portion of the box and the truncated conical wall.

  12. Research in experimental nuclear physics. Progress report, 1 April 1984-31 March 1985

    International Nuclear Information System (INIS)

    1984-11-01

    This report summarizes the work carried out by personnel from the University of Texas at Austin at the Los Alamos Clinton P. Anderson Meson Physics Facility (LAMPF) during the calendar year 1984. The research activities involved experiments done with the Energetic Pion Channel and Spectrometer (EPICS), the High Resolution Spectrometer (HRS), and some work has been done at Argonne National Laboratory and Kernforschungsanlage, Juelich, West Germany. A brief overview of work supported by this contract, a list of abstracts of papers reported at scientific meetings, and a list of published papers and preprints are given. These papers summarize experiments undertaken this year and in the proceeding year and indicate the work accomplished by the participants in this program of medium energy nuclear physics research. Studies include parameters of the neutron density distributions for the Ca isotopes for the analysis of π +- elastic scattering, the excitation of ΔS = 1 transitions via pion inelastic scattering in light nuclei, 12 C(π + ,π + ') inelastic scattering at very small angles, pion-induced double charge exchange reaction, and evidence for the population of a low-spin Δ-hole state at 248 MeV was found in 12 C via 13 C(p,d) 12 C* at 800 MeV

  13. Results of the power-up test of the nuclear-powered ship MUTSU and test programs of her experimental voyages

    International Nuclear Information System (INIS)

    Ochiai, Masa-aki; Ishida, Toshihisa; Itagaki, Masafumi; Sakamoto, Yukio; Kyouya, Masahiko

    1991-01-01

    The power-up test of N.S. MUTSU was performed successfully almost on schedule in spite of minor troubles resolved in a short time, and the results of various areas were satisfactory. The official sea trial was well carried out. Then, the ship was officially designated the first nuclear ship in Japan. Experimental voyages are to be performed to yield profitable data for further research on nuclear ships in the future. (author)

  14. EEG Analysis during complex diagnostic tasks in Nuclear Power Plants - Simulator-based Experimental Study

    International Nuclear Information System (INIS)

    Ha, Jun Su; Seong, Poong Hyun

    2005-01-01

    In literature, there are a lot of studies based on EEG signals during cognitive activities of human-beings but most of them dealt with simple cognitive activities such as transforming letters into Morse code, subtraction, reading, semantic memory search, visual search, memorizing a set of words and so on. In this work, EEG signals were analyzed during complex diagnostic tasks in NPP simulator-based environment. Investigated are the theta, alpha, beta, and gamma band EEG powers during the diagnostic tasks. The experimental design and procedure are represented in section 2 and the results are shown in section 3. Finally some considerations are discussed and the direction for the further work is proposed in section 4

  15. EEG Analysis during complex diagnostic tasks in Nuclear Power Plants - Simulator-based Experimental Study

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Jun Su; Seong, Poong Hyun [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2005-07-01

    In literature, there are a lot of studies based on EEG signals during cognitive activities of human-beings but most of them dealt with simple cognitive activities such as transforming letters into Morse code, subtraction, reading, semantic memory search, visual search, memorizing a set of words and so on. In this work, EEG signals were analyzed during complex diagnostic tasks in NPP simulator-based environment. Investigated are the theta, alpha, beta, and gamma band EEG powers during the diagnostic tasks. The experimental design and procedure are represented in section 2 and the results are shown in section 3. Finally some considerations are discussed and the direction for the further work is proposed in section 4.

  16. Fast instrumentation for loss of coolant accident (LOCA) experimental studies pertaining to nuclear reactors

    International Nuclear Information System (INIS)

    Venkat Raj, V.; Sreenivas Rao, G.; Belokar, D.G.; Dolas, P.K.

    1989-01-01

    The loss of coolant accident (LOCA) which involves a breach in the pressure boundary of the primary coolant system (PCS) is one of the postulated accident conditions against which the safety of the reactor system is to be ensured. Mathematical models have been developed to analyse this kind of transients. However, because of the extremely complicated nature of the phenomena involved, it is necessary to validate the analytical models with appropriate experimental data. Many parameters are to be measured during the experiments, out of which temperature, pressure, void fraction and two-phase mass flow rate are the most important parameters. Since the phenomenon is very fast, special fast response instruments are required. This paper deals with the considerations that govern the selection of appropriate instruments and the development of suitable instruments for transient two-phase flow and void fraction measurements. The requirements of the associated fast data acquisition system are also discussed. (author). 4 figs

  17. Structural, vibrational and nuclear magnetic resonance investigations of 4-bromoisoquinoline by experimental and theoretical DFT methods.

    Science.gov (United States)

    Arjunan, V; Thillai Govindaraja, S; Jayapraksh, A; Mohan, S

    2013-04-15

    Quantum chemical calculations of energy, structural parameters and vibrational wavenumbers of 4-bromoisoquinoline (4BIQ) were carried out by using B3LYP method using 6-311++G(**), cc-pVTZ and LANL2DZ basis sets. The optimised geometrical parameters obtained by DFT calculations are in good agreement with electron diffraction data. Interpretations of the experimental FTIR and FT-Raman spectra have been reported with the aid of the theoretical wavenumbers. The differences between the observed and scaled wavenumber values of most of the fundamentals are very small. The thermodynamic parameters have also been computed. Electronic properties of the molecule were discussed through the molecular electrostatic potential surface, HOMO-LUMO energy gap and NBO analysis. To provide precise assignments of (1)H and (13)CNMR spectra, isotropic shielding and chemical shifts were calculated with the Gauge-Invariant Atomic Orbital (GIAO) method. Copyright © 2013 Elsevier B.V. All rights reserved.

  18. The International Thermonuclear Experimental Reactor (ITER) international organisation: which laws apply to this international nuclear operator?

    International Nuclear Information System (INIS)

    Grammatico-Vidal, L.

    2009-01-01

    ITER is being carried out by way of international collaboration between seven partners (the European atomic energy community -EURATOM-, China, India, Japan, Russia, south korea and the United states) which together represent more than half the world population. From a project organisation point of view, it is supported by both financial and in-kind contributions provided by each of the partner; each member makes its contribution through a special legal entity called a 'domestic agency' to an international organisation which was set up by the Agreement on the Establishment of an International Fusion Energy Organization for the joint Implementation of the ITER project signed in Paris on 21. november 2006 and which entered into force on 24. october 2007 after ratification by each of the partners. The international agreement is to remain in effect for a period of 35 years and may be renewed for a period of 10 years without any change to its content. It is supplemented by an agreement of the same date on the privileges and immunities of the organisation and of its staff. The function of the ITER organisation is to construct, commission, operate and permanently shutdown the ITER facility, to encourage their exploitation by laboratories, other institutions and personnel participating in the fusion energy research and development programmes of its members and to promote public understanding and acceptance of fusion energy. The unique institutional structure for this project will be described briefly in the introduction before analysing the law applicable to this international organisation, a French nuclear operator, unique in France today. (N.C.)

  19. Relations between radiobiological hypoxia and nuclear magnetic resonance-imaged blood microcirculation in experimental tumors

    International Nuclear Information System (INIS)

    Koike, Sachiko; Ando, Koichi; Ikehira, Hiroo.

    1993-01-01

    Characteristics of hypoxic cells subjected to radiation were investigated and compared with those of microcirculation for two murine fibrosarcomas growing in C3H mice. Small NFSa tumors, growing in air-breathing mice, developed a radioresistant tail on the survival curve. The tail was indistinguishably parallel to a survival curve for an artificially hypoxic tumor. As the NFSa tumors increased in size, the hypoxic tail moved upward with no change of Do, resulting in increase of hypoxic fraction from 3.9% to 40%. The R1137 tumors had no radioresistant tail nor hypoxic fraction regardless of tumor size. However, large-sized R1137 tumors developed a significant number of radioresistant, hypoxic cells with an intermediate Do, and were effectively sensitized by administrating misonidazole before irradiation. Thus, the NFSa tumors were fractionally hypoxic, and the large R1137 tumors had intermediate hypoxia. Measurement of tumor microcirculation by gadolinium-enhanced nuclear magnetic resonance indicated that both blood flow and blood volume decreased significantly when the NFSa tumor grew large. Similar reduction in these microcirculation parameters was also observed for the R1137 tumor. The small-sized NFSa tumor had relatively larger blood volume and faster blood flow than the small-sized R1137 tumor. When large-sized tumors were compared to each other, the NFSa again had better blood flow than the R1137. However, the blood volume in the large-sized tumors was significantly (p<0.05) smaller for the NFSa tumor than for the R1137 tumor. It was concluded that blood flow could not be a single determinant for tumor hypoxia, and the difference between fractional hypoxia and intermediate hypoxia would be reflected in the ratio of blood flow to blood volume. (author)

  20. Experimental investigation on molten pool representing corium composition at Fukushima Daiichi nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    An, Sang Mo, E-mail: sangmoan@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yueong-gu, Daejeon, 305-353 (Korea, Republic of); Song, Jin Ho [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yueong-gu, Daejeon, 305-353 (Korea, Republic of); Kim, Jong-Yun [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yueong-gu, Daejeon, 305-353 (Korea, Republic of); Radiochemistry & Nuclear Nonproliferation, University of Science & Technology, Gajeong-ro 217, Yuseong-gu, Daejeon, 34113 (Korea, Republic of); Kim, HwanYeol [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yueong-gu, Daejeon, 305-353 (Korea, Republic of); Naitoh, Masanori [The Institute of Applied Energy, 1-14-2 Nishi-shimbashi, 1-Chome, Minato-ku, Tokyo, 105-0003 (Japan)

    2016-09-15

    A configuration of molten core in the Fukushima Daiichi NPP (nuclear power plant) was investigated by a melting and solidification experiment. About 5 kg of a mixture, whose composition in terms of weight is UO{sub 2} (60%), Zr + ZrO{sub 2} (25%), stainless steel (14%), B{sub 4}C (1%), was melted in a cold crucible using an induction heating technique. It was shown that the solidified melt consists of upper crust and lower solidified ingot. The solidified ingot was separated into two layers. A physical and chemical analysis was performed for the samples taken from the solidified melt to investigate the morphology and chemical characteristics. It was found that the solidified ingot consists of a metal-rich layer on the top and an oxide-rich layer at the bottom. In addition, the oxide layer at the bottom has composition close to the initial charge composition and surrounded by a thin crust layer. It turned out that B{sub 4}C was more concentrated in the upper metal-rich layer. These findings provide important insights for understanding the core melt progression and taking proper post-accident recovery actions for the Fukushima Daiichi NPP. - Highlights: • A configuration of molten core in the Fukushima Daiich NPP unit 1 is investigated. • Corium ingot consists of metallic layer on the top and oxidic layer at the bottom. • Boron carbide was more concentrated in the upper metallic layer. • Two layered configuration would contribute to the post-accident recovery actions.

  1. Experimental results from pressure testing a 1:6-scale nuclear power plant containment

    International Nuclear Information System (INIS)

    Horschel, D.S.

    1992-01-01

    This report discusses the testing of a 1:6-scale, reinforced-concrete containment building at Sandia National Laboratories, in Albuquerque, New Mexico. The scale-model, Light Water Reactor (LWR) containment building was designed and built to the American Society of Mechanical Engineers (ASME) code by United Engineers and Constructors, Inc., and was instrumented with over 1200 transducers to prepare for the test. The containment model was tested to failure to determine its response to static internal overpressurization. As part of the US Nuclear Regulatory Commission's program on containment integrity, the test results will be used to assess the capability of analytical methods to predict the performance of containments under severe-accident loads. The scaled dimensions of the cylindrical wall and hemispherical dome were typical of a full-size containment. Other typical features included in the heavily reinforced model were equipment hatches, personnel air locks, several small piping penetrations, and a ihin steel liner that was attached to the concrete by headed studs. In addition to the transducers attached to the model, an acoustic detection system and several video and still cameras were used during testing to gather data and to aid in the conduct of the test. The model and its instrumentation are briefly discussed, and is followed by the testing procedures and measured response of the containment model. A summary discussion is included to aid in understanding the significance of the test as it applies to real world reinforced concrete containment structures. The data gathered during SIT and overpressure testing are included as an appendix

  2. Experimental results from pressure testing a 1:6-scale nuclear power plant containment

    Energy Technology Data Exchange (ETDEWEB)

    Horschel, D.S. [Sandia National Labs., Albuquerque, NM (United States)

    1992-01-01

    This report discusses the testing of a 1:6-scale, reinforced-concrete containment building at Sandia National Laboratories, in Albuquerque, New Mexico. The scale-model, Light Water Reactor (LWR) containment building was designed and built to the American Society of Mechanical Engineers (ASME) code by United Engineers and Constructors, Inc., and was instrumented with over 1200 transducers to prepare for the test. The containment model was tested to failure to determine its response to static internal overpressurization. As part of the US Nuclear Regulatory Commission`s program on containment integrity, the test results will be used to assess the capability of analytical methods to predict the performance of containments under severe-accident loads. The scaled dimensions of the cylindrical wall and hemispherical dome were typical of a full-size containment. Other typical features included in the heavily reinforced model were equipment hatches, personnel air locks, several small piping penetrations, and a ihin steel liner that was attached to the concrete by headed studs. In addition to the transducers attached to the model, an acoustic detection system and several video and still cameras were used during testing to gather data and to aid in the conduct of the test. The model and its instrumentation are briefly discussed, and is followed by the testing procedures and measured response of the containment model. A summary discussion is included to aid in understanding the significance of the test as it applies to real world reinforced concrete containment structures. The data gathered during SIT and overpressure testing are included as an appendix.

  3. Experimental and modelling studies of iodine oxide formation and aerosol behaviour relevant to nuclear reactor accidents

    International Nuclear Information System (INIS)

    Dickinson, S.; Auvinen, A.; Ammar, Y.; Bosland, L.; Clément, B.; Funke, F.; Glowa, G.; Kärkelä, T.; Powers, D.A.; Tietze, S.; Weber, G.; Zhang, S.

    2014-01-01

    Highlights: • Radiolytic reactions can influence iodine volatility following a nuclear accident. • Kinetic models have been developed based on atmospheric chemistry studies. • Properties of iodine oxide aerosols produced by radiation have been measured. • Decomposition of iodine oxides by the action of heat or radiation has been observed. - Abstract: Plant assessments have shown that iodine contributes significantly to the source term for a range of accident scenarios. Iodine has a complex chemistry that determines its chemical form and, consequently, its volatility in the containment. If volatile iodine species are formed by reactions in the containment, they will be subject to radiolytic reactions in the atmosphere, resulting in the conversion of the gaseous species into involatile iodine oxides, which may deposit on surfaces or re-dissolve in water pools. The concentration of airborne iodine in the containment will, therefore, be determined by the balance between the reactions contributing to the formation and destruction of volatile species, as well as by the physico-chemical properties of the iodine oxide aerosols which will influence their longevity in the atmosphere. This paper summarises the work that has been done in the framework of the EC SARNET (Severe Accident Research Network) to develop a greater understanding of the reactions of gaseous iodine species in irradiated air/steam atmospheres, and the nature and behaviour of the reaction products. This work has mainly been focussed on investigating the nature and behaviour of iodine oxide aerosols, but earlier work by members of the SARNET group on gaseous reaction rates is also discussed to place the more recent work into context

  4. The mechanisms of the hadron-nucleus collision processes and of the hadron-nucleus collision induced nuclear reactions - in the light of experimental data

    International Nuclear Information System (INIS)

    Strugalski, Z.; Strugalska-Gola, E.

    1997-01-01

    The mechanisms of the hadron-nucleus collision processes and of the hadron-nucleus collision induced nuclear reactions are described - as experimentally based. The target nuclei are damaged definitely and locally in the collisions and the configurations of the nucleons in them became instable. The configuration must transit into stable stages of the nuclear transition reaction products. The difference between the initial internal energy of the unstable residual nucleus and the total final energy of the stable products of the nuclear transition reaction may be released in some cases

  5. Experimental study of space dependent nuclear reactor kinetics - Progress report; Eksperimentalno proucavanje prostorno zavisne kinetike nuklearnih reaktora - Izvestaj o napredovanju

    Energy Technology Data Exchange (ETDEWEB)

    Obradovic, D; Petrovic, M [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-11-15

    This paper describes experimental study of space-time behaviour of nuclear reactors by local complex-periodic perturbation of the absorption cross section and by measuring the local reactor response to this perturbation. Perturbation was done by BOR-1 fast oscillator. Cross correlation between the response and the perturbation was done numerically after completing the measurement by using digital computer. Obtained experimental results are preliminary and are measured with significant errors which were analysed in this paper. Results show qualitative agreement with those obtained by theoretical model. This paper is the first progress report in this field in our country. U radu je opisan eksperimentalni prilaz proucavanju prostorno-vremenskog ponasanja nuklearnih reaktora, vrseci lokalnu slozeno-periodicnu perturbaciju apsorpcionog preseka i mereci lokalni odziv reaktora na tu perturbaciju. Perturbacija je vrsena brzim oscilatorom BOR-1. Kroskorelacija izmedju odziva i perturbacije vrsena je numericki posle obavljenog merenja upotrebom digitalne racunske masine. Dobijeni eksperimentalni rezultati imaju preliminarni karakter i odredjeni su sa znatnim eksperimentalnim greskama koje su, u radu analizirane. Izlozeni rezultati pokazuju kvalitativna slaganja sa teorijski dobijenim modelom. Ovaj rad predstavlja prvi izvestaj o napredovanju na ovoj problematici kod nas (author)

  6. Experimental determination of nuclear reaction rates (n,γ) by the gamma-rays capture spectrometry technique

    International Nuclear Information System (INIS)

    Lucatero, M.A.

    1976-01-01

    The technique of the gamma-rays capture spectrometry was used in the experimental determination of nuclear reaction rates of the type (n,γ). This technique consists in the incidence of a thermal neutrons collimated beam upon a sample, detecting the capture spectrum of gamma rays emitted at a solid fixed angle. In the determination of the efficiency curve intrinsic to the detection electronic system the reactions 199 Hg(n,γ) 200 Hg, 56 Fe(n,γ) 57 Fe and 63 Cu(n,γ) 64 Cu were used with the energy of the gamma rays capture of 5.976, 7.635 and 7.915 Mev respectively, through the irradiation of standard samples of Hg(175.3g), Fe(110.4g) and Cu(108.5g) of cylindrical geometry the two former and parallelepiped the latter. The problem concerning the corrections due to the thermal neutrons flux depression, the gammas auto-attenuation, and the geometric factor due to the cylindrical and parallelepiped geometry are involved in the data process. The experimental determination of the reaction 35 Cl(n,γ) 36 Cl rate was made through the observation of the gamma caputre of 6.111 Mev when a sample of CaCl 2 of cylindrical geometry was irradiated. This rate can be favorably compared with the reaction rate determined theoretically. (author)

  7. Experimental and theoretical studies of nuclear generation of ozone from oxygen and oxygen--sulfur hexafluoride mixtures

    International Nuclear Information System (INIS)

    Elsayed-Ali, H.E.; Miley, G.H.

    1986-01-01

    A series of experimental measurements of the yield of O 3 in nuclear-induced O 2 and O 2 -SF 6 discharges are reported. The discharges were created by bombardment with energetic particles from the 10 B(n,α) 7 Li reaction. Continuous irradiation at dose rates of 10 15 --10 17 eV cm -3 s -1 and pulsed irradiation (--10 ms FWHM) at a peak dose rate of --10 20 eV cm -3 s -1 were conducted. At the lower dose rates, the addition of SF 6 generally increased the ozone yield due to the slowing of ozone destruction by negative oxygen and ozone ions. In contrast, at the high dose rates, the ozone concentration decreased due to SF 6 suppression of atomic oxygen formation by ion--ion recombination. A numerical model was developed and tested against experimental conditions. This model indicates that the steady-state ozone concentration was limited by the reaction O - 3 +O 3 →2O 2 +O - 2 with a rate coefficient of --1 x 10 -12 cm 3 s -1 . In addition to dose rate effects, pressure and temperature effects on ozone production are discussed and methods for increasing the ozone yield are suggested

  8. Experimental and theoretical studies of nuclear generation of ozone from oxygen and oxygen-sulfur hexafluoride mixtures

    Science.gov (United States)

    Elsayed-Ali, H. E.; Miley, G. H.

    1986-08-01

    A series of experimental measurements of the yield of O3 in nuclear-induced O2 and O2-SF6 discharges are reported. The discharges were created by bombardment with energetic particles from the 10B(n,α)7Li reaction. Continuous irradiation at dose rates of 1015-1017 eV cm-3 s-1 and pulsed irradiation (˜10 ms FWHM) at a peak dose rate of ˜1020 eV cm-3 s-1 were conducted. At the lower dose rates, the addition of SF6 generally increased the ozone yield due to the slowing of ozone destruction by negative oxygen and ozone ions. In contrast, at the high dose rates, the ozone concentration decreased due to SF6 suppression of atomic oxygen formation by ion-ion recombination. A numerical model was developed and tested against experimental conditions. This model indicates that the steady-state ozone concentration was limited by the reaction O-3+O3→2O2+O-2 with a rate coefficient of ˜1×10-12 cm3 s-1. In addition to dose rate effects, pressure and temperature effects on ozone production are discussed and methods for increasing the ozone yield are suggested.

