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Sample records for 144ce dlya blizhajshej

  1. The 144Ce source for SOX

    Science.gov (United States)

    Durero, M.; Vivier, M.; Agostini, M.; Altenmüller, K.; Appel, S.; Bellini, G.; Benziger, J.; Berton, N.; Bick, D.; Bonfini, G.; Bravo, D.; Caccianiga, B.; Calaprice, F.; Caminata, A.; Cavalcante, P.; Chepurnov, A.; Choi, K.; Cribier, M.; D'Angelo, D.; Davini, S.; Derbin, A.; Di Noto, L.; Drachnev, I.; Etenko, A.; Farinon, S.; Fischer, V.; Fomenko, K.; Franco, D.; Gabriele, F.; Gaffiot, J.; Galbiati, C.; Ghiano, C.; Giammarchi, M.; Goeger-Neff, M.; Goretti, A.; Gromov, M.; Hagner, C.; Houdy, T.; Hungerford, E.; Ianni, Aldo; Ianni, Andrea; Jonqueres, N.; Jedrzejczak, K.; Kaiser, M.; Kobychev, V.; Korablev, D.; Korga, G.; Kornoukhov; Kryn, D.; Lachenmaier, T.; Lasserre, T.; Laubenstein, M.; Lehnert, B.; Link, J.; Litvinovich, E.; Lombardi, F.; Lombardi, P.; Ludhova, L.; Lukyanchenko, G.; Machulin, I.; Manecki, S.; Maneschg, W.; Marcocci, S.; Maricic, J.; Mention, G.; Meroni, E.; Meyer, M.; Miramonti, L.; Misiaszek, M.; Montuschi, M.; Muratova, V.; Musenich, R.; Neumair, B.; Oberauer, L.; Obolensky, M.; Ortica, F.; Pallavicini, M.; Papp, L.; Perasso, L.; Pocar, A.; Ranucci, G.; Razeto, A.; Re, A.; Romani, A.; Roncin, R.; Rossi, N.; Schönert, S.; Scola, L.; Semenov, D.; Simgen, H.; Skorokhvatov, M.; Smirnov, O.; Sotnikov, A.; Sukhotin, S.; Suvorov; Tartaglia, R.; Testera, G.; Thurn, J.; Toropova, M.; Veyssiére, C.; Unzhakov, E.; Vogelaar, R. B.; von Feilitzsch, F.; Wang, H.; Weinz, S.; Winter, J.; Wojcik, M.; Wurm, M.; Yokley, Z.; Zaimidoroga, O.; Zavatarelli, S.; Zuber, K.; Zuzel, G.

    2016-02-01

    The SOX (Short distance neutrino Oscillations with BoreXino) project aims at testing the light sterile neutrino hypothesis. To do so, two artificials sources of antineutrinos and neutrinos respectively will be consecutively deployed at the Laboratori Nazionali del Gran Sasso (LNGS) in close vicinity to Borexino, a large liquid scintillator detector. This document reports on the source production and transportation. The source should exhibit a long lifetime and a high decay energy, a requirement fullfilled by the 144Ce-144Pr pair at secular equilibrium. It will be produced at FSUE “Mayak” PA using spent nuclear fuel. It will then be shielded and packed according to international regulation and shipped to LNGS across Europe. Knowledge of the Cerium antineutrino generator (CeANG) parameters is crucial for SOX as it can strongly impact the experiment sensitivity. Several apparatuses are being used or designed to characterize CeANG activity, radioactive emission and content. An overview of the measurements performed so far is presented here.

  2. Data of evolutionary structure change: 1DLYA-1RTEA [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1DLYA-1RTEA 1DLY 1RTE A A ------------SLFAKLGGREAVEAAVDKFYNKIVADP...TVSTYFSNTDMKVQRSKQFAFLAYALGGASEWKGKDMRTAHKDLVPHLSDVHFQAVARHLSDTLTELGVPPEDITDAMAVVASTRTEVLNMPQQ ...index>0 1RTE A 1RTE

  3. Data of evolutionary structure change: 1DLYA-1RTEB [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1DLYA-1RTEB 1DLY 1RTE A B ------------SLFAKLGGREAVEAAVDKFYNKIVADP...TVSTYFSNTDMKVQRSKQFAFLAYALGGASEWKGKDMRTAHKDLVPHLSDVHFQAVARHLSDTLTELGVPPEDITDAMAVVASTRTEVLNMPQQ ...ndex>0 1RTE B 1RTE

  4. The high precision measurement of the 144Ce activity in the SOX experiment

    Science.gov (United States)

    Di Noto, L.; Agostini, M.; Althenmüller, K.; Appel, S.; Bellini, G.; Benziger, J.; Berton, N.; Bick, D.; Bonfini, G.; Bravo—Berguño, D.; Caccianiga, B.; Calaprice, F.; Caminata, A.; Cavalcante, P.; Cereseto, R.; Chepurnov, A.; Choi, K.; Cribier, M.; DAngelo, D.; Davini, S.; Derbin, A.; Drachnev, I.; Durero, M.; Etenko, A.; Farinon, S.; Fischer, V.; Fomenko, K.; Franco, D.; Gabriele, F.; Gaffiot, J.; Galbiati, C.; Ghiano, C.; Giammarchi, M.; Göeger-Neff, M.; Goretti, A.; Gromov, M.; Hagner, C.; Houdy, Th; Hungerford, E.; Ianni, Aldo; Ianni, Andrea; Jonquères, N.; Jedrzejczak, K.; Kaiser, M.; Kobychev, V.; Korablev, D.; Korga, G.; Kornoukhov, V.; Kryn, D.; Lachenmaier, T.; Lasserre, T.; Laubenstein, M.; Lehnert, T.; Link, J.; Litvinovich, E.; Lombardi, F.; Lombardi, P.; Ludhova, L.; Lukyanchenko, G.; Machulin, I.; Manecki, S.; Maneschg, W.; Marcocci, S.; Maricic, J.; Mention, G.; Meroni, E.; Meyer, M.; Miramonti, L.; Misiaszek, M.; Montuschi, M.; Mosteiro, P.; Muratova, V.; Musenich, R.; Neumair, B.; Oberauer, L.; Obolensky, M.; Ortica, F.; Pallavicini, M.; Papp, L.; Perasso, L.; Pocar, A.; Ranucci, G.; Razeto, A.; Re, A.; Romani, A.; Roncin, R.; Rossi, C.; Rossi, N.; Schönert, S.; Scola, L.; Semenov, D.; Simgen, H.; Skorokhvatov, M.; Smirnov, O.; Sotnikov, A.; Sukhotin, S.; Suvorov, Y.; Tartaglia, R.; Testera, G.; Thurn, J.; Toropova, M.; Veyssière, C.; Vivier, M.; Unzhakov, E.; Vogelaar, R. B.; von Feilitzsch, F.; Wang, H.; Weinz, S.; Winter, J.; Wojcik, M.; Wurm, M.; Yokley, Z.; Zaimidoroga, O.; Zavatarelli, S.; Zuber, K.; Zuzel, G.

    2016-02-01

    In order to perform a resolutive measurement to clarify the neutrino anomalies and to observe possible short distance neutrino oscillations, the SOX (Short distance neutrino Oscillations with BoreXino) experiment is under construction. In the first phase, a 100 kCi 144Ce-144Pr antineutrino source will be placed under the Borexino detector at the Laboratori Nazionali del Gran Sasso (LNGS), in center of Italy, and the rate measurement of the antineutrino events, observed by the very low radioactive background Borexino detector, will be compared with the high precision (< 1%) activity measurement performed by two calorimeters. The source will be embedded in a 19 mm thick tungsten alloy shield and both the calorimeters have been conceived for measuring the thermal heat absorbed by a water flow. In this report the design of the calorimeters will be described in detail and very preliminary results will be also shown.

  5. Data of evolutionary structure change: 1DLWA-1DLYA [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1DLWA-1DLYA 1DLW 1DLY A A SLFEQLGGQAAVQAVTAQFYANIQADATVATFFNGIDMP...EAAVDKFYNKIVADPTVSTYFSNTDMKVQRSKQFAFLAYALGGASEWKGKDMRTAHKDLVPHLSDVHFQAVARHLSDTLTELGVPPEDITDAMAVVASTRTEVLNMPQ...HHGGGHHHH 0 1DLW A 1DLWA HANMG--VSN...Chain> 1DLY A 1DLY

  6. White paper: CeLAND - Investigation of the reactor antineutrino anomaly with an intense 144Ce-144Pr antineutrino source in KamLAND