  9. The Cyrano program. 1 - description and operation of an irradiation device 'Cyrano'. 2 - results of the experiments Cyrano 1 and 2 (study of the EL 4 first-bach pencil); measurement of the thermal conductivity integral for UO{sub 2} sintered up to 2300 deg C; evolution of fission gases at constant power; Programme Cyrano. 1 - description et exploitation d'un dispositif d'irradiation ''cyrano''. 2 - resultats des experiences cyrano 1 et 2 (etude du crayon EL4 1. jeu). Mesure de l'integrale de conductibilite thermique d'UO{sub 2} fritte jusqu'a 2300 deg C. Evolution des gaz de fission a puissance constante

    Energy Technology Data Exchange (ETDEWEB)

    Stora, J P; Chenebault, P [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires

    1968-07-01

    Two rods of the type 'EL 4 first score' have been irradiated in 'Cyrano' capsules which are suited for continuous measurement of the nuclear power evolved and equipped with thermocouples. The variations of the integral of conductivity of sintered 96 per cent theoretical dense UO{sub 2} has been established until 2300 deg. C; these variations are coherent with those previously measured out-of-pile. The released fission gases have been recovered at different times during the irradiation: the kinetics of release of stable gases is such that, in the experimental conditions (T{sub surface} = 610 deg. C, {integral}{sub T{sub s}}{sup T{sub c}} kdT = 34.7 W cm{sup -1}) the fraction of released gases is still widely increasing after 12 days of irradiation. Numerous observations have been made on concentrations of rare gases locally present in the irradiated fuel. (authors) [French] L'irradiation de deux crayons combustibles type EL 4, 1er jeu, a ete menee a bien dans des capsules 'Cyrano' equipees de dispositifs de mesure continue de la puissance nucleaire et de plusieurs reperes de temperatures; la variation de l'integrale de conductibilite thermique de l'oxyde d'uranium fritte (96 pour cent d. th.) a ete tracee jusqu'a 2300 deg. C; la courbe representative de ces variations est coherente avec celle obtenue precedemment hors pile. Les gaz de fission apparus hors du combustible ont ete extraits du crayon a plusieurs reprises pendant l'experience: la cinetique d'accumulation des gaz stables est telle que dans les conditions etudiees (T{sub surface} = 610 deg. C, {integral}{sub T{sub s}}{sup T{sub c}} kdT = 34.7 W cm{sup -1}) la fraction des gaz degages est encore largement croissante apres 12 jours d'irradiation. De nombreuses observations ont ete recueillies sur la nature et la concentration des gaz rares presents en differents points du combustible irradie. (auteurs)

  10. Experimental Methods to Estimate Accumulated Solids in Nuclear Waste Tanks - 13313

    Energy Technology Data Exchange (ETDEWEB)

    Duignan, Mark R.; Steeper, Timothy J.; Steimke, John L. [Savannah River Nuclear Solutions, Savannah River National Laboratory, Aiken, SC 29808 (United States)

    2013-07-01

    The Department of Energy has a large number of nuclear waste tanks. It is important to know if fissionable materials can concentrate when waste is transferred from staging tanks prior to feeding waste treatment plants. Specifically, there is a concern that large, dense particles, e.g., plutonium containing, could accumulate in poorly mixed regions of a blend tank heel for tanks that employ mixing jet pumps. At the request of the DOE Hanford Tank Operations Contractor, Washington River Protection Solutions, the Engineering Development Laboratory of the Savannah River National Laboratory performed a scouting study in a 1/22-scale model of a waste tank to investigate this concern and to develop measurement techniques that could be applied in a more extensive study at a larger scale. Simulated waste tank solids and supernatant were charged to the test tank and rotating liquid jets were used to remove most of the solids. Then the volume and shape of the residual solids and the spatial concentration profiles for the surrogate for plutonium were measured. This paper discusses the overall test results, which indicated heavy solids only accumulate during the first few transfer cycles, along with the techniques and equipment designed and employed in the test. Those techniques include: - Magnetic particle separator to remove stainless steel solids, the plutonium surrogate from a flowing stream. - Magnetic wand used to manually remove stainless steel solids from samples and the tank heel. - Photographs were used to determine the volume and shape of the solids mounds by developing a composite of topographical areas. - Laser range finders to determine the volume and shape of the solids mounds. - Core sampler to determine the stainless steel solids distribution within the solids mounds. - Computer driven positioner that placed the laser range finders and the core sampler over solids mounds that accumulated on the bottom of a scaled staging tank in locations where jet velocities

  11. An experimental technique for the modelling of air flow movements in nuclear plant

    International Nuclear Information System (INIS)

    Ainsworth, R.W.; Hallas, N.J.

    1986-01-01

    This paper describes an experimental technique developed at Harwell to model ventilation flows in plant at 1/5th scale. The technique achieves dynamic similarity not only for forced convection imposed by the plant ventilation system, but also for the interaction between natural convection (from heated objects) and forced convection. The use of a scale model to study flow of fluids is a well established technique, relying upon various criteria, expressed in terms of dimensionless numbers, to achieve dynamic similarity. For forced convective flows, simulation of Reynolds number is sufficient, but to model natural convection and its interaction with forced convection, the Rayleigh, Grashof and Prandtl numbers must be simulated at the same time. This paper describes such a technique, used in experiments on a hypothetical glove box cell to study the interaction between forced and natural convection. The model contained features typically present in a cell, such as a man, motor, stairs, glove box, etc. The aim of the experiment was to study the overall flow patterns, especially around the model man 'working' at the glove box. The cell ventilation was theoretically designed to produce a downward flow over the face of the man working at the glove box. However, the results have shown that the flow velocities produced an upwards flow over the face of the man. The work has indicated the viability of modelling simultaneously the forced and natural convection processes in a cell. It has also demonstrated that simplistic assumptions cannot be made about ventilation flow patterns. (author)

  12. Experimental studies on tungsten-armor impact on nuclear responses of solid breeding blanket

    International Nuclear Information System (INIS)

    Sato, S.; Nakao, M.; Verzilov, Y.; Ochiai, K.; Wada, M.; Kubota, N.; Kondo, K.; Yamauchi, M.; Enoeda, M.; Nishitani, T.

    2005-01-01

    In order to experimentally evaluate the tungsten armor impact on tritium production of the solid breeding blanket being developed by JAERI for tokamak-type DEMO reactors, neutronics integral experiments have been performed by using DT neutrons at Fusion Neutron Source (FNS) facility of JAERI. Solid breeding blanket mockups relevant to the DEMO blanket have been applied in this study. The mockups are constructed by a set of layers consisting of 0 - 25.2 mm thick tungsten, 16 mm thick F82H, 12 mm thick Li 2 TiO 3 and 100 - 200mm thick beryllium with cross-section of 660 x 660 mm in maximum. Pellets of Li 2 CO 3 are embedded inside the Li 2 TiO 3 layers to measure the tritium production rate. By installing the 5, 12.6 and 25.2 mm thick tungsten armors, sum of the integrated tritium productions at the pellets are reduced by about 2, 3 and 6 % relative to the case without the armor, respectively. Numerical calculations have been conducted using the Monte Carlo code. Calculation results for sum of the integrated tritium productions in the case with the tungsten armor agree well with the experiment data within 4% and 19% under condition without and with a neutron reflector, respectively. (author)

  13. Research on the improvement of nuclear safety -A study on the establishment of severe accident experimental facility-

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Kune Yull; Ryu, Keon Joong; Park, Chang Kyu; Sim, Seok Ku; Kim, Sang Baek; Nho, Ki Mann; Bang, Kwang Hyun; Park, Rae Jun; Lee, Seong Jae; Kang, Kyung Ho; Jo, Young Ro; Hong, Sung Wan; Jeong, Moon Ki; Park, Chun Kyung; Cheon, Se Young; Kim, In Sik; Moon, Sang Ki; Kim, Jong Hwan; Kim, Seong Ho; Sin, Ki Yeol; Cho, Jae Sun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    For the first phase (1992-1995) of the current research program under nuclear reactor safety enhancement project, the primary objective was placed on the development of an improved cavity design and on the improvement of theoretical models of the separate effects for major severe accident phenomena occurring in the reactor cavity. Also, during the fourth year of this project, small-scale experiments were performed to visualize the fundamental phenomena of boiling in narrow spaces that may exist between the debris crust and the reactor vessel lower head in preparation for the large-scale in-vessel cooling experiment planned for the second phase of the project (1996-2001). Separate effect tests have been performed during the first phase spanning the high pressure melt ejection (HPME) resulting in the direct containment heating (DCH), crust formation during cooling of the high temperature melt, fuel coolant interaction (FCI) in the process of injecting coolant onto the reactor cavity, and the molten core concrete interaction (MCCI). Some research programs were subcontracted with universities. Steam condensation on the containment inner wall was investigated by the POSTECH, while the experimental technique for the simultaneous measurement of particle size and velocity was developed by the KAIST. The second phase experimental projects center about the in-vessel accident management tests SONATA-IV (Simulation of Naturally Arrested Thermal Attack in Vessel) and ex-vessel accident management tests TOCATA-XV (Tests on Cavity Arrested Thermal Attack ex Vessel). In preparation for the second phase in-vessel experimental program, one of our research staff has participated in the PHEBUS-FP program in CEA Cadarache, France. Small-scale scoping tests were performed for the study of in-vessel cooling of debris in the lower head. (Abstract Truncated)

  14. Use of cadmium in solution in the EL 4 reactor moderator irreversible fixing of cadmium on the metallic surfaces; Utilisation du cadmium en solution dans le moderateur du reacteur EL 4 - fixation irreversible du cadmium sur les surfaces metalliques

    Energy Technology Data Exchange (ETDEWEB)

    Croix, O; Paoli, O; Lecomte, J; Dolle, L; Gallic, Y [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    In the framework of research into the poisoning of the EL-4 reactor by cadmium sulphate, measurements have been made by two different methods of the residual amounts of cadmium liable to be fixed irreversibly on the surfaces in contact with the heavy water. A marked influence of the pH has been noticed. The mechanism of the irreversible fixing is compatible with the hypothesis of an ion-exchange in the surface oxide layer. In a sufficiently wide range of pH the cadmium thus fixed causes very little residual poisoning. The stability of the cadmium sulphate solutions is however rather low in the conditions of poisoning. (authors) [French] Dans le cadre des etudes sur l'empoisonnement du reacteur EL-4 par le sulfate de cadmium, les quantites residuelles de cadmium susceptibles de se fixer irreversiblement sur les parois que mouillerait l'eau lourde, ont ete mesurees experimentalement par deux methodes differentes. On observe une influence nette du pH. Le mecanisme de la fixation irreversible est compatible avec l'hypothese d'un echange d'ions dans la pellicule d'oxyde superficielle. Dans des limites suffisamment larges de pH, la cadmium ainsi fixe n'occasionne pas d'empoisonnement residuel important. La stabilite des solutions de sulfate de cadmium dans les conditions de l'empoisonnement est cependant mediocre. (auteurs)

  15. Methods of Containment Adopted for the EL4 Reactor and Projected Heavy-Water, Gas-Cooled Plants; Mode de Confinement Adopte pour le Reacteur EL4 et les Projets de Centrales Eau Lourde-Gaz

    Energy Technology Data Exchange (ETDEWEB)

    Schulhof, P.; Justin, F. [Commissariat a l' Energie Atomique, Paris (France)

    1967-09-15

    After a brief description of the plant, the paper explains the principles adopted for preventing the release of waste gas, from the EL4 reactor and refers to some of the difficulties associated with this type of containment. From the economic standpoint, the authors present the results of a comparative civil engineering study of pre-stressed concrete and steel shells for a projected 60 MW(e) power station, giving various values for accidental pressures. They demonstrate the influence of the stress values adopted. (author) [French] Les auteurs rappellent les principes adoptes dans le reacteur EL4 pour le confinement des rejets gazeux, apres une description sommaire des installations. Suivent quelques aspects des difficultes introduites par ce type de confinement. Dans le domaine economique, ils presentent le resultat d'une etude comparative de genie civil d'enceintes en beton precontraint et en acier pour un projet de centrale de 600 MW(e), avec diverses valeurs de pression accidentelle. Dans cette etude, ils font ressortir l'influence des valeurs admises pour le taux de travail des materiaux. (author)

  16. Transfer of elements relevant to nuclear fuel cycle from soil to boreal plants and animals in experimental meso- and microcosms

    Energy Technology Data Exchange (ETDEWEB)

    Tuovinen, Tiina S., E-mail: tiina.tuovinen@uef.fi [Department of Environmental Science, University of Eastern Finland, P.O. Box 1627, FI-70211 Kuopio (Finland); Kasurinen, Anne; Häikiö, Elina [Department of Environmental Science, University of Eastern Finland, P.O. Box 1627, FI-70211 Kuopio (Finland); Tervahauta, Arja [Department of Biology, University of Eastern Finland, P.O. Box FI-70211, Kuopio (Finland); Makkonen, Sari; Holopainen, Toini; Juutilainen, Jukka [Department of Environmental Science, University of Eastern Finland, P.O. Box 1627, FI-70211 Kuopio (Finland)

    2016-01-01

    Uranium (U), cobalt (Co), molybdenum (Mo), nickel (Ni), lead (Pb), thorium (Th) and zinc (Zn) occur naturally in soil but their radioactive isotopes can also be released into the environment during the nuclear fuel cycle. The transfer of these elements was studied in three different trophic levels in experimental mesocosms containing downy birch (Betula pubescens), narrow buckler fern (Dryopteris carthusiana) and Scandinavian small-reed (Calamagrostis purpurea ssp. Phragmitoides) as producers, snails (Arianta arbostorum) as herbivores, and earthworms (Lumbricus terrestris) as decomposers. To determine more precisely whether the element uptake of snails is mainly via their food (birch leaves) or both via soil and food, a separate microcosm experiment was also performed. The element uptake of snails did not generally depend on the presence of soil, indicating that the main uptake route was food, except for U, where soil contact was important for uptake when soil U concentration was high. Transfer of elements from soil to plants was not linear, i.e. it was not correctly described by constant concentration ratios (CR) commonly applied in radioecological modeling. Similar nonlinear transfer was found for the invertebrate animals included in this study: elements other than U were taken up more efficiently when element concentration in soil or food was low. - Highlights: • We studied transfer of elements in boreal food chain using meso- and microcosms. • Elements related to nuclear fuel cycle and mining were examined. • Higher uptake at lower soil concentrations was observed for primary producers. • Snails took up elements mainly from food but for U also soil was an element source. • Non-linear transfer of essential elements was observed for herbivore and decomposer.

  17. Adaptive response of apoptosis in EL-4 lymphoma cells induced by low dose radiation and its mechanism

    International Nuclear Information System (INIS)

    Liu Shuchun; Gong Pingsheng; Wang Zhicheng; Sun Liguang; Gong Shouliang

    2008-01-01

    EL-4 lymphoma cells were irradiated with the inductive doses (D1: 25-200 mGy, dose rate: 12.5mGy/min) and the challenging dose (D2:0.5-3.0 Gy, dose rate: 287 mGy/min), and the time interval between D1 and D2 was 6 h. The percentage of cell apoptosis and the expressive levels of cell apoptosis-associated gene pro- reins were measured with flow cytometry. The percentages of cell apoptosis in the D1 + D2 group with 25-100 mGy (D1) and 1.5 Gy (D2) or 75 mGy (D1) and 25-200 mGy (D2) were significantly lower than those in the D2 group. As compared with the D2 group, the positive percentage of cell Bcl-2 protein expression increased somewhat, and Bax decreased significantly, meanwhile the ratio of Bcl-2/Bax increased significantly and p53 decreased somewhat in D1 + D2 group with 25-100 mGy (D1) and 1.5 Gy (D2). The adaptive response of EL-4 lymphoma cell apoptosis could be induced by pre-irradiation with 25-100 mGy. Meantime, the expressive levels of cell apoptosis-associated gene Bcl-2, Bax and p53 proteins could change accordingly with cell apoptosis. These gene protein changes may play an important role in the mechanism of the adaptive response. (authors)

  18. Effects of protein kinase C activators on phorbol ester-sensitive and -resistant EL4 thymoma cells.

    Science.gov (United States)

    Sansbury, H M; Wisehart-Johnson, A E; Qi, C; Fulwood, S; Meier, K E

    1997-09-01

    Phorbol ester-sensitive EL4 murine thymoma cells respond to phorbol 12-myristate 13-acetate with activation of ERK mitogen-activated protein kinases, synthesis of interleukin-2, and death, whereas phorbol ester-resistant variants of this cell line do not exhibit these responses. Additional aspects of the resistant phenotype were examined, using a newly-established resistant cell line. Phorbol ester induced morphological changes, ERK activation, calcium-dependent activation of the c-Jun N-terminal kinase (JNK), interleukin-2 synthesis, and growth inhibition in sensitive but not resistant cells. A series of protein kinase C activators caused membrane translocation of protein kinase C's (PKCs) alpha, eta, and theta in both cell lines. While PKC eta was expressed at higher levels in sensitive than in resistant cells, overexpression of PKC eta did not restore phorbol ester-induced ERK activation to resistant cells. In sensitive cells, PKC activators had similar effects on cell viability and ERK activation, but differed in their abilities to induce JNK activation and interleukin-2 synthesis. PD 098059, an inhibitor of the mitogen activated protein (MAP)/ERK kinase kinase MEK, partially inhibited ERK activation and completely blocked phorbol ester-induced cell death in sensitive cells. Thus MEK and/or ERK activation, but not JNK activation or interleukin-2 synthesis, appears to be required for phorbol ester-induced toxicity. Alterations in phorbol ester response pathways, rather than altered expression of PKC isoforms, appear to confer phorbol ester resistance to EL4 cells.

  19. Expression of insulin-like growth factor-2 receptors on EL4 lymphoma cells overexpressing growth hormone.

    Science.gov (United States)

    Farmer, John T; Weigent, Douglas A

    2007-01-01

    In the present study, we report the upregulation of functional IGF-2Rs in cells overexpressing growth hormone (GH). EL4 lymphoma cells stably transfected with an rGH cDNA overexpression vector (GHo) exhibited an increase in the binding of (125)I-IGF-2 with no change in the binding affinity compared to vector alone controls. An increase in the expression of the insulin-like growth factor-2 receptor (IGF-2R) in cells overexpressing GH was confirmed by Western blot analysis and IGF-2R promoter luciferase assays. EL4 cells produce insulin-like growth factor-2 (IGF-2) as detected by the reverse transcription-polymerase chain reaction (RT-PCR); however, no IGF-2 protein was detected by Western analysis. The increase in the expression of the IGF-2R resulted in greater levels of IGF-2 uptake in GHo cells compared to vector alone controls. The data suggest that one of the consequences of the overexpression of GH is an increase in the expression of the IGF-2R.

  20. Differential immunotoxic effects of ethanol on murine EL-4 lymphoma and normal lymphocytes is mediated through increased ROS production and activation of p38MAPK.

    Science.gov (United States)

    Premachandran, Sudha; Khan, Nazir M; Thakur, Vikas S; Shukla, Jyoti; Poduval, T B

    2012-08-01

    Ethanol has been used to achieve thymic depletion in myasthenia gravis patients. Ethanol (95%) has also been used widely in the therapy of many tumors including hepatocellular carcinoma. In light of these findings, we delineated the differential immunotoxic behavior and mechanism of lower concentration of ethanol towards murine EL-4 lymphoma and its normal counterpart lymphocytes. EL-4 lymphoma and normal lymphocytes were cultured with ethanol (0%-5%) for 6 h and cytotoxicity was measured by various methods. EL-4 cells treated with ethanol showed concentration-dependent loss of viability at 2%-5% ethanol concentration and exhibit proliferative arrest at preG1 stage. Acridine-orange and ethidium-bromide staining indicated that ethanol induced death in EL-4 cells, by induction of both apoptosis and necrosis which was further supported by findings of DNA-fragmentation and trypan blue dye exclusion test. However, treatment of lymphocytes with similar concentration of ethanol did not show any death-associated parameters. Furthermore, ethanol induced significantly higher ROS generation in EL-4 cells as compared to lymphocytes and caused PARP cleavage and activation of apoptotic proteins like p53 and Bax, in EL-4 cells and not in normal lymphocytes. In addition, ethanol exposure to EL-4 cells led to phosphorylation of p38MAPK, and upregulation of death receptor Fas (CD95). Taken together, these results suggest that ethanol upto a concentration of 5% caused no significant immunotoxicity towards normal lymphocytes and induced cell death in EL-4 cells via phosphorylation of p38MAPK and regulation of p53 leading to further activation of both extrinsic (Fas) and intrinsic (Bax) apoptotic markers.

  1. Effects of phorbol ester on mitogen-activated protein kinase kinase activity in wild-type and phorbol ester-resistant EL4 thymoma cells.