    CERN Document Server

    Gando, A; Ichimura, K; Ikeda, H; Inoue, K; Kibe, Y; Kishimoto, Y; Koga, M; Minekawa, Y; Mitsui, T; Morikawa, T; Nagai, N; Nakamura, K Nakajima K; Narita, K; Shimizu, I; Shimizu, Y; Shirai, J; Suekane, F; Suzuki, A; Takahashi, H; Takahashi, N; Takemoto, Y; Tamae, K; Watanabe, H; Xu, B D; Yabumoto, H; Yoshida, H; Yoshida, S; Berger, B E; Cribier, M; Decowski, P; Detwiler, J A; Durero, M; Dwyer, D; Efremenko, Y; Enomoto, S; Fischer, V; Fujikawa, B K; Gaffiot, J; Gelis, V M; Karwowski, H J; Kolomensky, Yu G; Kornoukhov, N; Lasserre, T; Learned, J G; Letourneau, A; Lhuillier, D; Maricic, J; Markoff, D M; Matsuno, S; Mention, G; Milincic, R; O'Donnell, T; Saldikov, I S; Scola, L; Tikhomirov, G V; Veyssiere, Ch; Vivier, M

    2013-01-01

    We propose to test for short baseline neutrino oscillations, implied by the recent reevaluation of the reactor antineutrino flux and by anomalous results from the gallium solar neutrino detectors. The test will consist of producing a 75 kCi 144Ce - 144Pr antineutrino source to be deployed in the Kamioka Liquid Scintillator Anti-Neutrino Detector (KamLAND). KamLAND's 13m diameter target volume provides a suitable environment to measure energy and position dependence of the detected neutrino flux. A characteristic oscillation pattern would be visible for a baseline of about 10 m or less, providing a very clean signal of neutrino disappearance into a yet-unknown, "sterile" state. Such a measurement will be free of any reactor-related uncertainties. After 1.5 years of data taking the Reactor Antineutrino Anomaly parameter space will be tested at > 95% C.L.

  7. CeLAND: search for a 4th light neutrino state with a 3 PBq 144Ce-144Pr electron antineutrino generator in KamLAND

    CERN Document Server

    Gando, A; Hayashida, S; Ikeda, H; Inoue, K; Ishidoshiro, K; Ishikawa, H; Koga, M; Matsuda, R; Matsuda, S; Mitsui, T; Motoki, D; Nakamura, K; Oki, Y; Otani, M; Shimizu, I; Shirai, J; Suekane, F; Suzuki, A; Takemoto, Y; Tamae, K; Ueshima, K; Watanabe, H; Xu, B D; Yamada, S; Yamauchi, Y; Yoshida, H; Cribier, M; Durero, M; Fischer, V; Gaffiot, J; Jonqueres, N; Kouchner, A; Lasserre, T; Leterme, D; Letourneau, A; Lhuillier, D; Mention, G; Rampal, G; Scola, L; Veyssiere, Ch; Vivier, M; Yala, P; Berger, B E; Kozlov, A; Banks, T; Dwyer, D; Fujikawa, B K; Han, K; Kolomensky, Yu G; Mei, Y; O'Donnell, T; Decowski, P; Markoff, D M; Yoshida, S; Kornoukhov, V N; Gelis, T V M; Tikhomirov, G V; Learned, J G; Maricic, J; Matsuno, S; Milincic, R; Karwowski, H J; Efremenko, Y; Detwiler, A; Enomoto, S

    2013-01-01

    The reactor neutrino and gallium anomalies can be tested with a 3-4 PBq (75-100 kCi scale) 144Ce-144Pr antineutrino beta-source deployed at the center or next to a large low-background liquid scintillator detector. The antineutrino generator will be produced by the Russian reprocessing plant PA Mayak as early as 2014, transported to Japan, and deployed in the Kamioka Liquid Scintillator Anti-Neutrino Detector (KamLAND) as early as 2015. KamLAND's 13 m diameter target volume provides a suitable environment to measure the energy and position dependence of the detected neutrino flux. A characteristic oscillation pattern would be visible for a baseline of about 10 m or less, providing a very clean signal of neutrino disappearance into a yet-unknown, sterile neutrino state. This will provide a comprehensive test of the electron dissaperance neutrino anomalies and could lead to the discovery of a 4th neutrino state for Delta_m^2 > 0.1 eV^2 and sin^2(2theta) > 0.05.

  8. A Brief Review of Past INL Work Assessing Radionuclide Content in TMI-2 Melted Fuel Debris: The Use of 144Ce as a Surrogate for Pu Accountancy

    Energy Technology Data Exchange (ETDEWEB)

    D. L. Chichester; S. J. Thompson

    2013-09-01

    This report serves as a literature review of prior work performed at Idaho National Laboratory, and its predecessor organizations Idaho National Engineering Laboratory (INEL) and Idaho National Engineering and Environmental Laboratory (INEEL), studying radionuclide partitioning within the melted fuel debris of the reactor of the Three Mile Island 2 (TMI-2) nuclear power plant. The purpose of this review is to document prior published work that provides supporting evidence of the utility of using 144Ce as a surrogate for plutonium within melted fuel debris. When the TMI-2 accident occurred no quantitative nondestructive analysis (NDA) techniques existed that could assay plutonium in the unconventional wastes from the reactor. However, unpublished work performed at INL by D. W. Akers in the late 1980s through the 1990s demonstrated that passive gamma-ray spectrometry of 144Ce could potentially be used to develop a semi-quantitative correlation for estimating plutonium content in these materials. The fate and transport of radioisotopes in fuel from different regions of the core, including uranium, fission products, and actinides, appear to be well characterized based on the maximum temperature reached by fuel in different parts of the core and the melting point, boiling point, and volatility of those radioisotopes. Also, the chemical interactions between fuel, fuel cladding, control elements, and core structural components appears to have played a large role in determining when and how fuel relocation occurred in the core; perhaps the most important of these reaction appears to be related to the formation of mixed-material alloys, eutectics, in the fuel cladding. Because of its high melting point, low volatility, and similar chemical behavior to plutonium, the element cerium appears to have behaved similarly to plutonium during the evolution of the TMI-2 accident. Anecdotal evidence extrapolated from open-source literature strengthens this logical feasibility for

  9. Appendix to Health and Safety Laboratory environmental quarterly, March 1, 1976--June 1, 1976. [Tabulated data on content of lead in surface air and /sup 7/Be, /sup 95/Zr, /sup 137/Cs, /sup 144/Ce, and /sup 90/Sr in surface air, milk, drinking water, and foods sampled in USA

    Energy Technology Data Exchange (ETDEWEB)

    Hardy, E.P. Jr.

    1976-07-01

    Tabulated data are presented on: the monthly deposition of /sup 89/Sr and /sup 90/Sr at some 100 world land sites; the content of lead and /sup 7/Be, /sup 95/Zr, /sup 137/Cs, and /sup 144/Ce in samples of surface air from various world sites; and the content of /sup 90/Sr in samples of milk, drinking water, and animal and human diets collected at various locations throughout the USA. (CH)

  10. Yield-Energy Dependence for 147Nd and 144Ce Under Strong Neutron Field

    Institute of Scientific and Technical Information of China (English)

    QIAN; Jing; LIU; Ting-jin; SUN; Zheng-jun; SHU; Neng-chuan

    2012-01-01

    <正>The data of the fission product yield play an important role in the nuclear science technology and nuclear engineering because they are the key data in the calculation of the decay heat, shield design, nuclear verification, radiochemistry reprocessing and nuclear safety, etc. Especially, it is the essential data in fission power estimation for a fission device. It is well known that there exists a consecutive neutron spectrum with the energy from 1 keV to 15 MeV for a fission-fusion device. So in order to estimate the

  11. Avtomatizirovannyy elektrokhemilyuminestsentnyy metod opredeleniya kortizola v slyune dlya diagnostiki endogennogo giperkortitsizma sredi patsientov s ozhireniem

    Directory of Open Access Journals (Sweden)

    Zhanna Evgenyevna Belaya

    2011-06-01

    Full Text Available Nighttime salivary cortisol (NSC has been suggested to be a useful diagnostic test for Cushings syndrome (CS. However, the reference range and cut-off value are assay-specific and discordant. The goal of this study was to assess the analytical performance of automated elecrochemiluminiscence immunoassay method (ECLIA in CS. Ninety eight healthy volunteers and 123 obese patients including 45 proved to be CS provided salivary samples collected by them at 23:00 using Sallivette. Two hundred and five subjects collected salivary samples for two consecutive days and samples from 197 subjects were frozen to perform Enzyme-linked immunosorbent assay (ELISA. Obese patients underwent the 1-mg overnight dexamethasone suppression test (1-DST. CS was confirmed by the histologic diagnosis after surgical treatment or autopsy. The reference range for healthy volunteer has been set 0,5-9,4 nmol/l. Reproducibility was assessed in all subjects by a day-to-day variability and reflected by an intraclass correlation coefficient of 0,785. The cut-off value of 9,4 nmol/l has been suggested to differentiate CS among obese patients to achieve sensitivity of 84,4% (95%confidence interval 71,2-92,2%; specificity of 92,3% (95%CI 84,2-96,4% and diagnostic odds ratio 65,1 (95% CI 20,4-207,6. Likelihood ratio positive was 11,0 (95% CI 5,0-23,9, with a likelihood ratio negative of 0,17 (95%CI 0,08-0,33. The comparison of the total areas under the ROC-curve for the measurement of NSC once, twice with mean level by ECLIA, the same samples by ELISA and 1-DST have not shown any statistically significant difference among the tests performance. Conclusion: Based on its remarkable reproducibility, easy noninvasive nature, automated assay and at least similar diagnostic performance, NSC measured by ECLIA on Cobas e601 is a preferable first-line screening test for CS.