    Science.gov (United States)

    Gause, K C; Homma, M K; Licciardi, K A; Seger, R; Ahn, N G; Peterson, M J; Krebs, E G; Meier, K E

    1993-08-05

    Phorbol ester-sensitive and -resistant EL4 thymoma cell lines differ in their ability to activate mitogen-activated protein kinase (MAPK) in response to phorbol ester. Treatment of wild-type EL4 cells with phorbol ester results in the rapid activations of MAPK and pp90rsk kinase, a substrate for MAPK, while neither kinase is activated in response to phorbol ester in variant EL4 cells. This study examines the activation of MAPK kinase (MAPKK), an activator of MAPK, in wild-type and variant EL4 cells. Phosphorylation of a 40-kDa substrate, identified as MAPK, was observed following in vitro phosphorylation reactions using cytosolic extracts or Mono Q column fractions prepared from phorbol ester-treated wild-type EL4 cells. MAPKK activity coeluted with a portion of the inactive MAPK upon Mono Q anion-exchange chromatography, permitting detection of the MAPKK activity in fractions containing both kinases. This MAPKK activity was present in phorbol ester-treated wild-type cells, but not in phorbol ester-treated variant cells or in untreated wild-type or variant cells. The MAPKK from wild-type cells was able to activate MAPK prepared from either wild-type or variant cells. MAPKK activity could be stimulated in both wildtype and variant EL4 cells in response to treatment of cells with okadaic acid. These results indicate that the failure of variant EL4 cells to activate MAP kinase in response to phorbol ester is due to a failure to activate MAPKK. Therefore, the step that confers phorbol ester resistance to variant EL4 cells lies between the activation of protein kinase C and the activation of MAPKK.

  2. TNF induction of EL4 hyposensitivity to lysis by recombinant (soluble) and membrane-associated TNFs: TNF binding, internalization, and degradation.

    Science.gov (United States)

    Fishman, M; Costlow, M

    1994-04-01

    EL4 mouse thymoma cells sensitive to TNF-mediated lysis only in the presence of cycloheximide (S-EL4) or in the presence or absence of cycloheximide (N-EL4) were used in these experiments. Murine tumor cell line (S-EL4) sensitivity to TNF cytotoxicity is augmented when cycloheximide is added together with TNF or when cycloheximide is added 1 hr before or after TNF. No enhanced sensitivity is observed when target cells are incubated with cycloheximide 2-4 hr before or after the addition of TNF. In the absence of cycloheximide, S-EL4 cells preexposed to murine TNF are less susceptible to lysis by TNF and TNF receptor-conjugated TNF but are lysed by integral membrane TNF. TNF-induced hyposensitivity is partially reversed by actinomycin D or by culturing the preexposed cells for 4 hr prior to TNF lytic assay. TNF preincubation of N- and S-EL4 cells results in an immediate decrease in 125I-TNF binding due to TNF receptor occupancy. Recovery of TNF-R occupancy and TNF internalization were subsequently noted.

  3. Experimental study on the heat transfer characteristics of a nuclear reactor containment wall cooled by gravitationally falling water

    Science.gov (United States)

    Pasek, Ari D.; Umar, Efrison; Suwono, Aryadi; Manalu, Reinhard E. E.

    2012-06-01

    Gravitationally falling water cooling is one of mechanism utilized by a modern nuclear Pressurized Water Reactor (PWR) for its Passive Containment Cooling System (PCCS). Since the cooling is closely related to the safety, water film cooling characteristics of the PCCS should be studied. This paper deals with the experimental study of laminar water film cooling on the containment model wall. The influences of water mass flow rate and wall heat rate on the heat transfer characteristic were studied. This research was started with design and assembly of a containment model equipped with the water cooling system, and calibration of all measurement devices. The containment model is a scaled down model of AP 1000 reactor. Below the containment steam is generated using electrical heaters. The steam heated the containment wall, and then the temperatures of the wall in several positions were measure transiently using thermocouples and data acquisition. The containment was then cooled by falling water sprayed from the top of the containment. The experiments were done for various wall heat rate and cooling water flow rate. The objective of the research is to find the temperature profile along the wall before and after the water cooling applied, prediction of the water film characteristic such as means velocity, thickness and their influence to the heat transfer coefficient. The result of the experiments shows that the wall temperatures significantly drop after being sprayed with water. The thickness of water film increases with increasing water flow rate and remained constant with increasing wall heat rate. The heat transfer coefficient decreases as film mass flow rate increase due to the increases of the film thickness which causes the increasing of the thermal resistance. The heat transfer coefficient increases slightly as the wall heat rate increases. The experimental results were then compared with previous theoretical studied.

  4. Ghrelin ameliorates intestinal barrier dysfunction in experimental colitis by inhibiting the activation of nuclear factor-kappa B

    International Nuclear Information System (INIS)

    Cheng, Jian; Zhang, Lin; Dai, Weiqi; Mao, Yuqing; Li, Sainan; Wang, Jingjie; Li, Huanqing; Guo, Chuanyong; Fan, Xiaoming

    2015-01-01

    Aim: This study aimed to investigate the effect and underlying mechanism of ghrelin on intestinal barrier dysfunction in dextran sulfate sodium (DSS)-induced colitis. Methods and results: Acute colitis was induced in C57BL/6J mice by administering 2.5% DSS. Saline or 25, 125, 250 μg/kg ghrelin was administrated intraperitoneally (IP) to mice 1 day before colitis induction and on days 4, 5, and 6 after DSS administration. IP injection of a ghrelin receptor antagonist, [D-lys 3 ]-GHRP-6, was performed immediately prior to ghrelin injection. Ghrelin (125 or 250 μg/kg) could reduce the disease activity index, histological score, and myeloperoxidase activities in experimental colitis, and also prevented shortening of the colon. Ghrelin could prevent the reduction of transepithelial electrical resistance and tight junction expression, and bolstered tight junction structural integrity and regulated cytokine secretion. Ultimately, ghrelin inhibited nuclear factor kappa B (NF-κB), inhibitory κB-α, myosin light chain kinase, and phosphorylated myosin light chain 2 activation. Conclusions: Ghrelin prevented the breakdown of intestinal barrier function in DSS-induced colitis. The protective effects of ghrelin on intestinal barrier function were mediated by its receptor GHSR-1a. The inhibition of NF-κB activation might be part of the mechanism underlying the effects of ghrelin that protect against barrier dysfunction. - Highlights: • Ghrelin ameliorates intestinal barrier dysfunction in experimental colitis. • The effect of ghrelin is mediated by GHSR-1a. • Inhibition of NF-κB activation

  5. Ghrelin ameliorates intestinal barrier dysfunction in experimental colitis by inhibiting the activation of nuclear factor-kappa B

    Energy Technology Data Exchange (ETDEWEB)

    Cheng, Jian; Zhang, Lin [Department of Gastroenterology, Jinshan Hospital of Fudan University, Shanghai (China); Dai, Weiqi [Department of Gastroenterology, Shanghai Tenth People' s Hospital, Tongji University, Shanghai (China); Mao, Yuqing [Department of Gastroenterology, Jinshan Hospital of Fudan University, Shanghai (China); Li, Sainan [Department of Gastroenterology, Shanghai Tenth People' s Hospital, Tongji University, Shanghai (China); Wang, Jingjie; Li, Huanqing [Department of Gastroenterology, Jinshan Hospital of Fudan University, Shanghai (China); Guo, Chuanyong [Department of Gastroenterology, Shanghai Tenth People' s Hospital, Tongji University, Shanghai (China); Fan, Xiaoming, E-mail: xiaomingfan57@sina.com [Department of Gastroenterology, Jinshan Hospital of Fudan University, Shanghai (China)

    2015-02-27

    Aim: This study aimed to investigate the effect and underlying mechanism of ghrelin on intestinal barrier dysfunction in dextran sulfate sodium (DSS)-induced colitis. Methods and results: Acute colitis was induced in C57BL/6J mice by administering 2.5% DSS. Saline or 25, 125, 250 μg/kg ghrelin was administrated intraperitoneally (IP) to mice 1 day before colitis induction and on days 4, 5, and 6 after DSS administration. IP injection of a ghrelin receptor antagonist, [D-lys{sup 3}]-GHRP-6, was performed immediately prior to ghrelin injection. Ghrelin (125 or 250 μg/kg) could reduce the disease activity index, histological score, and myeloperoxidase activities in experimental colitis, and also prevented shortening of the colon. Ghrelin could prevent the reduction of transepithelial electrical resistance and tight junction expression, and bolstered tight junction structural integrity and regulated cytokine secretion. Ultimately, ghrelin inhibited nuclear factor kappa B (NF-κB), inhibitory κB-α, myosin light chain kinase, and phosphorylated myosin light chain 2 activation. Conclusions: Ghrelin prevented the breakdown of intestinal barrier function in DSS-induced colitis. The protective effects of ghrelin on intestinal barrier function were mediated by its receptor GHSR-1a. The inhibition of NF-κB activation might be part of the mechanism underlying the effects of ghrelin that protect against barrier dysfunction. - Highlights: • Ghrelin ameliorates intestinal barrier dysfunction in experimental colitis. • The effect of ghrelin is mediated by GHSR-1a. • Inhibition of NF-κB activation.

  6. [The assessment of radionuclide contamination and toxicity of soils sampled from "experimental field" site of Semipalatinsk nuclear test site].

    Science.gov (United States)

    Evseeva, T I; Maĭstrenko, T A; Belykh, E S; Geras'kin, S A; Kriazheva, E Iu

    2009-01-01

    Large-scale maps (1:25000) of soil contamination with radionuclides, lateral distribution of 137Cs, 90Sr, Fe and Mn water-soluble compounds and soil toxicity in "Experimental field" site of Semipalatinsk nuclear test site were charted. At present soils from studied site (4 km2) according to basic sanitary standards of radiation safety adopted in Russian Federation (OSPORB) do not attributed to radioactive wastes with respect to data on artificial radionuclide concentration, but they do in compliance with IAEA safety guide. The soils studied can not be released from regulatory control due to radioactive decay of 137Cs and 90Sr and accumulation-decay of 241Am up to 2106 year according to IAEA concept of exclusion, exemption and clearance. Data on bioassay "increase of Chlorella vulgaris Beijer biomass production in aqueous extract from soils" show that the largest part of soils from the studied site (74%) belongs to stimulating or insignificantly influencing on the algae reproduction due to water-soluble compounds effect. Toxic soils occupy 26% of the territory. The main factors effecting the algae reproduction in the aqueous extracts from soil are Fe concentration and 90Sr specific activity: 90Sr inhibits but Fe stimulates algae biomass production.

  7. Enhancement of the power system efficiency using the hybrid-type harmonic filters for a KSTAR nuclear fusion experimental system

    International Nuclear Information System (INIS)

    Yoon, Dong-Hee; Lee, Hansang; Park, Byungju; Jang, Gilsoo

    2011-01-01

    Highlights: → The low power factor and power quality problems are occurred by the operation of the PF facility in KSTAR system. We model the power system of KSTAR system including the PF facility. We show a method of the filter insertion to improve the problem and conduct the simulations to verify our method. - Abstract: The KSTAR system, which includes a large amount of nonlinear load, is a relatively high reactive power consumption load which injects harmonic currents into the power system which could result in the possibility for a power system perturbation to occur in the transmission lines, affecting nearby customers. In order to maintain the power quality and power factor in the inner system of the KSTAR system and the adjacent distribution lines, the assessment of the effect of the DC power supply in the KSTAR system is required for appropriate countermeasures to be put in place. In this paper, on the basis of a preliminary inspection of the power system near a KSTAR system, the simulation of a compensating device is performed for the prevention of abnormal voltage variations caused by a large amount of reactive and nonlinear load. In addition, through the comparison of the pre- and post-application of compensation devices in the actual power system, it is verified that a stable operation of the KSTAR nuclear fusion experimental system can be achieved.

  8. Zirconium and Yttrium (p, d) Surrogate Nuclear Reactions: Measurement and determination of gamma-ray probabilities: Experimental Physics Report

    Energy Technology Data Exchange (ETDEWEB)

    Burke, J. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hughes, R. O. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Escher, J. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Scielzo, N. D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Casperson, R. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ressler, J. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Saastamoinen, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ota, S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Park, H. I. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ross, T. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McCleskey, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McCleskey, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Austin, R. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Rapisarda, G. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-09-21

    This technical report documents the surrogate reaction method and experimental results used to determine the desired neutron induced cross sections of 87Y(n,g) and the known 90Zr(n,g) cross section. This experiment was performed at the STARLiTeR apparatus located at Texas A&M Cyclotron Institute using the K150 Cyclotron which produced a 28.56 MeV proton beam. The proton beam impinged on Y and Zr targets to produce the nuclear reactions 89Y(p,d)88Y and 92Zr(p,d)91Zr. Both particle singles data and particle-gamma ray coincident data were measured during the experiment. This data was used to determine the γ-ray probability as a function of energy for these reactions. The results for the γ-ray probabilities as a function of energy for both these nuclei are documented here. For completeness, extensive tabulated and graphical results are provided in the appendices.

  9. Study on some experimental conditions that affect corrosion of some structural steel materials using in nuclear power plant

    International Nuclear Information System (INIS)

    Hoang Nhuan; Nguyen Thi Kim Dung; Hoang Xuan Thi; Nguyen Thi Thuc Phuong; Ngo Xuan Hung; Nguyen Thanh Chung; Tran Xuan Vinh; Hoang Van Duc; Hoang Thi Tuyen; Nguyen Duc Thang

    2017-01-01

    The corrosion cracking of stainless steels is an important degradation phenomenon not only in nuclear reactors but also in the other industrial factories. In this work, experimental research of mechanical properties and electro-chemical processes to degradation of carbon steel and SS304 was carried out. Hardness values, ultimate tensile strength, yield strength, elongation values and impact energy which are typical for material mechanical properties were measured. When changing heat treatment conditions, the differences of mechanical properties were not really significant. In electro-chemical experiments, the OCP results of C45 steel and 304 Stainless Steel in Cl - environment took initial assessment of corrosion process. The corrosion process of C45 was accelerated over Cl - concentration. In the case of 304 Stainless Steel, Cl - ions did not significantly affect corrosion process, only slowed down the formation of the chromium oxide layer on the SS304 surface. In the last section, experiments were conducted to get a procedure on the determination of 10 B/ 11 B isotope ratio in water samples by isotope dilution – inductively coupled plasma mass spectrometry. (author)

  10. Analysis on Propagation Characteristics and Experimental Verification of A1 Circumferential Waves in Nuclear Fuel Rods Coated with Oxide Layers

    International Nuclear Information System (INIS)

    Joo, Young Sang; Jung, Hyun Kyu; Cheong, Yong Moo; Ih, Jeong Guon

    1999-01-01

    The resonance scattering of acoustic waves from the cylindrical shells of nuclear fuel rods coated with oxide layers has been theoretically modeled and numerically analyzed for the propagation characteristics of the circumferential waves. The normal mode solutions of the scattering pressure of the coated shells have been obtained. The pure resonance components have been isolated using the newly proposed inherent background coefficients. The propagation characteristics of resonant circumferential waves for the shells coated with oxide layers are affected by the presence and the thickness of an oxide layer. The characteristics have been experimentally confirmed through the method of isolation and identification of resonances. The change of the phase velocity of the A 1 circumferential wave mode for the coated shell is negligible at the specified partial waves in spite of the presence of the oxide layer and the increase in coating thickness. Utilizing the invariability characteristics of the phase velocity of the A 1 mode, the oxide layer thickness of the coated shells can be estimated. A new nondestructive technique for the relative measurement of the coating thickness of coated shells has been proposed

  11. Thermal, chemical, and mass transport processes induced in abyssal sediments by the emplacement of nuclear wastes: Experimental and modelling results

    International Nuclear Information System (INIS)

    McVey, D.F.; Erickson, K.L.; Seyfried, W.E. Jr.

    1983-01-01

    In this chapter the authors discuss the current status of heat and mass transport studies in the marine red clay sediments that are being considered as a nuclear waste isolation medium and review analytical and experimental studies. Calculations based on numerical models indicate that for a maximum allowable sediment-canister interface temperatures of 200 0 to 250 0 C, the sediment can absorb about 1.5kW initial power from waste buried 30 m in the sediment in a canister that is 3 m long and 0.3 m in diameter. The resulting fluid displacement due to convections is found to be small, less than 1 m. Laboratory studies of the geochemical effects induced by heating sediment-seawater mixtures indicate that the canister and waste form should be designed to resist a hot, relatively acidic oxidizing environment. Since the thermally altered sediment volume of about 5.5 m/sup 3/ is small relative to the sediment volume overlying the canister, the acid and oxidizing conditions should significantly affect the properties of the far field only if thermodiffusional process (Soret effect) prove to be significant. If thermodiffusional effects are important, however, near-field chemistry will differ considerably from that predicted from results of constant temperature sediment-seawater interaction experiments

  12. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The first text deals with a new circular concerning the collect of the medicine radioactive wastes, containing radium. This campaign wants to incite people to let go their radioactive wastes (needles, tubes) in order to suppress any danger. The second text presents a decree of the 31 december 1999, relative to the limitations of noise and external risks resulting from the nuclear facilities exploitation: noise, atmospheric pollution, water pollution, wastes management and fire prevention. (A.L.B.)

  13. Experimental investigation on single-phase pressure losses in nuclear debris beds: Identification of flow regimes and effective diameter

    Energy Technology Data Exchange (ETDEWEB)

    Clavier, R., E-mail: remi.clavier@irsn.fr [Institut de Radioprotection et de Sûreté Nucléaire (IRSN) – PSN-RES/SEREX/LE2M, Cadarache bât. 327, 13115 St Paul-lez-Durance (France); Chikhi, N., E-mail: nourdine.chikhi@irsn.fr [Institut de Radioprotection et de Sûreté Nucléaire (IRSN) – PSN-RES/SEREX/LE2M, Cadarache bât. 327, 13115 St Paul-lez-Durance (France); Fichot, F. [Institut de Radioprotection et de Sûreté Nucléaire (IRSN) – PSN-RES/SAG/LEPC, Cadarache bât. 700, 13115 St Paul-lez-Durance (France); Quintard, M. [Université de Toulouse – INPT – UPS – Institut de Mécanique des Fluides de Toulouse (IMFT), Allée Camille Soula, F-31400 Toulouse (France); CNRS – IMFT, F-31400 Toulouse (France)

    2015-10-15

    Highlights: • Single-phase pressure drops versus flow rates in particle beds are measured. • Conditions are representative of the reflooding of a nuclear fuel debris bed. • Darcy, weak inertial, strong inertial and weak turbulent regimes are observed. • A Darcy–Forchheimer law is found to be a good approximation in this domain. • A predictive correlation is derived from new experimental data. - Abstract: During a severe nuclear power plant accident, the degradation of the reactor core can lead to the formation of debris beds. The main accident management procedure consists in injecting water inside the reactor vessel. Nevertheless, large uncertainties remain regarding the coolability of such debris beds. Motivated by the reduction of these uncertainties, experiments have been conducted on the CALIDE facility in order to investigate single-phase pressure losses in representative debris beds. In this paper, these results are presented and analyzed in order to identify a simple single-phase flow pressure loss correlation for debris-bed-like particle beds in reflooding conditions, which cover Darcean to Weakly Turbulent flow regimes. The first part of this work is dedicated to study macro-scale pressure losses generated by debris-bed-like particle beds, i.e., high sphericity (>80%) particle beds with relatively small size dispersion (from 1 mm to 10 mm). A Darcy–Forchheimer law, involving the sum of a linear term and a quadratic deviation, with respect to filtration velocity, has been found to be relevant to describe this behavior in Darcy, Strong Inertial and Weak Turbulent regimes. It has also been observed that, in a restricted domain (Re = 15 to Re = 30) between Darcy and Weak Inertial regimes, deviation is better described by a cubic term, which corresponds to the so-called Weak Inertial regime. The second part of this work aims at identifying expressions for coefficients of linear and quadratic terms in Darcy–Forchheimer law, in order to obtain a

  14. EL4 cell-based colorimetric toxin neutralization activity assays for determination of neutralizing anti-ricin antibodies.

    Science.gov (United States)

    Lindsey, Changhong Y; Brown, J Edward; Torabazar, Nahid R; Smith, Leonard A

    2013-01-01

    A recombinant ricin toxin A-chain 1-33/44-198 vaccine (RVEc), developed at the United States Army Medical Research Institute of Infectious Diseases as a vaccine candidate, is under investigation in a phase 1 clinical study. To effectively evaluate the immunogenicity of this ricin vaccine and to eliminate the use of radioactive material, an EL4 cell-based colorimetric toxin neutralization activity (TNA) assay using a CellTiter 96 AQueous One Solution Cell Proliferation Assay Reagent has been developed, optimized, and applied in the vaccine efficacy studies. The TNA assay measures the protective neutralizing anti-ricin antibodies in animal sera by determining the cell viability after ricin exposure in the assay system and comparing it to a purified mouse polyclonal antiricin IgG standard curve. The standard curve of the anti-ricin TNA assay closely fits a four-parameter logistic regression model. The unknown test sample concentration was expressed as microg/mL, but not the 50% effective concentration (EC50), which was determined by most TNA assays. The neutralizing endpoint titers, not the 50% effective dilution (ED50), of human specimens were measured with the TNA assay in support of the clinical study of the RVEc vaccine. The optimal amount of ricin toxin, EL4 cells, and concentration of standards used in the assay system was established to minimize false-negative and false-positive results of serum specimens from the nonclinical and clinical studies of RVEc. The testing conditions were adjusted to optimize assay performance. The colorimetric TNA assay replaced a radioactive TNA assay previously used in the ricin vaccine studies.