  12. Aktemra - pervyy i edinstvennyy biologicheskiy preparat, demonstriruyushchiy prevoskhodstvo nad sushchestvuyushchimi standartami terapii revmatoidnogo artrita

    Directory of Open Access Journals (Sweden)

    - -

    2008-01-01

    ostro neobkhodimy novye varianty terapii RA. Uil'yam M. Berns - glava podrazdeleniya Farma kompanii «Rosh»: «Dannye poslednikh issledovaniy yavlyayutsya obnadezhivayushchey novost'yu dlya patsientov, stradayushchikh ot razrushitel'nykh effektov RA. My verim, chto Aktemra - pervyy i edinstvennyy biologicheskiy preparat, demonstriruyushchiy preimushchestvo pered sushchestvuyushchimi standartami lecheniya RA, - oblegchit sostoyanie mnogikh bol'nykh. Krome togo, Aktemra predostavlyaet bol'she shansov dlya dostizheniya ranney i prodolzhitel'noy remissii».

  13. Aktemra - pervyy i edinstvennyy biologicheskiy preparat, demonstriruyushchiy prevoskhodstvo nad sushchestvuyushchimi standartami terapii revmatoidnogo artrita

    Directory of Open Access Journals (Sweden)

    - -

    2008-09-01

    ostro neobkhodimy novye varianty terapii RA. Uil'yam M. Berns - glava podrazdeleniya Farma kompanii «Rosh»: «Dannye poslednikh issledovaniy yavlyayutsya obnadezhivayushchey novost'yu dlya patsientov, stradayushchikh ot razrushitel'nykh effektov RA. My verim, chto Aktemra - pervyy i edinstvennyy biologicheskiy preparat, demonstriruyushchiy preimushchestvo pered sushchestvuyushchimi standartami lecheniya RA, - oblegchit sostoyanie mnogikh bol'nykh. Krome togo, Aktemra predostavlyaet bol'she shansov dlya dostizheniya ranney i prodolzhitel'noy remissii».

  14. Effect of different doses of ionizing radiation on the distribution of /sup 144/cerium in rabbits

    Energy Technology Data Exchange (ETDEWEB)

    Kossakowski, S.; Lojek, W. (Veterinary Research Institute, Pulawy (Poland). Dept. of Radiobiology)

    1984-08-01

    Investigations were carried out in 84 rabbits irradiated with 103 and 206 mC/kg, resp., followed by intravenous contamination with /sup 144/Ce 6 days after irradiation. Radioactivity of muscles and internal organs of the rabbits was determined at different periods. The distribution of /sup 144/Ce in irradiated rabbits was slower and remained on a lower level than in control animals. These changes depended on the radiation doses.

  15. Bibliography of Soviet Laser Developments. Number 70, March - April 1984.

    Science.gov (United States)

    1985-06-12

    Andriyakhin, V.M.; Mayorov, V.S.; Yakunin, V.P. ~ Measuring the spatial distribution of the intensity of industrial C02 laser radiation. FKOMA, no. 2...Storozhev, V.V. (SKBIRE) . Industrial equipment for producing fiber lightguides and fiberoptic communications systems. Pribory i oborudovaniye dlya...8217. Yestyesvennyye i tochnyye nauki, tekhnika) EAAED Electrotehnica, electronica Si automatica. Automatica si electronica series (Bucharest) EEAED Electrotehnica

  16. Alcohol and the clinical picture of gout

    OpenAIRE

    M S Eliseev; Nasonov, E L; V G Barskova; M S Yeliseyev; V A Nasonova; Ye L Nasonov

    2007-01-01

    Tsel' issledovaniya. Izuchenie vliyaniya alkogolya na klinicheskie proyavleniya u bol'nykh podagricheskim artritom. Material i metody. V issledovanie vklyucheny 280 muzhchin, bol'nykh podagroy (kriterii S.L. Wallace). Dlya vyyavleniya skrytoy tyagi k alkogolyu ispol'zovalsya voprosnik CAGE, putem oprosa vyyavlyalos' kolichestvo prinimaemogo alkogolya v nedelyu. U vsekh bol'nykh otsenivali antropometricheskie pokazateli, syvorotochnye urovni pechenochnykh fermentov, bilirubina, kreatinina, moc...