  15. MONJU experimental data analysis and its feasibility evaluation to build up the standard data base for large FBR nuclear core design

    International Nuclear Information System (INIS)

    Sugino, K.; Iwai, T.

    2006-01-01

    MONJU experimental data analysis was performed by using the detailed calculation scheme for fast reactor cores developed in Japan. Subsequently, feasibility of the MONJU integral data was evaluated by the cross-section adjustment technique for the use of FBR nuclear core design. It is concluded that the MONJU integral data is quite valuable for building up the standard data base for large FBR nuclear core design. In addition, it is found that the application of the updated data base has a possibility to considerably improve the prediction accuracy of neutronic parameters for MONJU. (authors)

  16. FY2017 Final Report: Power of the People: A technical ethical and experimental examination of the use of crowdsourcing to support international nuclear safeguards verification.

    Energy Technology Data Exchange (ETDEWEB)

    Gastelum, Zoe Nellie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sentz, Kari [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Swanson, Meili Claire [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rinaudo, Cristina [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-10-01

    Recent advances in information technology have led to an expansion of crowdsourcing activities that utilize the “power of the people” harnessed via online games, communities of interest, and other platforms to collect, analyze, verify, and provide technological solutions for challenges from a multitude of domains. To related this surge in popularity, the research team developed a taxonomy of crowdsourcing activities as they relate to international nuclear safeguards, evaluated the potential legal and ethical issues surrounding the use of crowdsourcing to support safeguards, and proposed experimental designs to test the capabilities and prospect for the use of crowdsourcing to support nuclear safeguards verification.

  17. Analysis of Consequences in the Loss-of-Coolant Accident in Wendelstein 7-X Experimental Nuclear Fusion Facility

    Energy Technology Data Exchange (ETDEWEB)

    Uspuras, E., E-mail: algis@mail.lei.lt [Laboratory of Nuclear Installations Safety, Lithuanian Energy Institute, Kaunas (Lithuania)

    2012-09-15

    . The results of analysis demonstrated that proposed burst disk, connecting the plasma vessel with torus hall, opens and pressure inside plasma vessel do not exceed the limiting 1100 kPa absolute pressure. Thus, the plasma vessel remains intact after loss-of-coolant accident during no-plasma operation of Wendelstein 7-X experimental nuclear fusion facility. (author)

  18. TH-CD-201-07: Experimentally Investigating Proton Energy Deposition On the Microscopic Scale Using Fluorescence Nuclear Track Detectors

    Energy Technology Data Exchange (ETDEWEB)

    Underwood, T [Massachusetts General Hospital and Harvard Medical School, Boston, MA (United States); University College London, London (United Kingdom); McFadden, C; Sawakuchi, G [The University of Texas MD Anderson Cancer Center, Houston, TX (United States); Trenholm, D [Massachusetts General Hospital, Boston, MA (United States); Verburg, J; Paganetti, H; Schuemann, J [Massachusetts General Hospital and Harvard Medical School, Boston, MA (United States)

    2016-06-15

    Purpose: In order to further understand the interplay between proton physics and radiobiology it is necessary to consider proton energy deposition on the microscopic scale. In this work we used Fluorescent Nuclear Track Detectors (FNTDs) to experimentally investigate proton energy deposition, track-by-track. Methods: We irradiated 8×4×0.5mm{sup 3} FNTD chips (Landauer Inc) at seven water depths along a pristine proton Bragg peak with range=12cm. After irradiation, the FNTDs were scanned using a confocal microscope (FV1200, Olympus) with a high-power red laser and an oil-immersion objective lens (UPLSAPO60XO, NA=1.35). 10 slice image stacks were acquired with a slice-thickness of 2µm at multiple positions across each FNTD. Image-based analyses of track radius and track “mass” (integrated signal intensity) were performed using trackpy. For comparison, Monte Carlo simulated data were obtained using TOPAS and TOPAS-nBio. Results: Excellent correlation was observed between median track mass and TOPAS dose-averaged linear energy transfer. The resolution of the imaging system was determined insufficient to detect a relationship between track radius and exposure depth. Histograms of track mass (i) displayed strong repeatability across positions within an FNTD and (ii) varied in peak position and shape as a function of depth. TOPAS-nBio simulations implemented on the nanometer scale using physics lists from GEANT4-DNA yielded energy deposition distributions for individual protons and electrons scored within a virtual FNTD. Good agreement was found between these simulated datasets and the FNTD track mass distributions. Conclusion: Robust experimental measurements of the integral energy deposited by individual proton tracks can be performed using FNTDs. Monte Carlo simulations offer an exceedingly powerful approach to the quantification of proton energy deposition on the microscopic scale, but whilst they have been well validated at the macroscopic level, their

  19. Experimental ratio between the 'real' dose per organ and the calculated dose determined by means of the Embalse nuclear power plant's personal dosimeter

    International Nuclear Information System (INIS)

    Thomasz, E.; Salas, C.A.

    1987-01-01

    The specific purpose of the study was to determine the experimental ratio between the reading of dosimeters used by the personnel of the Embalse nuclear power plant and the 'real' dose absorbed by the worker in different organs. An anthropomorphic phantom ALDERSON internal and externally loaded with approximately 150 TLD crystals was used. This phantom was placed in five enclosures that were usually occupied by workers of the Embalse nuclear power plant. In this way, the average dose per organ and the effective equivalent dosis in each enclosure could be calculated and compared with the personal dosimeters placed over the thorax and the conversion factor rem/rem for each enclosure was determined. The average factor resulting from the five considered enclosures was 0.73 rem/rem. This means that the personal dosimeters over value the real dosis absorbed by the personnel of the Embalse nuclear power plant in approximately 37%. (Author)

  20. Experimental effects of dynamics and thermodynamics in nuclear reactions on the symmetry energy as seen by the CHIMERA 4 π detector

    Energy Technology Data Exchange (ETDEWEB)

    De Filippo, E.; Pagano, A. [INFN, Catania (Italy)

    2014-02-15

    Heavy-ion collisions have been widely used in the last decade to constrain the parameterizations of the symmetry energy term of the nuclear equation of state (EOS) for asymmetric nuclear matter as a function of baryonic density. In the Fermi energy domain one is faced with variations of the density within a narrow range of values around the saturation density ρ{sub 0}=0.16 fm{sup -3} down towards sub-saturation densities. The experimental observables which are sensitive to the symmetry energy are constructed starting from the detected light particles, clusters and heavy fragments that, in heavy-ion collisions, are generally produced by different emission mechanisms at different stages and time scales of the reaction. In this review the effects of dynamics and thermodynamics on the symmetry energy in nuclear reactions are discussed and characterized using an overview of the data taken so far with the CHIMERA multi detector array. (orig.)

  1. [Antitumor effect of recombinant Xenopus laevis vascular endothelial growth factor (VEGF) as a vaccine combined with adriamycin on EL4 lymphoma in mice].

    Science.gov (United States)

    Niu, Ting; Liu, Ting; Jia, Yong-Qian; Liu, Ji-Yan; Wu, Yang; Hu, Bing; Tian, Ling; Yang, Li; Kan, Bing; Wei, Yu-Quan

    2005-09-01

    To explore the antitumor effect of immunotherapy with recombinant Xenopus laevis vascular endothelial growth factor (xVEGF) as a vaccine combined with adriamycin on lymphoma model in mice. EL4 lymphoma model was established in C57BL/6 mice. Mice were randomized into four groups: combination therapy, adriamycin alone, xVEGF alone and normal saline (NS) groups, and then were given relevant treatments. The growth of tumor, the survival rate of tumor-bearing mice, and the potential toxicity of regimens above were observed. Anti-VEGF antibody-producing B cells (APBCs) were detected by enzyme-linked immunospot (ELISPOT) assay. In addition, microvessel density (MVD) of tumor was detected by immunohistochemistry, and tumor cell apoptosis was also detected by TUNEL staining. The tumor volumes of mice were significantly smaller in combination group than those in other three groups (P < 0.05). Complete regression of tumor was observed in 3 of 10 mice in combination group. Forty-eight days after inoculation of tumor cells, the survival rate of mice was significantly higher in combination group than in NS group (P < 0.01). The anti-VEGF APBC count in combination group or xVEGF group was significantly higher, compared with that in adriamycin group or NS group (P < 0.01). MVD in tumor tissues was significantly lower in combination group than those in other three groups (P < 0.05). Moreover, tumor cell apoptosis was significantly higher in combination group than those in other three groups (P < 0.05). In this experimental study, the use of xVEGF vaccine and adriamycin as a combination of immunotherapy with chemotherapy has sucessfully produced synergistic antitumor effect on lymphoma in mice.

  2. Extension of the energy range of experimental activation cross-sections data of deuteron induced nuclear reactions on indium up to 50MeV.

    Science.gov (United States)

    Tárkányi, F; Ditrói, F; Takács, S; Hermanne, A; Ignatyuk, A V

    2015-11-01

    The energy range of our earlier measured activation cross-sections data of longer-lived products of deuteron induced nuclear reactions on indium were extended from 40MeV up to 50MeV. The traditional stacked foil irradiation technique and non-destructive gamma spectrometry were used. No experimental data were found in literature for this higher energy range. Experimental cross-sections for the formation of the radionuclides (113,110)Sn, (116m,115m,114m,113m,111,110g,109)In and (115)Cd are reported in the 37-50MeV energy range, for production of (110)Sn and (110g,109)In these are the first measurements ever. The experimental data were compared with the results of cross section calculations of the ALICE and EMPIRE nuclear model codes and of the TALYS 1.6 nuclear model code as listed in the on-line library TENDL-2014. Copyright © 2015 Elsevier Ltd. All rights reserved.

  3. [Establishment of EL4 tumor-bearing mouse models and investigation on immunological mechanisms of anti-tumor effect of melphalan].

    Science.gov (United States)

    Li, Mo-lin; Li, Chuan-gang; Shu, Xiao-hong; Jia, Yu-jie; Qin, Zhi-hai

    2006-03-01

    To establish mouse lymphoma EL4 tumor-bearing mouse models in wild type C57BL/6 mice and nude C57BL/6 mice respectively, and to further investigate the immunological mechanisms of anti-tumor effect of melphalan. Mouse lymphoma EL4 cells were inoculated subcutaneously into wild type C57BL/6 mice (immune-competent mice). Twelve days later, melphalan of different doses were administered intraperitoneally to treat these wild type C57BL/6 tuomr-bearing mice. Tumor sizes were observed and recorded subsequently to find out the minimal dose of melphalan that could cure the tuomr-bearing mice. Then the same amount of EL4 tumor cells were inoculated subcutaneously into wild type C57BL/6 mice and nude C57BL/6 mice (T cell-deficient mice) simultaneously, which had the same genetic background of C57BL/6. Twelve days later, melphalan of the minimal dose was given intraperitoneally to treat both the wild type and nude C57BL/6 tuomr-bearing mice. Tumor sizes were observed and recorded in these two different types of mice subsequently. A single dose of melphalan (7.5 mg/kg) could cure EL4 tumor-bearing wild type C57BL/6 mice, but could not induce tumor regression in EL4 tumor-bearing nude C57BL/6 mice. A single dose of melphalan has obvious anti-tumor effect on mouse lymphoma EL4 tumor-bearing wild type C57BL/6mice, which requires the involvement of T lymphocytes in the host probably related to their killing functions.

  4. [Study of the immunological mechanism of anti-tumor effects of 5-FU by establishing EL4 tumor-bearing mouse models].

    Science.gov (United States)

    Li, Mo-Lin; Li, Chuan-Gang; Shu, Xiao-Hong; Li, Ming-Xia; Jia, Yu-Jie; Qin, Zhi-Hai

    2007-11-01

    To investigate the immunological mechanism of anti-tumor effect of 5-FU by establishing lymphoma EL4 tumor-bearing mouse models in wild type C57BL/6 mice and nude C57BL/6 mice, respectively. The mouse lymphoma EL4 cells were inoculated subcutaneously into wild type C57BL/6 mice (immune-competent mice). Twelve days later, 5-FU of different doses was administered intraperitoneally to treat these wild type C57BL/6 tumor-bearing mice. The size of tumors in the wild type C57BL/6 mice was observed and recorded to explore the minimal dose of 5-FU that could cure the tumor-bearing mice. Then the same amount of EL4 tumor cells was inoculated subcutaneously into wild type C57BL/6 mice and nude C57BL/6 mice (T cell-deficient mice) simultaneously, which had the same genetic background of C57BL/6. Twelve days later, 5-FU of the minimal dose was given intraperitoneally to treat both the wild type and nude C57BL/6 tumor-bearing mice. The size of tumors in the two different types of mice was observed and recorded. A single dose of 5-FU (75 mg/kg) cured both the EL4 tumor-bearing wild type C57BL/6 mice and the EL4 tumor-bearing nude C57BL/6 mice in the first week. Two weeks after 5-FU treatment, all of the nude mice died of tumor relapse while most of the wild type C57BL/6 mice were fully recovered. A single dose of 5-FU has marked anti-tumor effects on lymphoma EL4 tumor-bearing C57BL/6 mice with or without T lymphocytes. The relapse of tumors after 5-FU treatment might be related to the function of T lymphocytes.

  5. Doxorubicin plus tumor necrosis factor alpha combination treatments in EL4-lymphoma-bearing C57BL/6 mice.

    Science.gov (United States)

    Ehrke, M J; Verstovsek, S; Ujházy, P; Meer, J M; Eppolito, C; Maccubbin, D L; Mihich, E

    1998-02-01

    The therapeutic efficacy of a total of 42 single-agent or combination protocols involving doxorubicin (Adriamycin, ADM) and tumor necrosis factor alpha (TNFalpha) were evaluated in the syngeneic murine lymphoma model, C57BL/6-EL4. Combination treatments were the most effective and the therapeutic effects were schedule-dependent; e.g. it was generally advantageous for ADM to precede TNFalpha administration. Two protocols selected for further study were 4 mg/kg ADM i.v. on days 1 and 8 plus TNFalpha, i.v., at either 16000 U (7 microg)/injection, on days 1 and 8 or 4000 U (1.7 microg)/injection, on days 11-15. Survival of mice bearing one of four EL4 sublines having different in vitro drug sensitivities was assessed. These sublines were E10 (ADM-sensitive/TNFalpha-resistant), E16 (sensitive/sensitive), ER2 (ADM-resistant/TNFalpha-sensitive) and ER13 (resistant/resistant). Between 80% and 100% long-term survivors (i.e. tumor free on day 60) were obtained with the two treatments in mice bearing ADM-sensitive sublines, even though one of these sublines, E10, was resistant to TNFalpha in vitro. Induction of long-term survival appeared, therefore, to correlate with in vitro defined sensitivity/resistance to ADM, but not to TNFalpha Treatment-induced modulations of tumoricidal immune effector functions were also examined. Taken together, the results indicated that induction of long-term survival involved complex interactions of: (1) ADM-induced tumor modifications, including, but not limited to, tumor debulking, (2) combination-treatment-induced modifications of splenic cytolytic T cell and macrophage activities, and (3) the restoration of thymus cellularity. Finally, when long-term survivors resulting from treatment of E10- or E16-bearing mice were implanted with ER2 on day 120, the majority survived, indicating that long-term immune memory, capable of recognizing drug resistant variants, had been established.

  6. Membrane Raft Organization Is More Sensitive to Disruption by (n-3) PUFA Than Nonraft Organization in EL4 and B Cells123

    OpenAIRE

    Rockett, Benjamin Drew; Franklin, Andrew; Harris, Mitchel; Teague, Heather; Rockett, Alexis; Shaikh, Saame Raza

    2011-01-01

    Model membrane and cellular detergent extraction studies show (n-3) PUFA predominately incorporate into nonrafts; thus, we hypothesized (n-3) PUFA could disrupt nonraft organization. The first objective of this study was to determine whether (n-3) PUFA disrupted nonrafts of EL4 cells, an extension of our previous work in which we discovered an (n-3) PUFA diminished raft clustering. EPA or DHA treatment of EL4 cells increased plasma membrane accumulation of the nonraft probe 1,1′-dilinoleyl-3,...

  7. Design of the Small Rods Forming the Fuel Element of the First Charge of the EL4 Reactor. Cladding Problems; Etude des crayons constituant l'element combustible du premier jeu d'EL4 - probleme de la gaine; Problema pokrytiya nebol'shikh steeknej, obrazushchikh toplivnyj ehlement pervoj zagruzki reaktora EL.4; Estudio de las barras que constituyen los elementos combustibles de la primera carga del reactor EL4 - el problema de las vainas

    Energy Technology Data Exchange (ETDEWEB)

    Bailly, H.; Ringot, C.; Weisz, M. [Centre d' Etudes Nucleaires de Saclay (France)

    1963-11-15

    The fuel element for the first charge of EL4 makes use of stainless steel cans. The grade of steel chosen and the can thickness depend on the corrosion resistance and mechanical strength required. The operating stresses and temperatures are such that fabrication of a can lasting throughout the life of the fuel element calls for a highly resistant grade of steel, of thickness greater than 0.5 mm. When the can bears on the fuel as a result of creep, deformation in diametrical clearance may lead to ovalization and folding, while deformation in longitudinal clearance may cause buckling of the can. Numerous tests have been carried out on cans of thickness 0.3 and 0.4 mm to determine type of deformation as a function of clearance. To be certain of avoiding ovalization with the thicknesses proposed and to keep the internal temperature of the fuel as low as possible, the clearance must be reduced to zero in fabrication. (author) [French] L'element combustible du premier jeu EL4 utilise des gaines en acier inoxydable. Le choix de la nuance et de l'epaisseur de la gaine est lie a des considerations de tenue a la corrosion et de tenue mecanique. Les contraintes et les temperatures d'utilisation ne permettent pas de concevoir une gaine resistante pendant toute la vie de l'element combustible a moins d'utiliser une nuance tres resistante et d'epaisseur superieure a 0,5 mm. On admet que la gaine s'applique par fluage sur le combustible: la deformation dans les jeux diametraux peut conduire a la formation d'une ovalisation et d'un pli; la deformation dans les jeux longitudinaux peut conduire a des flambages de la gaine. De nombreux essais ont ete realises sur des gaines d'epaisseurs 0,3 et 0,4 mm pour connaitre le mode de deformation en fonction des jeux. Pour etre certain de ne jamais avoir d'ovalisation avec les epaisseurs envisagees, et pour avoir la temperature a coeur du combustible la plus basse possible, on est conduit a reduire a zero le jeu en fabrication. (author

  8. Experimentation of nuclear weapons, releases and storages of radioactive wastes in the Kara sea and in New Zemble

    International Nuclear Information System (INIS)

    Charmasson, S.

    1996-01-01

    132 nuclear weapons were tested from 1955 to 1990 in New Zemble. From 1959 to 1993, low level liquid radioactive wastes, low and medium level solid radioactive wastes, reactor core and fuel of submarine and nuclear propelled ships were released in the Kara and the Barentz seas. For these two seas, a recapitulation of the different radioactive sources and the found level of radioactivity of the marine environment are presented. (A.B.). 22 refs. 4 figs., 6 tabs

  9. Development of experimental method to simulate the corrosion products in the primary system of nuclear power plant

    International Nuclear Information System (INIS)

    Kim, Sang Hyun; Kim, In Sup; Jang, Chang Heui

    2005-01-01

    Corrosion products are recognized as one of the major sources of occupational radiation exposure for nuclear power plant workers. Numerous studies have been conducted on the primary water chemistry to reduce the amount of crud in the primary circuit to avoid the radioactivity build-up in the plant. However, experiments with crud are restricted in laboratory because the crud is highly radioactive material. The objective of this study is to develop the simulating method of corrosion product in nuclear power plant

  10. Design and development of microcontroller based programmable ramp generator for AC-DC converter for simulating decay power transient in experimental facility for nuclear power plants

    International Nuclear Information System (INIS)

    Srivastava, Gaurava Deep; Kulkarni, R.D.

    2015-01-01

    In nuclear power plants, fuel is subjected to a wide range of power and temperature transients during normal and abnormal conditions. The reactor setback and step-back power pattern, fast temperature profile occurred during Loss of Coolant Accident and decay power followed by shutdown of power plant are the typical transients in nuclear power plant. For a variety of reactor engineering and reactor safety related study, one needs to simulate these transients in experimental facility. In experimental facilities, high response AC-DC converters are used to handle these power and temperature transients safely in a controlled manner for generating a database which is utilized for design of thermal hydraulic system, development of computer codes, study of reliability of reactor safety system, etc. for nuclear power plants. The paper presents the methodology developed for simulating the typical reactor decay power transient in an experimental facility. The design and simulation of AC-DC power electronic converter of 3 MW capacity is also presented. The microcontroller based programmable ramp generator is designed and hardware implemented for feeding reference voltage to the closed loop control system of AC-DC converter for obtaining the decay power profile at the converter output. The typical decay power transient of the nuclear power plant is divided into several small power ramps for simulating the transient. The signal corresponding to each power ramp is generated by programmable ramp generator and fed to the comparator for generating control signal for the converter. The actual decay power transient obtained from the converter is compared with the theoretical decay power transient. (author)

  11. Experimental nuclear thermoelectric assembly open-quotes Gammaclose quotes-a prototype of an unattended self-regulating nuclear thermoelectric station

    International Nuclear Information System (INIS)

    Buinitskii, B.A.; Kaplar, E.P.; Kondrat'ev, F.V.; Leppik, P.A.; Nafikov, D.Ya.; Pavelko, V.I.; Rychev, A.S.; Tarasov, V.P.; Khlopkin, N.S.

    1993-01-01

    At the beginning of the seventies, the concept of building small atomic power stations with direct conversion of the thermal energy of a reactor for supplying electricity and heat to consumers located at remote and inaccessible regions was developed on the basis of assessment calculations and technical studies made in the I.V. Kurchatov Institute of Atomic Energy. When new technical solutions were adopted to put this concept into practice, combined trials on a test stand were required. For this purpose, the nuclear thermoelectric test-demonstration assembly open-quotes Gammaclose quotes was built and put into operation in 1981. It is based on the three principles which determine the development of unattended self-regulating nuclear thermoelectric stations: using a water-water reactor with self-regulation of the power as a source of heat; using a cooling system without pumps but with natural circulation of the coolant in the primary and intermediate circuits for removing the hend thermoelectric conversion of heat into electricity. During the ten years of operation of the open-quotes Gammaclose quotes assembly, a research program on the principles of unattended self-regulating nuclear thermoelectric stations was carried out and the results are summarized

  12. The mouse tumor cell lines EL4 and RMA display mosaic expression of NK-related and certain other surface molecules and appear to have a common origin.

    Science.gov (United States)

    Gays, F; Unnikrishnan, M; Shrestha, S; Fraser, K P; Brown, A R; Tristram, C M; Chrzanowska-Lightowlers, Z M; Brooks, C G

    2000-05-15

    As a potential means for facilitating studies of NK cell-related molecules, we examined the expression of these molecules on a range of mouse tumor cell lines. Of the lines we initially examined, only EL4 and RMA expressed such molecules, both lines expressing several members of the Ly49 and NKRP1 families. Unexpectedly, several of the NK-related molecules, together with certain other molecules including CD2, CD3, CD4, CD32, and CD44, were often expressed in a mosaic manner, even on freshly derived clones, indicating frequent switching in expression. In each case examined, switching was controlled at the mRNA level, with expression of CD3zeta determining expression of the entire CD3-TCR complex. Each of the variable molecules was expressed independently, with the exception that CD3 was restricted to cells that also expressed CD2. Treatment with drugs that affect DNA methylation and histone acetylation could augment the expression of at least some of the variable molecules. The striking phenotypic similarity between EL4 and RMA led us to examine the state of their TCRbeta genes. Both lines had identical rearrangements on both chromosomes, indicating that RMA is in fact a subline of EL4. Overall, these findings suggest that EL4 is an NK-T cell tumor that may have retained a genetic mechanism that permits the variable expression of a restricted group of molecules involved in recognition and signaling.

  13. Experimental studies of particle acceleration with ultra-intense lasers - Applications to nuclear physics experiments involving laser-produced plasmas

    International Nuclear Information System (INIS)

    Plaisir, C.

    2010-11-01

    For the last ten years, the Ultra High Intensity Lasers offer the opportunity to produce accelerated particle beams which contain more than 10 12 electrons, protons accelerated into a few ps. We have simulated and developed some diagnostics based on nuclear activation to characterize both the angular and the energy distributions of the particle beams produced with intense lasers. The characterization methods which are presented are illustrated by means of results obtained in different experiments. We would use the particle beams produced to excite nuclear state in a plasma environment. It can modify intrinsic characteristics of the nuclei such as the half-life of some isomeric states. To prepare this kind of experiments, we have measured the nuclear reaction cross section (gamma,n) to produce the isomeric state of the 84 Rb, which has an excitation energy of 463 keV, with the electron accelerator ELSA of CEA/DIF in Bruyeres-le-Chatel (France). (author)

  14. Mortality and cancer incidence 1952-1998 in UK participants in the UK atmospheric nuclear weapons tests and experimental programmes

    International Nuclear Information System (INIS)

    Muirhead, C.R.; Bingham, D.; Haylock, R.G.E.; O'Hagan, J.A.; Goodill, A.A.; Berridge, G.L.C.; English, M.A.; Hunter, N.; Kendall, G.M.

    2003-01-01

    An updated analysis has been conducted of mortality and cancer incidence among men from the United Kingdom who took part in the UK atmospheric nuclear weapon tests and experimental programmes in Australia and the Pacific between 1952 and 1967. Rates of multiple myeloma, leukaemia, other cancers, and non-cancer causes of death were studied, as in previous analyses of these men. Based on a total of 21,357 test participants and 22,333 controls identified from the same Ministry of Defence (MOD) archives, information was obtained on deaths and cancer registrations up to the end of 1998. Compared with national mortality rates, rates of deaths from all causes increased to a similar extent in both test participants and controls with longer follow-up, with Standardised Mortality Ratios (SMRs) of 89 and 88 respectively over the full follow-up period and a relative risk of 1.01 (90% confidence interval (Cl) 0.98-1.05). For all cancers, the corresponding SMRs were 93 for test participants and 92 for controls, with a relative risk of 1.01 (90% Cl 0.96-1.08) for all cancers. Mortality from multiple myeloma was consistent with national rates both for test participants and controls, and the relative risk of myeloma incidence among test participants relative to controls was 1.14 (90% Cl 0.74-1.74) over the full follow up period and 0.79 (90% Cl 0.45-1.38) during the extended period of follow up (1991-98). Over the full follow-up period, leukaemia mortality among test participants was consistent with national rates, whilst rates among controls were significantly lower (SMR 68), and there was a suggestion of a raised risk among test participants relative to controls (relative risk 1.45 (0.96-2.17), one-sided p=0.07, two-sided p=0.14); the corresponding relative risk for leukaemia incidence was 1.33 (0.97-1.84), one-sided p==0.07, two-sided p=0.14. After excluding chronic lymphatic leukaemia (CLL), which is not thought to be radiation-inducible, the relative risk of leukaemia

  15. Membrane raft organization is more sensitive to disruption by (n-3) PUFA than nonraft organization in EL4 and B cells.

    Science.gov (United States)

    Rockett, Benjamin Drew; Franklin, Andrew; Harris, Mitchel; Teague, Heather; Rockett, Alexis; Shaikh, Saame Raza

    2011-06-01

    Model membrane and cellular detergent extraction studies show (n-3) PUFA predominately incorporate into nonrafts; thus, we hypothesized (n-3) PUFA could disrupt nonraft organization. The first objective of this study was to determine whether (n-3) PUFA disrupted nonrafts of EL4 cells, an extension of our previous work in which we discovered an (n-3) PUFA diminished raft clustering. EPA or DHA treatment of EL4 cells increased plasma membrane accumulation of the nonraft probe 1,1'-dilinoleyl-3,3,3',3'-tetramethylindocarbocyanine perchlorate by ~50-70% relative to a BSA control. Förster resonance energy transfer imaging showed EPA and DHA also disrupted EL4 nanometer scale nonraft organization by increasing the distance between nonraft molecules by ~25% compared with BSA. However, changes in nonrafts were due to an increase in cell size; under conditions where EPA or DHA did not increase cell size, nonraft organization was unaffected. We next translated findings on EL4 cells by testing if (n-3) PUFA administered to mice disrupted nonrafts and rafts. Imaging of B cells isolated from mice fed low- or high-fat (HF) (n-3) PUFA diets showed no change in nonraft organization compared with a control diet (CD). However, confocal microscopy revealed the HF (n-3) PUFA diet disrupted lipid raft clustering and size by ~40% relative to CD. Taken together, our data from 2 different model systems suggest (n-3) PUFA have limited effects on nonrafts. The ex vivo data, which confirm previous studies with EL4 cells, provide evidence that (n-3) PUFA consumed through the diet disrupt B cell lipid raft clustering.

  16. Membrane Raft Organization Is More Sensitive to Disruption by (n-3) PUFA Than Nonraft Organization in EL4 and B Cells123

    Science.gov (United States)

    Rockett, Benjamin Drew; Franklin, Andrew; Harris, Mitchel; Teague, Heather; Rockett, Alexis; Shaikh, Saame Raza

    2011-01-01

    Model membrane and cellular detergent extraction studies show (n-3) PUFA predominately incorporate into nonrafts; thus, we hypothesized (n-3) PUFA could disrupt nonraft organization. The first objective of this study was to determine whether (n-3) PUFA disrupted nonrafts of EL4 cells, an extension of our previous work in which we discovered an (n-3) PUFA diminished raft clustering. EPA or DHA treatment of EL4 cells increased plasma membrane accumulation of the nonraft probe 1,1′-dilinoleyl-3,3,3′,3′-tetramethylindocarbocyanine perchlorate by ~50–70% relative to a BSA control. Förster resonance energy transfer imaging showed EPA and DHA also disrupted EL4 nanometer scale nonraft organization by increasing the distance between nonraft molecules by ~25% compared with BSA. However, changes in nonrafts were due to an increase in cell size; under conditions where EPA or DHA did not increase cell size, nonraft organization was unaffected. We next translated findings on EL4 cells by testing if (n-3) PUFA administered to mice disrupted nonrafts and rafts. Imaging of B cells isolated from mice fed low- or high-fat (HF) (n-3) PUFA diets showed no change in nonraft organization compared with a control diet (CD). However, confocal microscopy revealed the HF (n-3) PUFA diet disrupted lipid raft clustering and size by ~40% relative to CD. Taken together, our data from 2 different model systems suggest (n-3) PUFA have limited effects on nonrafts. The ex vivo data, which confirm previous studies with EL4 cells, provide evidence that (n-3) PUFA consumed through the diet disrupt B cell lipid raft clustering. PMID:21525263

  17. Development and implantation of application systems for reduction and analysis of experimental data in Nuclear Physics area

    International Nuclear Information System (INIS)

    Cardoso Junior, J.L.; Schelin, H.R.; Lemos, B.J.K.C.; Tanaka, E.H.; Castro, A.T.C.G.

    1984-01-01

    Several application systems for reduction and analysis of experimental data are described. These codes were development and/or implanted in tee IEAv/CTA CYBER 170/750 system. A brief description of the experimental data acquisition modes and the necessary reduction for analysis is given. Information on the purposes, uses and access of the codes are given [pt

  18. Study of the experimental parameters for the determination of Ca, Cr, Cu, Fe, Mn and Ni on nuclear grade UO2 by X-ray fluorescence technique

    International Nuclear Information System (INIS)

    Salvador, V.L.R.

    1982-01-01

    An analytical method for the simultaneous determinations of low concentrations of Ca, Cr, Cu, Fe, Mn and Ni on the nuclear grade UO 2 by X-ray fluorescence technique, without the use of chemical treatment, is described. The optimization of the experimental conditions was established on the X-ray fluorescence spectrometer and a low limit of detection (4 - 7 μg/gU) was achieved which satisfies the requirement in the nuclear fuel specification. The samples were prepared in the form of double layer pressed pellets using boric acid as a binding agent. The characteristic first order K sub(α) line intensity of each minor component was measured and the values of its concentrations were deduced using respective standard calibrations curves. The precision, accuracy and acceptability of the method were determined for all elements. The values of the precision are in the range of 2 - 10% and the accuracy are lower than 7%. (Author) [pt

  19. Importance of the pharmacological profile of the bound ligand in enrichment on nuclear receptors: toward the use of experimentally validated decoy ligands.

    Science.gov (United States)

    Lagarde, Nathalie; Zagury, Jean-François; Montes, Matthieu

    2014-10-27

    The evaluation of virtual ligand screening methods is of major importance to ensure their reliability. Taking into account the agonist/antagonist pharmacological profile should improve the quality of the benchmarking data sets since ligand binding can induce conformational changes in the nuclear receptor structure and such changes may vary according to the agonist/antagonist ligand profile. We indeed found that splitting the agonist and antagonist ligands into two separate data sets for a given nuclear receptor target significantly enhances the quality of the evaluation. The pharmacological profile of the ligand bound in the binding site of the target structure was also found to be an additional critical parameter. We also illustrate that active compound data sets for a given pharmacological activity can be used as a set of experimentally validated decoy ligands for another pharmacological activity to ensure a reliable and challenging evaluation of virtual screening methods.

  20. Experimental study of the combined utilization of nuclear power heating plants for big towns and industrial complexes

    International Nuclear Information System (INIS)

    Neumann, J.; Barabas, K.

    1977-01-01

    The paper describes a comparison of nuclear power heating plants with an output corresponding to 1000MW(e) with plants of the same output using coal or oil. The economic aspects are compared, both as regards investment and operation costs. The comparison of the environmental aspects is performed on the atmospheric pollution from exhausts and gaseous emission and on the thermal pollutions in hydrosphere and atmosphere. Basic nuclear power plant schemes with two PWRs, each of 1500MW(th), are described. The plant supplies electric power and heat for factories and municipal heating systems (apartments, shops, and other auxiliary municipal facilities). At the same time the basic heat-flow diagram of a nuclear power heating plant is given, together with the relative losses. The study emphasizes the possible utilization of waste heat for heating glasshouses of 200m 2 . The problems of utilizing waste heat, and the needs of a big town and of industrial complexes in the vicinity of the nuclear power heating plant are also considered. (author)

  1. Decree of May 4, 2015 creating a Commission of Information on ancient Pacific sites of nuclear experimentations

    International Nuclear Information System (INIS)

    Le Drian, Jean-Yves

    2015-01-01

    This official publication indicates the mission and composition of the Commission of Information which has been created to gather information and inform the public on the impact on health and on the environment of nuclear tests performed in the Mururoa and Fangatofa sites. It also describes how this Commission will operate

  2. The role of nuclear emulsions in the institutionalization of research in experimental physics in Brazil; O papel das emulsoes nucleares na institucionalizacao da pesquisa em fisica experimental no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Vieira, Cassio Leite [Instituto Ciencia Hoje, Rio de Janeiro, RJ (Brazil); Videira, Antonio A.P. [Universidade do Estado do Rio de Janeiro (UERJ), RJ (Brazil); Conselho Nacional de Desenvolvimento Cientifico e Tecnologico (CNPq), Brasilia, DF (Brazil)

    2011-07-01

    In this paper, we describe and analyze the introduction and the use of the nuclear emulsions technique in Brazil. Even though consistent researches in cosmic ray physics had been done since the forties of the last century in this country, physicists here only began using this technique after Cesar Lattes' works in Bristol (England) and Berkeley (US). Despite being the implantation of the technique in this country posterior to the origin of the method itself dated from late 1900s, Brazilian scientists were quickly familiarized with it and adopted it not only in cosmic rays, but also in particle physics and nuclear physics, employing it until recently. In our work, we will be concerned with the reasons of this longevity. In other words, why were the nuclear emulsions technique employed for so many years in Brazil, even after its vanishing in physics researches centers in the world? We advance here that the answer to this question involves the institutionalization of science in Brazil mainly physics and economical, social, and geographic reasons. (author)

  3. Modelling in the experimental study of the hydrogen mixing with inner atmosphere of the safety containers of nuclear power plants in post LOCA conditions

    International Nuclear Information System (INIS)

    Fineschi, F.; Lanza, S.

    1979-01-01

    In light water nuclear power plants hydrogen releases from the pressure containment system may take place following a loss-of-coolant accident. In view of preparing technical safeguards aiming at the control of the flame propagation probability and of explosions, it is important to know the space-time distribytion of hydrogen concentrations in the safety containers. It is shown that an experimental study on a scale model is praticable only in the case when full turbulence conditions occur in the container and in the model. Then general aspects of a methodology capable to verify with a reasonable confiance degree the validity of the assumptions is illustrated

  4. Summary Report of Consultants' Meeting on Accuracy of Experimental and Theoretical Nuclear Cross-Section Data for Ion Beam Analysis and Benchmarking

    International Nuclear Information System (INIS)

    Abriola, Daniel; Dimitriou, Paraskevi; Gurbich, Alexander F.

    2013-11-01

    A summary is given of a Consultants' Meeting assembled to assess the accuracy of experimental and theoretical nuclear cross-section data for Ion Beam Analysis and the role of benchmarking experiments. The participants discussed the different approaches to assigning uncertainties to evaluated data, and presented results of benchmark experiments performed in their laboratories. They concluded that priority should be given to the validation of cross- section data by benchmark experiments, and recommended that an experts meeting be held to prepare the guidelines, methodology and work program of a future coordinated project on benchmarking.

  5. Forecast of criticality experiments and experimental programs needed to support nuclear operations in the United States of America: 1994-1999

    International Nuclear Information System (INIS)

    Rutherford, D.

    1995-01-01

    This Forecast is generated by the Chair of the Experiment Needs Identification Workgroup (ENIWG), with input from Department of Energy and the nuclear community. One of the current concerns addressed by ENIWG was the Defense Nuclear Facilities Safety Board's Recommendation 93-2. This Recommendation delineated the need for a critical experimental capability, which includes (1) a program of general-purpose experiments, (2) improving the information base, and (3) ongoing departmental programs. The nuclear community also recognizes the importance of criticality theory, which, as a stepping stone to computational analysis and safety code development, needs to be benchmarked against well-characterized critical experiments. A summary projection of the Department's needs with respect to criticality information includes (1) hands-on training, (2) criticality and nuclear data, (3) detector systems, (4) uranium- and plutonium-based reactors, and (5) accident analysis. The Workgroup has evaluated, prioritized, and categorized each proposed experiment and program. Transportation/Applications is a new category intended to cover the areas of storage, training, emergency response, and standards. This category has the highest number of priority-1 experiments (nine). Facilities capable of performing experiments include the Los Alamos Critical Experiment Facility (LACEF) along with Area V at Sandia National Laboratory. The LACEF continues to house the most significant collection of critical assemblies in the Western Hemisphere. The staff of this facility and Area V are trained and certified, and documentation is current. ENIWG will continue to work with the nuclear community to identify and prioritize experiments because there is an overwhelming need for critical experiments to be performed for basic research and code validation

  6. Experimental determination of nuclear reaction rates in 238U and 235U along of the radius of fuel pellets of the IPEN/MB-01 reactor

    International Nuclear Information System (INIS)

    Mura, Luis Felipe Liambos

    2015-01-01

    This research presents and consolidates an alternative methodology for determining nuclear reaction rates along the radial direction of the fuel pellets which does not require high neutron flux. This technique is based on irradiating a thin UO 2 disk inserted into a removable fuel rod at the IPEN/MB-01 reactor core. Several gamma spectrometry are performed after irradiation using a HPGe detector. Six lead collimators with different diameters are sequentially alternated during this process, thus, the nuclear radioactive capture which occurs in 238 U and the fissions which occur in both 235 U and 238 U are measured according to six different radial regions of the fuel disk. Geometric efficiency corrections due to the introduction of collimators in HPGe detection system are determined by MCNP-5 code. The fission rate measurements are performed using the 99 Mo. This radionuclide was studied and proved ideal for these measurements because it is formed in linear behavior in the reactor core, have a high yield fission and emits low-energy photons. Measurements were performed irradiating UO 2 disks (with 4.3% enrichment) in the central position of the IPEN/MB-01 core at 100 watts power level during one hour. Some measurements were performed using a cadmium glove wrapped in the fuel rod to determine the nuclear reaction rates in the epithermal energy range. The experimental results obtained are compared with nuclear reaction rate calculations by means of MCNP-5 with ENDF/B-VII.0 data library showing discrepancies of up to 9% in 238 U capture rates and 14% for U fission rates for epithermal energies. Uncertainties regarding the nuclear capture rates have maximum values of 4.5% and the fission rates has maximum values of 11.3%. (author)

  7. Forecast of criticality experiments and experimental programs needed to support nuclear operations in the United States of America: 1994--1999

    Energy Technology Data Exchange (ETDEWEB)

    Rutherford, D.

    1994-03-01

    This Forecast is generated by the Chair of the Experiment Needs Identification Workgroup (ENIWG), with input from Department of Energy and the nuclear community. One of the current concerns addressed by ENIWG was the Defense Nuclear Facilities Safety Board`s Recommendation 93-2. This Recommendation delineated the need for a critical experimental capability, which includes (1) a program of general-purpose experiments, (2) improving the information base, and (3) ongoing departmental programs. The nuclear community also recognizes the importance of criticality theory, which, as a stepping stone to computational analysis and safety code development, needs to be benchmarked against well-characterized critical experiments. A summary project of the Department`s needs with respect to criticality information includes (1) hands-on training, (2) criticality and nuclear data, (3) detector systems, (4) uranium- and plutonium-based reactors, and (5) accident analysis. The Workgroup has evaluated, prioritized, and categorized each proposed experiment and program. Transportation/Applications is a new category intended to cover the areas of storage, training, emergency response, and standards. This category has the highest number of priority-1 experiments (nine). Facilities capable of performing experiments include the Los Alamos Critical Experiment Facility (LACEF) along with Area V at Sandia National Laboratory. The LACEF continues to house the most significant collection of critical assemblies in the Western Hemisphere. The staff of this facility and Area V are trained and certified, and documentation is current. ENIWG will continue to work with the nuclear community to identify and prioritize experiments because there is an overwhelming need for critical experiments to be performed for basic research and code validation.

  8. Forecast of criticality experiments and experimental programs needed to support nuclear operations in the United States of America: 1994--1999

    International Nuclear Information System (INIS)

    Rutherford, D.

    1994-03-01

    This Forecast is generated by the Chair of the Experiment Needs Identification Workgroup (ENIWG), with input from Department of Energy and the nuclear community. One of the current concerns addressed by ENIWG was the Defense Nuclear Facilities Safety Board's Recommendation 93-2. This Recommendation delineated the need for a critical experimental capability, which includes (1) a program of general-purpose experiments, (2) improving the information base, and (3) ongoing departmental programs. The nuclear community also recognizes the importance of criticality theory, which, as a stepping stone to computational analysis and safety code development, needs to be benchmarked against well-characterized critical experiments. A summary project of the Department's needs with respect to criticality information includes (1) hands-on training, (2) criticality and nuclear data, (3) detector systems, (4) uranium- and plutonium-based reactors, and (5) accident analysis. The Workgroup has evaluated, prioritized, and categorized each proposed experiment and program. Transportation/Applications is a new category intended to cover the areas of storage, training, emergency response, and standards. This category has the highest number of priority-1 experiments (nine). Facilities capable of performing experiments include the Los Alamos Critical Experiment Facility (LACEF) along with Area V at Sandia National Laboratory. The LACEF continues to house the most significant collection of critical assemblies in the Western Hemisphere. The staff of this facility and Area V are trained and certified, and documentation is current. ENIWG will continue to work with the nuclear community to identify and prioritize experiments because there is an overwhelming need for critical experiments to be performed for basic research and code validation

  9. Experimental and numerical investigations on the direct contact condensation phenomenon in horizontal flow channels and its implications in nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    Ceuca, Sabin Cristian [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany); Laurinavicius, Darius [Lithuanian Energy Institute, Kaunas (Lithuania)

    2016-11-15

    The complex direct contact condensation phenomenon is investigated in horizontal flow channels both experimentally and numerically with special emphasis on its implications on safety assessment studies. Under certain conditions direct contact condensation can act as the driving force for the water hammer phenomenon with potentially local devastating results, thus posing a threat to the integrity of the affected NPP components. New experimental results of in-depth analysis of the direct contact condensation phenomena obtained in Kaunas at the Lithuanian Energy Institute will be presented. The German system code ATHLET employing for the calculation of the heat transfer coefficient a mechanistic model accounting for two different eddy length scales, combined with the interfacial area transport equation will be assessed against condensation induced water hammer experimental data from the integral thermal-hydraulic experimental facility PMK-2, located at the KFKI Atomic Energy Research Institute in Budapest Hungary.

  10. Pressure suppression system (PSS) for nuclear ships. Experimental results obtained at the GKSS PSS-test-facillity

    International Nuclear Information System (INIS)

    Aust, E.; Niemann, H.R.; Schwan, H.; Vollbrandt, J.

    1978-01-01

    The PSS-test facility is shortly presented which was designed to show experimentally the operation of the pressure suppression containment for the NCS 80 concept. The results of the experimental LOCA-simulation tests in the PSS-test facility are illustrated by diagrams. The observed phenomena as chugging and pessure oscillations immediately after vent clearing are reported as well as the thermohydraulic loadings of the total system. Finally a short view is given on the future test program

  11. International ENEA/ISMES/ENS specialist meeting on 'On-site experimental verification of the seismic behaviour of nuclear reactor structures and components'. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-07-01

    The seismic verification of nuclear plants is a subject of increasing interest in all the industrial countries, with respect to both the safety aspects and the impact of the seismic event on the design and the costs of a nuclear reactor. This topic is especially of great interest for a country like Italy, whose territory is unfortunately characterized by non - negligible seismicity: we remember, not too many years ago, the catastrophic earthquakes of Frioul and Irpinia, that caused thousands of dead people. The meeting aimed at establishing the state-of-the-art on on-site testing of nuclear reactors structures and components, with particular attention to experiences and research programmes concerning: methodologies of on-site tests and interpretation of the experimental data; seismic monitoring systems, recorded data, their use and interpretation; calibration and validation of numerical analyses. Six technical sessions were held, during which 23 high papers were presented and discussed, and six panel discussions were held (the importance of discussion was emphasized in the meeting). The technical contributions consisted of: an introduction paper, summarizing the seismic studies performed in Italy for PEC reactor and explaining the reasons why on-site tests had been performed on this reactor; 6 invited lectures, one for each of the countries that are more deeply involved in seismic analysis, providing the state-of-the-art on the topics of interest for the meeting; 16 contributed papers dealing with more specific technical items, related to the various countries and international organizations.

  12. International ENEA/ISMES/ENS specialist meeting on 'On-site experimental verification of the seismic behaviour of nuclear reactor structures and components'. Proceedings

    International Nuclear Information System (INIS)

    1988-01-01

    The seismic verification of nuclear plants is a subject of increasing interest in all the industrial countries, with respect to both the safety aspects and the impact of the seismic event on the design and the costs of a nuclear reactor. This topic is especially of great interest for a country like Italy, whose territory is unfortunately characterized by non - negligible seismicity: we remember, not too many years ago, the catastrophic earthquakes of Frioul and Irpinia, that caused thousands of dead people. The meeting aimed at establishing the state-of-the-art on on-site testing of nuclear reactors structures and components, with particular attention to experiences and research programmes concerning: methodologies of on-site tests and interpretation of the experimental data; seismic monitoring systems, recorded data, their use and interpretation; calibration and validation of numerical analyses. Six technical sessions were held, during which 23 high papers were presented and discussed, and six panel discussions were held (the importance of discussion was emphasized in the meeting). The technical contributions consisted of: an introduction paper, summarizing the seismic studies performed in Italy for PEC reactor and explaining the reasons why on-site tests had been performed on this reactor; 6 invited lectures, one for each of the countries that are more deeply involved in seismic analysis, providing the state-of-the-art on the topics of interest for the meeting; 16 contributed papers dealing with more specific technical items, related to the various countries and international organizations

  13. Numerical and experimental simulation of accident processes using KMS large-scale test facility under the program of training university students for nuclear power industry

    International Nuclear Information System (INIS)

    Aniskevich, Yu.N.

    2005-01-01

    The KMS large-scale test facility is being constructed at NITI site and designed to model accident processes in VVER reactor plants and provide experimental data for safety analysis of both existing and future NPPs. The KMS phase I is at the completion stage. This is a containment model of 2000 m3 volume intended for experimentally simulating heat and mass transfers of steam-gas mixtures and aerosols inside containment. The KMS phase II will incorporate a reactor model (1:27 scale) and be used for analysing a number of events including primary and secondary LOCA. The KMS program for background training of university students in the nuclear field will include preparation and conduction of experiments, analysis of experiment data. The KMS program for background training of university students in nuclear will include: participation in the development and application of experiment procedures, preparation and carrying out experiments; carrying out pretest and post-test calculations with different computer codes; on-the-job training as operators of experiment scenarios; training of specialists in measurement and information acquisition technologies. (author)

  14. LEW 88180, LEW 87119, and ALH 85119: New EH6, EL7, and EL4 Enstatite Chondrites

    Science.gov (United States)

    Zhang, Y.; Benoit, P. H.; Sears, D. W. G.

    1993-07-01

    The EH and EL chondrites formed in a uniquely reducing environment, containing low-Fe pyroxene, abundant metal, and a number of unusual sulphides and other minerals [1]. An important aspect of their history is that while the EL chondrites consist predominantly of metamorphosed meteorites, the EH consist primarily of little-metamorphosed meteorites (e.g., [2]), and yet EL chondrites have lower equilibrium temperatures than EH chondrite [3,4]. To help understand this observation and its implication for the history of the classes, we have been searching for new enstatite chondrites, looking especially for meteorites of previously unknown chemical-petrologic class. Using our normal INAA methods [5] and sample splits of 100-200 mg, the bulk composition of nine Antarctic enstatite chondrites and one fall were determined. The data were used to assign the meteorites to chemical classes, the Ni/Ir vs. Al/V plot (Fig. 1) being especially useful since it uses the refractory element difference between EH and EL chondrites and is insensitive to metal-silicate heterogeneity. The well-analyzed Qingzhen was included to check our method. ALH84170, ALH84206, and EET87746, which Mason described as E3, E4, and E4 were all found to be EH chondrites [6]. Our data for the three paired EL3 chondrites were discussed earlier (MAC88136, 88180, and 88184) [7,8]. LEW88180, LEW87119, and ALH85119, which Mason described as type E6, E6, and E4 respectively [6], are EH, EL, and EL; thus LEW88180 and ALH85119 appear to be the first EH6 and EL4 chondrites. The compositions of kamacite, phosphide, and niningerite-alabandite (Fig. 2) for ALH84170, ALH84206, EET87746, LEW88180, and ALH85119 are consistent with Mason's petrologic type assignments [6]. The mineral composition of LEW88180 (2.7% Si and 9.4% Ni in the kamacite, 7.8% Ni in the phosphide, and 60% FeS in the niningerite) confirms our classification of this meteorite as EH6. ALH85119 contains kamacite with 0.5% Si and 7% Ni, phosphide with 46

  15. Heuristic guidelines and experimental evaluation of effective augmented-reality based instructions for maintenance in nuclear power plants

    International Nuclear Information System (INIS)

    Yim, Ho Bin; Seong, Poong Hyun

    2010-01-01

    Research highlights: → Augmented reality (AR) instructions were built for NPPs maintenance personnel. → 4-5 pieces of information at a time were optimum for AR instructions in this study. → A large variance in mode no. 5 implies these were also found to be critical amount. → Heuristic guidelines were suggested to make AR instructions more effective. - Abstract: As industrial plants and factories age, their maintenance requirements increase. Because maintenance mistakes directly increase the operating costs of a power plant, maintenance quality is significant concern to plant management. By law, all personnel working with nuclear technology must be re-trained every three years in Korea; however, as the statistical data show, the number of shutdown accidents at nuclear power plants (NPPs) due to maintenance failure is still high and needs to be reduced. Industries have started to adopt various technologies to increase the speed and accuracy of maintenance. Among those technologies, augmented reality (AR) is the latest multimedia presentation technology to be applied to plant maintenance, and it offers superior intuitiveness and user interactivity over other conventional multimedia. This empirical study aims to measure the optimum amounts of information to be delivered at a time and to identify what types of information enhance the learning ability of novices and to suggest heuristic guidelines by which to make effective AR training instructions. In the first experiment, the optimum amount of information in an AR learning environment for novices was found to be 4-5 pieces of information in a chunk by comparing results between a pre-test and an after-test. This result implies that intentionally made chunks help novices learn more effectively. In the second experiment, the AR training instruction based on the suggested heuristic guidelines was slightly more effective than other AR training instructions. Maintenance in nuclear power plants can be more reliable

  16. Synergistic effect of EMF-BEMER-type pulsed weak electromagnetic field and HPMA-bound doxorubicin on mouse EL4 T-cell lymphoma

    Czech Academy of Sciences Publication Activity Database

    Říhová, Blanka; Etrych, Tomáš; Šírová, Milada; Tomala, Jakub; Ulbrich, Karel; Kovář, Marek

    2011-01-01

    Roč. 19, č. 10 (2011), s. 890-899 ISSN 1061-186X R&D Projects: GA AV ČR IAA400200702 Institutional research plan: CEZ:AV0Z50200510; CEZ:AV0Z40500505 Keywords : EL4 T-cell lymphoma * athymic mice * DOX(HYD)-HPMA Subject RIV: EC - Immunology Impact factor: 2.696, year: 2011

  17. Protective specific immunity induced by cyclophosphamide plus tumor necrosis factor alpha combination treatment of EL4-lymphoma-bearing C57BL/6 mice.

    Science.gov (United States)

    Krawczyk, C M; Verstovsek, S; Ujházy, P; Maccubbin, D; Ehrke, M J

    1995-06-01

    A combination treatment protocol initiated 12 days after tumor injection, when the tumor was large, by administering cyclophosphamide (CY, 150 or 250 mg/kg) intraperitoneally followed by intravenous tumor necrosis factor alpha (TNF alpha, 1000 units injection) on days 13, 16, 18, 21, and 23, resulted in about 60% long-term survival (i.e., survival for at least 60 days) in the syngeneic C57BL/6 mouse/EL4 lymphoma model system. The establishment of a specific antitumor immune memory and its possible therapeutic relevance was verified by reinjecting 60-day survivors with EL4 cells; all 60-day survivors that had received the combination treatments rejected the implants and survived for a further 60 days. Thymic cellularity was reduced during treatment and its recovery appeared to correlate with long-term survival and immunity. Thymocytes from mice treated with the combination were found to express significant levels of specific anti-EL4 cytolytic activity following a 4-day stimulation culture with X-irradiated EL4 cells and low concentrations of interleukin-2. This response could not be generated with thymocytes from naive animals. In each case the effect seen with the combination of a moderate CY dose (150 mg/kg) with TNF alpha was better than that seen with either dose of CY alone and equal to or better than that seen with the higher dose of CY combined with TNF alpha. These results indicate that treatment with a single moderate dose of CY in combination with TNF alpha is effective against a large, established tumor in this murine model. Furthermore, all the long-term survivors induced by this treatment developed protective immunity against reimplanted tumor and demonstrated a long-term specific immune memory in the thymus.

  18. Transcriptomic analysis of mouse EL4 T cells upon T cell activation and in response to protein synthesis inhibition via cycloheximide treatment

    OpenAIRE

    Lim, Pek Siew; Hardy, Kristine; Peng, Kaiman; Shannon, Frances M.

    2015-01-01

    T cell activation involves the recognition of a foreign antigen complexed to the major histocompatibility complex on the antigen presenting T cell to the T cell receptor. This leads to activation of signaling pathways, which ultimately leads to induction of key cytokine genes responsible for eradication of foreign antigens. We used the mouse EL4 T cell as a model system to study genes that are induced as a result of T cell activation using phorbol myristate acetate (PMA) and calcium ionomycin...

  19. Numerical and experimental analysis of the vibratory behavior of a nuclear power plant piping system excitated by a pump

    International Nuclear Information System (INIS)

    Vatin, E.; Guillou, J.; Tephany, F.; Trollat, C.

    1993-08-01

    This paper presents a study on the dynamic response of piping systems installed in the French 1300 MWe Nuclear Power Plants. Variations in pressure are generated by a multi-staged centrifugal pump mounted on the piping system and provide a dynamic excitation of the pipe. This type of dynamic loading has led to nozzle cracks for some of the pipes, whereas, for other installations, it has not be found detrimental. This study presents an explanation of the different dynamic behavior observed at the various plants. To this end, a numerical model, calibrated with on-site measurements, is impleted. (authors). 8 figs., 1 tab., 5 refs

  20. Experimental investigation of the temperature dependence of sound velocity in the structural materials for nuclear power engineering

    International Nuclear Information System (INIS)

    Roshchupkin, V.V.; Pokrasin, M.A.; Chernov, A.I.; Semashko, N.A.; Filonenko, S.F.

    1999-01-01

    The purpose of the study consists in determination of the sound velocity temperature dependence in structural materials for nuclear power engineering. In particular, the Zr-2.5%Nb, Hastelloys-H alloys and X2.5M steel are studied. The facility for studying acoustic parameters of metals and alloys is described. The software makes it possible to obtain the results in various forms with the data stored in the memory for further analysis. The data on the above alloys obtained by use of various methods are presented and analyzed [ru

  1. Dose-rate effect of adaptive response of apoptosis and cell cycle progression induced by low-dose ionizing radiation in EL-4 lymphoma cells in vitro

    International Nuclear Information System (INIS)

    Liu Shuchun; Lu Zhe; Li Yanbo; Kang Shunai; Gong Shouliang; Zhao Wenju

    2008-01-01

    Objective: To observe the dose-rate effect of adaptive response of apoptosis and cell cycle progression induced by low-dose ionizing radiation in EL-4 lymphoma cells in vitro in order to reveal the possible mechanism of biological effect and adaptive response induced by low dose radiation. Methods: The experiment was divided into D2 (challenging dose), D1 (inductive dose) + D2 and sham-irradiation groups. EL-4 lymphoma cells were irradiated with D1 (75 mGy, 6.25-200.00 mGy·mm -1 ) and D2(1.5 Gy, 287 mGy·min -1 ), the time interval between D1 and D2 was 6 h. The percentage of apoptosis and each cell cycle phase were measured with flow cytometry. Results: When the dose rates of D1 were 6.25-50.00 mGy·min -1 , the percentages of apoptosis in the D1 + D2 group were significantly lower than those in the D2 group (P 0 /G 1 phase cells decreased significantly (P -1 , D2 is 1.5 Gy (287 mGy·min -1 ), and the time interval between D1 and D2 is 6 h, the adaptive response of apoptosis and cell cycle progression in EL-4 lymphoma cells in vitro could be induced. (authors)

  2. Transcriptomic analysis of mouse EL4 T cells upon T cell activation and in response to protein synthesis inhibition via cycloheximide treatment

    Directory of Open Access Journals (Sweden)

    Pek Siew Lim

    2016-03-01

    Full Text Available T cell activation involves the recognition of a foreign antigen complexed to the major histocompatibility complex on the antigen presenting T cell to the T cell receptor. This leads to activation of signaling pathways, which ultimately leads to induction of key cytokine genes responsible for eradication of foreign antigens. We used the mouse EL4 T cell as a model system to study genes that are induced as a result of T cell activation using phorbol myristate acetate (PMA and calcium ionomycin (I as stimuli. We were also interested to examine the importance of new protein synthesis in regulating the expression of genes involved in T cell activation. Thus we have pre-treated mouse EL4 T cells with cycloheximide, a protein synthesis inhibitor, and left the cells unstimulated or stimulated with PMA/I for 4 h. We performed microarray expression profiling of these cells to correlate the gene expression with chromatin state of T cells upon T cell activation [1]. Here, we detail further information and analysis of the microarray data, which shows that T cell activation leads to differential expression of genes and inducible genes can be further classified as primary and secondary response genes based on their protein synthesis dependency. The data is available in the Gene Expression Omnibus under accession number GSE13278. Keywords: EL4 T cell, Microarray, T cell activation, Inducible genes

  3. Interleukin-1 beta induced synthesis of protein kinase C-delta and protein kinase C-epsilon in EL4 thymoma cells: possible involvement of phosphatidylinositol 3-kinase.

    Science.gov (United States)

    Varley, C L; Royds, J A; Brown, B L; Dobson, P R

    2001-01-01

    We present evidence here that the proinflammatory cytokine, interleukin-1 beta (IL-1 beta) stimulates a significant increase in protein kinase C (PKC)-epsilon and PKC-delta protein levels and increases PKC-epsilon, but not PKC-delta, transcripts in EL4 thymoma cells. Incubation of EL4 cells with IL-1 beta induced protein synthesis of PKC-epsilon (6-fold increase) by 7 h and had a biphasic effect on PKC-delta levels with peaks at 4 h (2-fold increase) and 24 h (4-fold increase). At the level of mRNA, PKC-epsilon, but not PKC-delta levels, were induced after incubation of EL4 cells with IL-1 beta. The signalling mechanisms utilized by IL-1 beta to induce the synthesis of these PKC isoforms were investigated. Two phosphatidylinositol (PI) 3-kinase-specific inhibitors, wortmannin and LY294002, inhibited IL-1 beta-induced synthesis of PKC-epsilon. However, the PI 3-kinase inhibitors had little effect on the IL-1 beta-induced synthesis of PKC-delta in these cells. Our results indicate that IL-1 beta induced both PKC-delta and PKC-epsilon expression over different time periods. Furthermore, our evidence suggests that IL-1 beta induction of PKC-epsilon, but not PKC-delta, may occur via the PI 3-kinase pathway. Copyright 2001 S. Karger AG, Basel

  4. Activities report in nuclear physics

    NARCIS (Netherlands)

    Jansen, J. F. W.; Scholten, O.

    1987-01-01

    Experimental studies of giant resonances, nuclear structure, light mass systems, and heavy mass systems are summarized. Theoretical studies of nuclear structure, and dynamics are described. Electroweak interactions; atomic and surface physics; applied nuclear physics; and nuclear medicine are

  5. Experimental investigation and modelling of tritium washout by precipitation in the area of the nuclear power plant of Paks, Hungary.

    Science.gov (United States)

    Köllo, Z; Palcsu, L; Major, Z; Papp, L; Molnár, M; Ranga, T; Dombóvári, P; Manga, L

    2011-01-01

    Tritium occurs in nature in trace amounts, but its concentration is changing due to natural and artificial sources. Studies focusing on natural tritium have to take into account the effect of artificial sources. Also, the impact of tritium is an important issue in environmental protection, e.g. in connection with the emissions from nuclear power plants. The present work focuses on the rain washout of tritium emitted from the Paks nuclear power plant in Hungary. Rainwater collectors were placed around the plant and after a period of precipitation, rainwater was collected and analysed for tritium content. Samples were analysed using low-level liquid scintillation counting, with some also subject to the more accurate (3)He ingrowth method. The results clearly show the trace of the tritium plume emitted from the plant; however, values are only about one order of magnitude higher than environmental background levels. A washout model was devised to estimate the distribution of tritium around the plant. The model gives slightly higher concentrations than those measured in the field, but in general the agreement is satisfactory. The modelled values demonstrate that the effect of the plant on rainwater tritium levels is negligible over a distance of some kilometres. Copyright © 2010 Elsevier Ltd. All rights reserved.

  6. Theoretical and experimental investigation on adaptability of charcoal beds to containment filter venting in Italian nuclear power plant

    International Nuclear Information System (INIS)

    Caropreso, G.; Leonardi, A.; Perna, W.; Sgalambro, G.

    1989-01-01

    The work has been divided into three parts. The first one gives a description of the facilities under investigation during some selected accidental conditions, also described. The second part, which consists of an experimental work, tries to identify the behavior of charcoal beds in terms of pressure drop vs the aerosol mass loading and of aerosol retention efficiency. On the basis of the experimental findings, the prediction of the behavior of the real beds is carried out in the third part, as regards the pressure drop through the beds, related to the selected accident scenarios. In addition in this last part the results of a preliminary evaluation of the maximum decay power picked up by the beds without reaching the carbon self-ignition temperature have been reported

  7. Inelastic seismic behavior of post-installed anchors for nuclear safety related structures: Generation of experimental database

    Energy Technology Data Exchange (ETDEWEB)

    Mahadik, Vinay, E-mail: vinay.mahadik@iwb.uni-stuttgart.de; Sharma, Akanshu; Hofmann, Jan

    2016-02-15

    Highlights: • Experiments for evaluating seismic behavior of anchors were performed. • Two undercut anchor products in use in nuclear facilities were considered. • Monotonic tension, shear and cycling tension tests at different crack widths. • Crack cycling tests at constant, in-phase and out-of phase tension loads. • Characteristics for the two anchors as a function of crack width were identified. - Abstract: Post installed (PI) anchors are often employed for connections between concrete structure and components or systems in nuclear power plants (NPP) and related facilities. Standardized practices for nuclear related structures demand stringent criteria, which an anchor has to satisfy in order to qualify for use in NPP related structures. In NPP and related facilities, the structure–component interaction in the event of an earthquake depends on the inelastic behavior of the concrete structure, the component system and also the anchorage system that connects them. For analysis, anchorages are usually assumed to be rigid. Under seismic actions, however, it is known that anchors may undergo significant plastic displacement and strength degradation. Analysis of structure–component interaction under seismic loads calls for numerical models simulating inelastic behavior of anchorage systems. A testing program covering different seismic loading scenarios in a reasonably conservative manner is required to establish a basis for generating numerical models of anchorage systems. Currently there is a general lack of modeling techniques to consider the inelastic behavior of anchorages in structure–component interaction under seismic loads. In this work, in view of establishing a basis for development of numerical models simulating the inelastic behavior of anchors, seismic tests on two different undercut anchors qualified for their use in NPP related structures were carried out. The test program was primarily based on the DIBt-KKW-Leitfaden (2010) guidelines

  8. Experimental facility with two-phase flow and with high concentration of non-condensable gases for research and development of emergency cooling system of advanced nuclear reactors

    International Nuclear Information System (INIS)

    Macedo, Luiz Alberto; Baptista Filho, Benedito Dias

    2006-01-01

    The development of emergency cooling passive systems of advanced nuclear reactors requires the research of some relative processes to natural circulation, in two-phase flow conditions involving condensation processes in the presence of non-condensable gases. This work describes the main characteristics of the experimental facility called Bancada de Circulacao Natural (BCN), designed for natural circulation experiments in a system with a hot source, electric heater, a cold source, heat exchanger, operating with two-phase flow and with high concentration of noncondensable gas, air. The operational tests, the data acquisition system and the first experimental results in natural circulation are presented. The experiments are transitory in natural circulation considering power steps. The distribution of temperatures and the behavior of the flow and of the pressure are analyzed. The experimental facility, the instrumentation and the data acquisition system demonstrated to be adapted for the purposes of research of emergency cooling passive systems, operating with two-phase flow and with high concentration of noncondensable gases. (author)

  9. Experimental measurements and nuclear model calculations on the excitation functions of $^{nat}Ce(^{3}He, xn)$ and $^{141}$therapeutic radionuclide $^{140}$Nd

    CERN Document Server

    Hilgers, K; Coenen, H H; Qaim, S M

    2005-01-01

    For production of the therapy related Auger electron emitting neutron deficient nuclide /sup 140/Nd (T/sub fraction 1/2/=3.37d) two routes were investigated: the nuclear reaction range from 15 to 36 MeV and the reaction /sup 141/Pr(p,2n)/sup 140isotopes, namely /sup 139/Nd and /sup 141/Nd, as well as to cerium(IV)-oxide and praseodymium (III)-oxide were obtained by sedimentation and the conventional stacked-foil technique was used for cross section measurements. All the experimental data obtained in this work were compared with the results of theoretical calculations using the exciton model code ALICE-IPPE as well as with literature experimental data, if available. In general, good agreement between experimental and theoretical results was found. The theoretical thick target yields of all the product nuclides were calculated from the measured excitation functions. The theoretical thick target yield of amounts to 12 MBq/mu Acenterdoth and over the energy range E/sub p/=30rightward arrow15 Me V to 210 MBq/mu; A...

  10. Energy coupling of nuclear bursts in and above the ocean surface: source region calculations and experimental validation

    International Nuclear Information System (INIS)

    Clarke, D.B.; Harben, P.E.; Rock, D.W.; White, J.W.; Piacsek, A.

    1997-01-01

    In support of the Comprehensive Test Ban, research is under way on the long range propagation of signals from nuclear explosions in deep underwater sound (SOFAR) channel. Initially our work at LLNL on signals in the source region considered explosions in or above deep ocean. We studied the variation of wave properties and source region energy coupling as a function of height or depth of burst. Initial calculations on the CALE hydrodynamics code were linked at a few hundred milliseconds to a version of NRL's weak code, NPE, which solves the nonlinear progressive wave equation. The simulation of the wave propagation was carried down to 5000 m depth and out to 10,000 m range. We have completed ten such simulations at a variety of heights and depths below the ocean surface

  11. Instrumentation report 1: specification, design, calibration, and installation of instrumentation for an experimental, high-level, nuclear waste storage facility

    International Nuclear Information System (INIS)

    Brough, W.G.; Patrick, W.C.

    1982-01-01

    The Spent Fuel Test-Climax (SFT-C) is being conducted 420 m underground at the Nevada Test Site under the auspices of the US Department of Energy. The test facility houses 11 spent fuel assemblies from an operating commercial nuclear reactor and numerous other thermal sources used to simulate the near-field effects of a large repository. We developed a large-scale instrumentation plan to ensure that a sufficient quality and quantity of data were acquired during the three- to five-year test. These data help satisfy scientific, operational, and radiation safety objectives. Over 800 data channels are being scanned to measure temperature, electrical power, radiation, air flow, dew point, stress, displacement, and equipment operation status (on/off). This document details the criteria, design, specifications, installation, calibration, and current performance of the entire instrumentation package

  12. Experimental and numerical investigation of water flow through spacer grids of nuclear fuel elements using the Open FOAM code

    International Nuclear Information System (INIS)

    Vidal, Guilherme A.M.; Vieira, Tiago A.S.; Castro, Higor F.P.

    2017-01-01

    With the advancement and development of computational tools, the studies of thermofluidodynamic behavior in nuclear fuel elements have been developed in recent years. Of the devices present in these elements, the spacing grids received more attention. They have kept the fuel rods equally spaced and have fins that aim to improve the heat transfer process between the water and the fuel element. Therefore, the grids present an important structural and thermal function. This work was carried out with the purpose of verifying and validating simulations of spacer grids using OpenFOAM (2017) software of Computational Fluid Dynamics (CFD). The simulations were validated using results obtained through the commercial CFD program, Ansys CFX, and experiments available in the literature and obtained in test sections assembled on the Water-Air Circuit (CCA) of the CDTN thermo-hydraulic laboratory

  13. Experimental research on the flow field uniformity in the filter house of a nuclear air cleaning system

    International Nuclear Information System (INIS)

    Jiang Feng; Yang Jun; Ye Suisheng

    2000-01-01

    The filter house structure is designed using similarity laws showing that the filter house structure causes a non-uniform flow field. The flow field is also measured experimentally. The air flow field is analyzed for different conditions. The results show that: (1) The HEPA filters affect the dispersion of the air flow; (2) The appropriate angle for air input to the rectifier satisfies the requirements for uniform air flow for the test conditions; (3) The rectifier has little influence on the air flow for operating conditions

  14. Statistical investigations of the failure behaviour of components in the AVR-experimental nuclear power plant. Vol. 1

    International Nuclear Information System (INIS)

    Hennings, W.

    1989-08-01

    From operational reports of the years 1970 to 1984, failure rates of valves in gas circuits of the AVR experimental power plant were determined. Also, potential influences of environmental and operational conditions were investigated. The resulting failure rates are for manual valves app. 0,1.10 -6 /h, for pneumatic valves between 3 and 9.10 -6 /h, for solenoid valves between 1,5 and 4.10 -6 /h and for control valves between 12 and 41.10 -6 /h. (orig.) [de

  15. Nuclear physics

    International Nuclear Information System (INIS)

    Kamal, Anwar

    2014-01-01

    Explains the concepts in detail and in depth. Provides step-by-step derivations. Contains numerous tables and diagrams. Supports learning and teaching with numerous worked examples, questions and problems with answers. Sketches also the historical development of the subject. This textbook explains the experimental basics, effects and theory of nuclear physics. It supports learning and teaching with numerous worked examples, questions and problems with answers. Numerous tables and diagrams help to better understand the explanations. A better feeling to the subject of the book is given with sketches about the historical development of nuclear physics. The main topics of this book include the phenomena associated with passage of charged particles and radiation through matter which are related to nuclear resonance fluorescence and the Moessbauer effect., Gamov's theory of alpha decay, Fermi theory of beta decay, electron capture and gamma decay. The discussion of general properties of nuclei covers nuclear sizes and nuclear force, nuclear spin, magnetic dipole moment and electric quadrupole moment. Nuclear instability against various modes of decay and Yukawa theory are explained. Nuclear models such as Fermi Gas Model, Shell Model, Liquid Drop Model, Collective Model and Optical Model are outlined to explain various experimental facts related to nuclear structure. Heavy ion reactions, including nuclear fusion, are explained. Nuclear fission and fusion power production is treated elaborately.

  16. Development and optimization of nuclear heating and gamma flux measurement techniques in experimental reactors: identification, mastery, treatment and reduction of uncertainties

    International Nuclear Information System (INIS)

    Amharrak, H.

    2012-01-01

    This thesis work focuses on the needs for qualification of neutron and photonics calculation schemes in the future Jules Horowitz technological Reactor (RJH) and Pressurized Water Reactors (PWR). It is necessary to establish reliable measurement results with well defined associated uncertainties, for qualification and/or validation. The objective of this thesis is to develop and to improve the nuclear heating measurement methods (especially gamma photons) in MINERVE and EOLE experimental reactors at CEA-Cadarache, using thermo-luminescent detectors (TLD), optically stimulated luminescence detectors (OSLD) and an ionization chamber. It is to identify, prioritize, treat and reduce the various sources of uncertainty and systematic bias associated with the measurement. In a previous study, where nuclear heating was estimated from an integrated radiation dose by TLD in MINERVE and EOLE reactors, it has been shown that dose calculation underestimated the experiment by 25% with a total uncertainty of 15% (2σ). This systematic bias observed has been largely attributed to a lack of nuclear data used to perform the calculations. Therefore, in this work a new series of experiments was set up in the MINERVE reactor to reduce the measurement uncertainties, and better understand the origins of the discrepancies with the modeling. These experiments were carried out in an aluminum or hafnium surrounding (in specifically designed boxes) using a new procedure and analysis methodology. In these experiments, the TLD are calibrated individually, the repeatability of the measurement is experimentally evaluated and the laws of TLD heat are optimized. These improvements are subsequently used for the measurement of nuclear heating in AMMON program (EOLE reactor), dedicated to the qualification of neutron and photonics calculation schemes in the RJH reactor. The measurements of the gamma emitted, with a delay (delayed gamma) after shutdown of the MINERVE reactor, were also carried out

  17. An overview of experimental results obtained under the prestressed concrete nuclear pressure vessel development program at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Naus, D.J.

    1979-01-01

    Under the Prestressed Concrete Nuclear Pressure Development Program at the Oak Ridge National Laboratory, various aspects of Prestressed Concrete Pressure Vessels (PCPVs) are investigated with respect to reliability, structural performance, constructability, and economy. These investigations are conducted under the High-Temperature Gas-Cooled Reactor (HTGR) Program and the Gas-Cooled Fast Reactor (GCFR) Program. The objectives are to: (1) provide technical support to ongoing PCPV design activities, (2) contribute to the overall technological data base, and (3) provide independent review and evaluations. Specific areas of interest at present include finite-element analysis development, materials and structural behaviour tests, instrumentation evaluations and development, and structural model tests. The following provides an overview of both the HTGR and GCFR PCPV activities and a summary of recent experimental results

  18. Experimental investigation of hydrous pyrolysis of diesel fuel and the effect of pyrolysis products on performance of the candidate nuclear waste repository at Yucca Mountain, Nevada

    International Nuclear Information System (INIS)

    Jackson, K.J.; Carroll, S.A.

    1994-01-01

    It is thought that a significant amount of diesel fuel and other hydrocarbon-rich phases may remain inside the candidate nuclear waste repository at Yucca Mountain after construction and subsequent emplacement of radioactive waste. Although the proposed repository horizon is above the water table, the remnant hydrocarbon phases may react with hydrothermal solutions generated by high temperature conditions that will prevail for a period of time in the repository. The preliminary experimental results of this study show that diesel fuel hydrous pyrolysis is minimal at 200 degrees C and 70 bars. The composition of the diesel fuel remained constant throughout the experiment and the concentration of carboxylic acids in the aqueous phases was only slightly above the detection limit (1-2 ppm) of the analytical technique

  19. Radiation protection, radioactive waste management and site monitoring at the nuclear scientific experimental and educational centre IRT-Sofia at INRNE-BAS.

    Science.gov (United States)

    Mladenov, Al; Stankov, D; Nonova, Tz; Krezhov, K

    2014-11-01

    This article identifies important components and describes the safe practices in implementing radiation protection and radioactive waste management programmes, and in their optimisation at the Nuclear Scientific Experimental and Educational Centre with research reactor IRT at INRNE-BAS. It covers the instrumentation and personal protective equipment and organisational issues related to the continuous site monitoring. The reactor is under major reconstruction and the measures applied to radiation monitoring of environment and working area focused on restricting the radiation exposure of the staff as well as compliance with international good practices related to the environmental and public radiation safety requirements are also addressed. © The Author 2014. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  20. Effect of the size of experimental channels of the lead slowing-down spectrometer SVZ-100 (Institute for Nuclear Research, Moscow) on the moderation constant

    Energy Technology Data Exchange (ETDEWEB)

    Latysheva, L. N.; Bergman, A. A.; Sobolevsky, N. M., E-mail: sobolevs@inr.ru [Russian Academy of Sciences, Institute for Nuclear Research (Russian Federation); Ilic, R. D. [Vinca Institute of Nuclear Sciences (Serbia)

    2013-04-15

    Lead slowing-down (LSD) spectrometers have a low energy resolution (about 30%), but their luminosity is 10{sup 3} to 10{sup 4} times higher than that of time-of-flight (TOF) spectrometers. A high luminosity of LSD spectrometers makes it possible to use them to measure neutron cross section for samples of mass about several micrograms. These features specify a niche for the application of LSD spectrometers in measuring neutron cross sections for elements hardly available in macroscopic amounts-in particular, for actinides. A mathematical simulation of the parameters of SVZ-100 LSD spectrometer of the Institute for Nuclear Research (INR, Moscow) is performed in the present study on the basis of the MCNPX code. It is found that the moderation constant, which is the main parameter of LSD spectrometers, is highly sensitive to the size and shape of detecting volumes in calculations and, hence, to the real size of experimental channels of the LSD spectrometer.

  1. Effect of the size of experimental channels of the lead slowing-down spectrometer SVZ-100 (Institute for Nuclear Research, Moscow) on the moderation constant

    International Nuclear Information System (INIS)

    Latysheva, L. N.; Bergman, A. A.; Sobolevsky, N. M.; Ilić, R. D.

    2013-01-01

    Lead slowing-down (LSD) spectrometers have a low energy resolution (about 30%), but their luminosity is 10 3 to 10 4 times higher than that of time-of-flight (TOF) spectrometers. A high luminosity of LSD spectrometers makes it possible to use them to measure neutron cross section for samples of mass about several micrograms. These features specify a niche for the application of LSD spectrometers in measuring neutron cross sections for elements hardly available in macroscopic amounts—in particular, for actinides. A mathematical simulation of the parameters of SVZ-100 LSD spectrometer of the Institute for Nuclear Research (INR, Moscow) is performed in the present study on the basis of the MCNPX code. It is found that the moderation constant, which is the main parameter of LSD spectrometers, is highly sensitive to the size and shape of detecting volumes in calculations and, hence, to the real size of experimental channels of the LSD spectrometer.

  2. Estimation of radioactive contamination of soils from the "Balapan" and the "Experimental field" technical areas of the Semipalatinsk nuclear test site.

    Science.gov (United States)

    Evseeva, T; Belykh, E; Geras'kin, S; Majstrenko, T

    2012-07-01

    In spite of the long history of the research, radioactive contamination of the Semipalatinsk nuclear test site (SNTS) in the Republic of Kazakhstan has not been adequately characterized. Our cartographic investigation has demonstrated highly variable radioactive contamination of the SNTS. The Cs-137, Sr-90, Eu-152, Eu-154, Co-60, and Am-241 activity concentrations in soil samples from the "Balapan" site were 42.6-17646, 96-18250, 1.05-11222, 0.6-4865, 0.23-4893, and 1.2-1037 Bq kg(-1), correspondingly. Cs-137 and Sr-90 activity concentrations in soil samples from the "Experimental field" site were varied from 87 up to 400 and from 94 up to 1000 Bq kg(-1), respectively. Activity concentrations of Co-60, Eu-152, and Eu-154 were lower than the minimum detectable activity of the method used. Concentrations of naturally occurring radionuclides (K-40, Ra-226, U-238, and Th-232) in the majority of soil samples from the "Balapan" and the "Experimental field" sites did not exceed typical for surrounding of the SNTS areas levels. Estimation of risks associated with radioactive contamination based on the IAEA clearance levels for a number of key radionuclides in solid materials shows that soils sampled from the "Balapan" and the "Experimental field" sites might be considered as radioactive wastes. Decrease in specific activity of soil from the sites studied up to safety levels due to Co-60, Cs-137, Sr-90, Eu-152, Eu-154 radioactive decay and Am-241 accumulation-decay will occur not earlier than 100 years. In contrast, soils from the "Experimental field" and the "Balapan" sites (except 0.5-2.5 km distance from the "Chagan" explosion point) cannot be regarded as the radioactive wastes according safety norms valid in Russia and Kazakhstan. Copyright © 2012 Elsevier Ltd. All rights reserved.

  3. Nuclear physics

    International Nuclear Information System (INIS)

    Patel, S.B.

    1991-01-01

    This book is a simple and direct introduction to the tools of modern nuclear physics, both experimental and mathematical. Emphasizes physical intuition and illuminating analogies, rather than formal mathematics. Topics covered include particle accelerators, radioactive series, types of nuclear reactions, detection of the neutrino, nuclear isomerism, binding energy of nuclei, fission chain reactions, and predictions of the shell model. Each chapter contains problems and illustrative examples. Pre-requisites are calculus and elementary vector analysis

  4. Thermal analysis of the modified Hallum Nuclear Power Facility cask using experimentally obtained thermal boundary conditions corresponding to an engulfing open pool fire

    International Nuclear Information System (INIS)

    Longenbaugh, R.S.; Sanchez, L.C.; Gregory, J.J.

    1987-08-01

    This report presents the two-dimensional heat transfer analysis of an open pool fire surrounding a modified radioactive materials transport cask. The cask is an older cask that was used by the Hallum Nuclear Power Facility (HNPF). The HNPF cask did not have a neutron shielding region but was modified to include one for testing purposes. Analysis of the thermal effects of an engulfing open pool fire was performed with the use of the heat transfer code Q/TRAN, which had previously been used in thermal benchmarking problems for spent nuclear fuel casks. Boundary condition data for the analysis were derived from experimental open pool fire tests of large-scale calorimeter test articles performed at SNL that produced information about cask surface heat flux versus surface temperature relationships. Data analysis was directed toward a determination of the thermal response of the cask, particularly the extent of lead melt since lead is used within the HNPF cask's gamma-shielding region. Parameters, such as surface emissivity and internal heat generation rate, can affect the results of the thermal analysis which control the amount of lead melt. A parameter sensitivity analysis was performed using a one-dimensional model to describe how surface emissivity and internal heat generation rates affect the temperature distribution within the cask. The information from this analysis was used to determine the range of parameters for the two-dimensional thermal analysis. 13 refs., 57 figs., 8 tabs

  5. Experimental assessment of the thermal performance of storage canister/holding fixture configurations for the Los Alamos Nuclear Materials Storage Facility

    International Nuclear Information System (INIS)

    Bernardin, J.D.; Naffziger, D.C.; Gregory, W.S.

    1997-11-01

    This report presents experimental results on the thermal performance of various nested canister configurations and canister holding fixtures to be used in the Los Alamos Nuclear Materials Storage Facility. The experiment consisted of placing a heated aluminum billet (to represent heat-generating nuclear material) inside curved- and flat-bottom canisters with and without holding plate fixtures and/or extended fin surfaces. Surface temperatures were measured at several locations on the aluminum billet, inner and outer canisters, and the holding plate fixture to assess the effectiveness of the various configurations in removing and distributing the heat from the aluminum billet. Results indicated that the curved-bottom canisters, with or without holding fixtures, were extremely ineffective in extracting heat from the aluminum billet. The larger thermal contact area provided by the flat-bottom canisters compared with the curved-bottom design, greatly enhanced the heat removal process and lowered the temperature of the aluminum billet considerably. The addition of the fixture plates to the flat-bottom canister geometry greatly enhances the heat removal rates and lowers the canister operating temperatures considerably. The addition of the fixture plates to the flat-bottom canister geometry greatly enhances the heat removal rates and lowers the canister operating temperatures considerably. Finally, the addition of extended fin surfaces to the outer flat-bottom canister positioned on a fixture plate, reduced the canister temperatures still further

  6. Publication of nuclear magnetic resonance experimental data with semantic web technology and the application thereof to biomedical research of proteins.

    Science.gov (United States)

    Yokochi, Masashi; Kobayashi, Naohiro; Ulrich, Eldon L; Kinjo, Akira R; Iwata, Takeshi; Ioannidis, Yannis E; Livny, Miron; Markley, John L; Nakamura, Haruki; Kojima, Chojiro; Fujiwara, Toshimichi

    2016-05-05

    The nuclear magnetic resonance (NMR) spectroscopic data for biological macromolecules archived at the BioMagResBank (BMRB) provide a rich resource of biophysical information at atomic resolution. The NMR data archived in NMR-STAR ASCII format have been implemented in a relational database. However, it is still fairly difficult for users to retrieve data from the NMR-STAR files or the relational database in association with data from other biological databases. To enhance the interoperability of the BMRB database, we present a full conversion of BMRB entries to two standard structured data formats, XML and RDF, as common open representations of the NMR-STAR data. Moreover, a SPARQL endpoint has been deployed. The described case study demonstrates that a simple query of the SPARQL endpoints of the BMRB, UniProt, and Online Mendelian Inheritance in Man (OMIM), can be used in NMR and structure-based analysis of proteins combined with information of single nucleotide polymorphisms (SNPs) and their phenotypes. We have developed BMRB/XML and BMRB/RDF and demonstrate their use in performing a federated SPARQL query linking the BMRB to other databases through standard semantic web technologies. This will facilitate data exchange across diverse information resources.

  7. The appropriateness of the systematic framework to develop diagnosis procedures of nuclear power plants-an experimental verification

    International Nuclear Information System (INIS)

    Park, Jinkyun; Jung, Wondea

    2006-01-01

    It has been well recognized that a diagnosis procedure that allows operators to successfully identify the nature of an on-going event is inevitable for an effective and appropriate recovery. Unfortunately, studies for a framework that can suggest a unified and consistent process in constructing a serviceable diagnosis procedure seem to be scant. Thus, Park et al. have suggested a systematic framework that can be used to construct a useful diagnosis procedure. In addition, the diagnosis procedure that is currently in use at the reference nuclear power plant (NPP) is reformed in order to demonstrate the appropriateness of the suggested framework. However, the necessity of a well-designed experiment is proposed to confirm the appropriateness of the suggested framework. In this regard, in this study, an experiment is conducted using a full-scope simulator of the reference NPP. From the experiment, two sets of operators' diagnosis performance data are collected, and then they are compared to investigate the change of an operator's diagnosis performance with respect to two types of diagnosis procedures. As a result, it is shown that an operator's diagnosis performance is improved when the revised diagnosis procedure is used. Therefore, it is reasonable to conclude that the suggested framework is useful in constructing an effective diagnosis procedure

  8. Wind tunnel experimental study on effect of inland nuclear power plant cooling tower on air flow and dispersion of pollutant

    International Nuclear Information System (INIS)

    Qiao Qingdang; Yao Rentai; Guo Zhanjie; Wang Ruiying; Fan Dan; Guo Dongping; Hou Xiaofei; Wen Yunchao

    2011-01-01

    A wind tunnel experiment for the effect of the cooling tower at Taohuajiang nuclear power plant on air flow and dispersion of pollutant was introduced in paper. Measurements of air mean flow and turbulence structure in different directions of cooling tower and other buildings were made by using an X-array hot wire probe. The effects of the cooling tower and its drift on dispersion of pollutant from the stack were investigated through tracer experiments. The results show that the effect of cooling tower on flow and dispersion obviously depends on the relative position of stack to cooling towers, especially significant for the cooling tower parallel to stack along wind direction. The variation law of normalized maximum velocity deficit and perturbations in longitudinal turbulent intensity in cooling tower wake was highly in accordance with the result of isolated mountain measured by Arya and Gadiyaram. Dispersion of pollutant in near field is significantly enhanced and plume trajectory is changed due to the cooling towers and its drift. Meanwhile, the effect of cooling tower on dispersion of pollutant depends on the height of release. (authors)

  9. Ultimate storage of spent fuel elements from the AVR experimental nuclear power plant in the Asse Salt Mine

    Energy Technology Data Exchange (ETDEWEB)

    Wolf, J.

    1975-02-15

    The present paper is intended to serve as the basis for the licensing procedures both in respect of the transport and storage techniques and also for the ultimate storage itself. In regard to the technique it will be shown on the basis of design drawings and calculations that the handling, transport and storage of the fuel elements can be safely carried out in accordance with the regulations in force. In regard to the ultimate storage itself, since no highly radioactive wastes with a long-lived actinide content have yet been stored, it will be necessary to show that an unacceptable contamination of the biosphere will be avoided even in the long term under all anticipated conditions. It will further be necessary to show by calculations and suitable tests, in view of the radioactive gas and fissile material content, that no danger due to gas release from the fuel elements will arise during the operating life of the mine and that a nuclear criticality risk can be excluded for all time.

  10. US team measurements during the June 1987 experimental HT release at the Chalk River Nuclear Laboratories, Ontario, Canada

    International Nuclear Information System (INIS)

    Jalbert, R.A.; Murphy, C.E.

    1988-01-01

    In June 1987, an experiment was performed at the Chalk River Nuclear Laboratories in Ontario, Canada, to study the oxidation of HT in the environment. The experiment involved a 30-minute release of 100 Ci of HT to the atmosphere at an elevation of one meter. The HTOHT ratios were shown to slowly increase downwind (/approximately/4 /times/ 10/sup /minus/5/ at 50 meters to almost 10/sup /minus/3 at 400 meters) as conversion of HT takes place. For several days after the release, HTO concentrations in the atmosphere remained elevated. Freeze-dried water from vegetation samples was found to be very low in HTO immediately after the release suggesting a very low direct uptake of HTO in air by vegetation. The tritiated water concentration increased during the first day, peaking during the second day (about 400 to 600 pCiml of water at 50 meters from the source) and decreasing by the end of the second day. The organically bound tritium continued to accumulate during the period following exposure (about 10 pCigm dry weight at 50 meters after two days). 4 refs., 6 figs., 2 tabs

  11. U.S. team measurements during the June 1987 experimental HT release at the Chalk River Nuclear Laboratories, Ontario, Canada

    International Nuclear Information System (INIS)

    Jalbert, R.A.; Murphy, C.E.

    1988-01-01

    In June 1987, an experiment was performed at the Chalk River Nuclear Laboratories in Ontario, Canada, to study the oxidation of HT in the environment. The experiment involved a 30-minute release of 3.54 TBq (95.7 Ci) of HT to the atmosphere at an elevation of one meter. The HTO/HT ratios were shown to slowly increase downwind (-- 4 x 10/sup -5/ at 50 meters to almost 10/sup -3/ at 400 meters) as conversion of HT takes place. For several days after the release, HTO concentrations in the atmosphere remained elevated. Freeze-dried water from vegetation samples was found to be very low in HTO immediately after the release suggesting a very low direct uptake of HTO in air by vegetation. The free-HTO concentration in vegetation increased during the first day, peaking during the second day (about 1.5 - 3.0 x 10/sup 4/ Bq/L at 50 meters from the source) and decreasing by the end of the second day. The organically bound tritium continued to accumulate during the period following exposure (about 400 Bq/kg dry weight at 50 meters after two days)

  12. Extension of the energy range of the experimental activation cross-sections data of longer-lived products of proton induced nuclear reactions on dysprosium up to 65MeV.

    Science.gov (United States)

    Tárkányi, F; Ditrói, F; Takács, S; Hermanne, A; Ignatyuk, A V

    2015-04-01

    Activation cross-sections data of longer-lived products of proton induced nuclear reactions on dysprosium were extended up to 65MeV by using stacked foil irradiation and gamma spectrometry experimental methods. Experimental cross-sections data for the formation of the radionuclides (159)Dy, (157)Dy, (155)Dy, (161)Tb, (160)Tb, (156)Tb, (155)Tb, (154m2)Tb, (154m1)Tb, (154g)Tb, (153)Tb, (152)Tb and (151)Tb are reported in the 36-65MeV energy range, and compared with an old dataset from 1964. The experimental data were also compared with the results of cross section calculations of the ALICE and EMPIRE nuclear model codes and of the TALYS nuclear reaction model code as listed in the latest on-line libraries TENDL 2013. Copyright © 2015. Published by Elsevier Ltd.

  13. Experimental validation of the decay power calculation code and nuclear databases - FISPACT-97 and EAF-97 and FENDL/A-2.0

    International Nuclear Information System (INIS)

    Sublet, J.

    1998-01-01

    The calculation of activation inventories is a key input to virtually all aspects of the safety and environmental assessment of fusion power devices, such as ITER. For the licensing of such devices, regulatory authorities will require proof that the calculations of activation, and calculations to which activation quantities are inputs, are either correct or conservative. An important aspect of activation is decay heat power. In fusion power plants, decay power arises after shutdown from the energy released in the decay of the products of neutron activation, mainly from gamma and beta rays. Computation of the decay power is performed by sophisticated computer codes which solve the large number of coupled differential equations which govern the generation and decay chains for the many nuclides involved. They rely on a large volume of nuclear data, both neutron activation cross-sections and radioactive decay data. Validation of decay power code predictions by means of direct comparison with integral data measurements of sample structural materials under fusion-typical neutron spectra generates confidence in the decay power values calculated. It also permits an assessment of the adequacy of the methods and nuclear data and indicates any inaccuracy or omission that may have led to erroneous results. No experimental data on decay power existed for fusion reactor structural materials and irradiation conditions before a series of experiments were performed using the Fusion Neutron Source FNS facility at the Japan Atomic Energy Research Institute JAERI. Fusion relevant material samples were irradiated in a simulated D-T neutron field for times up to 7 hours and the decay power so generated measured for cooling times up to three months. Using the highly sensitive Whole Energy Absorption Spectrometer (WEAS) method, both β and γ rays decay energies were measured at selected cooling times as early as one minute after the irradiation ended. Coupled to the experiments, and at

  14. Growth of the parvovirus minute virus of mice MVMp3 in EL4 lymphocytes is restricted after cell entry and before viral DNA amplification: cell-specific differences in virus uncoating in vitro.

    OpenAIRE

    Previsani, N; Fontana, S; Hirt, B; Beard, P

    1997-01-01

    Two murine parvoviruses with genomic sequences differing only in 33 nucleotides (8 amino acids) in the region coding for the capsid proteins show different host cell specificities: MVMi grows in EL4 T lymphocytes and MVMp3 grows in A9 fibroblasts. In this study we compared the courses of infections with these two viruses in EL4 cells in order to investigate at which step(s) the infection process of MVMp3 is interrupted. The two viruses bound equally well to EL4 cells, and similar amounts of M...

  15. An experimental study on a training support system utilizing trainee's eye gaze point and think aloud protocol for diagnosing nuclear power plant anomalies

    International Nuclear Information System (INIS)

    Ozawa, Takahisa; Samejima, Ryouta; Shimoda, Hiroshi; Yoshikawa, Hidekazu

    2003-01-01

    An experimental system has been developed for aiming at supporting the simulator training of diagnosis nuclear power plant anomaly, where an expert provides the instructions to a trainee by his/her own educational and experienced point of view. This system has several characteristics as follows: (1) the expert can provide the instruction through the local area network or the Internet, (2) the training task is the detection of the primary cause of plant anomaly, which is not including the plant operation but requires only thinking, and (3) the system can automatically detects the trainee's view-point and think aloud protocols and provide these two types of information to the expert in real time for supporting his/her instruction. A laboratory experiment using this system was conducted, where an expert, who had really engaged in plant operation as a chief operator, was employed as the instructor for novice students. As the result of analyzing the experimental data, it was found that the two types of information, trainee's viewpoints and his verbal protocols, have some potential of effectiveness for supporting the instructor to estimate the trainees diagnostic thinking process and provide the instruction. (author)

  16. Development of a standard database for FBR core nuclear design (XI). Analysis of the Experimental Fast Reactor 'JOYO' MK-I start-up test and operation data

    International Nuclear Information System (INIS)

    Yokoyama, Kenji; Numata, Kazuyuki

    2000-03-01

    As a recent research, Japan Nuclear Cycle Development Institute (JNC) develops a database of integral data in addition to the JUPITER experiments, aiming at further improvement for accuracy and reliability. In this report, the authors describe the evaluation of the C/E values and the sensitivity analysis for the Experimental Fast Reactor 'JOYO' MK-I core. The minimal criticality, sodium void reactivity worth, fuel assembly worth and burn-up coefficient were analyzed. The results of both the minimal criticality and the fuel assembly worth, which were calculated by the standard analytical method for JUPITER experiments, agreed well with the measured values. On the other hand, the results of the sodium void reactivity worth have a tendency to overestimate. As for the burn-up coefficient, it was seen that the C/E values had a dispersion among the operation cycles. The authors judged that further investigation for the estimation of the experimental error will increase the applicability of the integral data to the adjusted library. Furthermore, sensitivity analyses for the minimal criticality, sodium void reactivity worth and fuel assembly worth showed the characteristics of 'JOYO' MK-I core in comparison with ZPPR-9 core of JUPITER experiments. (J.P.N.)

  17. Calcium plays a key role in paraoxon-induced apoptosis in EL4 cells by regulating both endoplasmic reticulum- and mitochondria-associated pathways.

    Science.gov (United States)

    Li, Lan; Du, Yi; Ju, Furong; Ma, Shunxiang; Zhang, Shengxiang

    2016-01-01

    Paraoxon (POX) is one of the most toxic organophosphorus pesticides, but its toxic mechanisms associated with apoptosis remain unclear. The aim of this study was to investigate calcium-associated mechanisms in POX-induced apoptosis in EL4 cells. EL4 cells were exposed to POX for 0-16 h. EGTA was used to chelate Ca(2+ ) in extracellular medium, and heparin and procaine were used to inhibit Ca(2+ )efflux from the endoplasmic reticulum (ER). Z-ATAD-FMK was used to inhibit caspase-12 activity. The apoptotic rate assay, western blotting and immunocytochemistry (ICC) were used to reveal the mechanisms of POX-induced apoptosis. POX significantly increased the expression and activation of caspase-12 and caspase-3, enhanced expression of calpain 1 and calpain 2, and induced the release of cyt c, but did not change the expression of Grp 78. Inhibiting caspase-12 activity alleviated POX-induced upregulation of calpain 1 and caspase-3, promoted POX-induced upregulation of calpain 2, and reduced POX-induced cyt c release, suggesting that there was a cross-talk between the ER-associated pathway and mitochondria-associated apoptotic signals. Attenuating intracellular calcium concentration with EGTA, heparin or procaine decreased POX-induced upregulation of calpain 1, calpain 2, caspase-12 and caspase-3, and reduced POX-induced cyt c release. After pretreatment with EGTA or procaine, POX significantly promoted expression of Grp 78. Calcium played a key role in POX-induced apoptosis in EL4 cells by regulating both ER- and mitochondria-associated pathways. The cross-talk of ER- and mitochondria-associated pathways was accomplished through calcium signal.

  18. Nuclear fuel behaviour modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-07-01

    The Technical Committee Meeting (TCM) included separate sessions on the specific topics of fuel thermal performance and fission product retention. On thermal performance, it is apparent that the capability exists to measure conductivity in high burnup fuel either by out-of-pile measurement or by instrumentation of test reactor rods. State-of-the-art modelling codes contain models for the conductivity degradation process, and hence adequate predictions of fuel temperature are achievable. Concerning fission product release, it is clear that many groups around the world are actively investigating the subject, with experimental and modelling programmes being pursued. However, a general consensus on the exact mechanisms of gas release and related gas bubble swelling has yet to emerge, even at medium burnup levels. Fission gas phenomena, not only the release to open volumes, but the whole sequence of processes taking place prior to this, need to be modelled in any modern fuel performance code. The presence of gaseous fission products may generate rapid fuel swelling during power transients, and this can cause PCI and rod failure. At high burnups, the quantity of released gases could give rise to pressures exceeding the safe limits. Modelling of pellet-cladding interaction (PCI) effects during transient operation is also an active area of study for many groups. In some situations a purely empirical approach to failure modelling can be justified, while for other applications a more detailed mechanistic approach is required. Another aspect of cladding modelling which was featured at the TCM concerned corrosion and hydriding. Although this issue can be the main life-limiting factor on fuel duty, it is apparent that modelling methods, and the experimental measurement techniques that underpin them, are adequate. A session was included on MOX fuel modelling. Substantial programmes of work, especially by the MOX vendors, appear to be underway to bring the level of understanding

  19. Experimental study of the temperature distribution in the TRIGA IPR-R1 Brazilian research reactor; Investigacao experimental da distribuicao de temperaturas no reator nuclear de pesquisa TRIGA IPR-R1

    Energy Technology Data Exchange (ETDEWEB)

    Mesquita, Amir Zacarias

    2005-07-01

    The TRIGA-IPR-R1 Research Nuclear Reactor has completed 44 years in operation in November 2004. Its initial nominal thermal power was 30 kW. In 1979 its power was increased to 100 kW by adding new fuel elements to the reactor. Recently some more fuel elements were added to the core increasing the power to 250 kW. The TRIGA-IPR-R1 is a pool type reactor with a natural circulation core cooling system. Although the large number of experiments had been carried out with this reactor, mainly on neutron activation analysis, there is not many data on its thermal-hydraulics processes, whether experimental or theoretical. So a number of experiments were carried out with the measurement of the temperature inside the fuel element, in the reactor core and along the reactor pool. During these experiments the reactor was set in many different power levels. These experiments are part of the CDTN/CNEN research program, and have the main objective of commissioning the TRIGA-IPR-R1 reactor for routine operation at 250 kW. This work presents the experimental and theoretical analyses to determine the temperature distribution in the reactor. A methodology for the calibration and monitoring the reactor thermal power was also developed. This methodology allowed adding others power measuring channels to the reactor by using thermal processes. The fuel thermal conductivity and the heat transfer coefficient from the cladding to the coolant were also experimentally valued. lt was also presented a correlation for the gap conductance between the fuel and the cladding. The experimental results were compared with theoretical calculations and with data obtained from technical literature. A data acquisition and processing system and a software were developed to help the investigation. This system allows on line monitoring and registration of the main reactor operational parameters. The experiments have given better comprehension of the reactor thermal-fluid dynamics and helped to develop numerical

  20. Heterogenous populations of cytotoxic cells in the peritoneal cavity of BALB/c mice immunized with allogeneic EL4 leukemia cells

    International Nuclear Information System (INIS)

    Zighelboim, J.; Bonavida, B.; Fahey, J.L.

    1974-01-01

    Adherent cells, presumably macrophages, obtained from the peritoneal cavity shortly after rejection of the allogeneic leukemia EL4, produced effective cell-mediated cytotoxicity (CMC) in vitro. These cytotoxic cells were sensitive to anti-macrophage serum and resistant to anti-thymocyte serum and 10,000 roentgen irradiation. In contrast, a second population of specifically cytotoxic cells were nonadherent, sensitive to x-rays and anti-thymocyte serum, but not to anti-macrophage serum. The two cell populations had a cooperative cytotoxic effect in vitro against allogeneic tumor cells