  17. Renormalization of Seasonals in the Additive Seasonal Model: Is it Necessary?

    Science.gov (United States)

    1984-02-01

    but with subsequently placing the c hange over switch ID- PRO of the PI 1-1 instrument in the ś"-൒" positions. Since by pi sc ing the change over...information for self instruction. A schlieren pro -jector installed in the simulator above the work station of the trainee simulates the situation. It...and Fresnukhin, L. N., Mikroprotsessory. Osnovy postroyeniya mikro -computer: ucheb. posobiye dlya VTUZov (Microprocessors. The Base of the Sturucture

  18. ChTO DELAT'', ESLI V PERIOD LEChENIYa INGIBITORAMI FAKTORA NEKROZA OPUKhOLI α VOZNIK PSORIAZ?

    Directory of Open Access Journals (Sweden)

    Yu. V. Muravyev

    2011-01-01

    Full Text Available Ingibitory faktora nekroza opukholi α (FNO α – infliksimab, adalimumab i etanertsept – k aprelyu 2009 g. poluchili bolee 2 mln bol'nykh vo vsem mire. Vse eti preparaty okazalis' odinakovo effektivny (okolo 60% bol'nykh otvetili na lechenie pri revmatoidnom artrite (RA, ankiloziruyushchem spondilite (AS, psoriaze, psoriaticheskom artrite i odobreny dlya lecheniya etikh boleznei [1, 2]. Odnako ikh ispol'zovanie mozhet byt' svyazano s tselym ryadom neblagopriyatnykh reaktsii, odnoi iz kotorykh yavlyaetsya obostrenie ili razvitie novykh sluchaev psoriaza [3].

  19. Monte Carlo simulations in neutrino physics: the example of the SOX experiment

    OpenAIRE

    Caminata, A.; Agostini, M.; Caccianiga, B.; Toropova, M.; Veyssiere, C.; Vivier, M.; Unzhakov, E.; Vogelaar, R. B.; Feilitzsch, F. von; Wang, H.; Weinz, S.; Winter, J.; Wojcik, M.; Calaprice, F.; Wurm, M.

    2016-01-01

    The SOX project aims to test the existence of light sterile neutrinos. A solid signal would mean the discovery of the first particles beyond the Standard Electroweak Model and would have profound implications in our understanding of the Universe and of fundamental particle physics. In case of a negative result, it is able to close a long standing debate about the reality of the neutrino anomalies. The SOX experiment will use a \\mbox{$^{144}$Ce-$^{144}$Pr} antineutrino generator placed at shor...

  20. Appendix to Health and Safety Laboratory environmental quarterly report. [Fallout radionuclides deposited and in surface air at various world sites; /sup 137/Cs and /sup 90/Sr in milk and drinking water in New York City; and stable Pb in surface air

    Energy Technology Data Exchange (ETDEWEB)

    Hardy, E.P. Jr.

    1977-07-01

    Tabulated data are presented on the deposition of fallout /sup 89/Sr and /sup 90/Sr at various world land sites through 1976; the ..gamma.. spectra and content of /sup 7/Be, /sup 95/Zr, /sup 137/Cs, /sup 144/Ce, /sup 90/Sr, /sup 210/Pb, /sup 238/Pu, /sup 239/Pu, and stable Pb in samples of surface air collected during 1966 at various world sites; and the content of fallout /sup 137/Cs and /sup 90/Sr in samples of drinking water and milk collected in New York City through 1976. (CH)

  1. Determination of IRT-2M fuel burnup by gamma spectrometry.

    Science.gov (United States)

    Koleška, Michal; Viererbl, Ladislav; Marek, Milan; Ernest, Jaroslav; Šunka, Michal; Vinš, Miroslav

    2016-01-01

    A spectrometric system was developed for evaluating spent fuel in the LVR-15 research reactor, which employs highly enriched (36%) IRT-2M-type fuel. Such system allows the measurement of detailed fission product profiles. Within these measurements, nuclides such as (137)Cs, (134)Cs, (144)Ce, (106)Ru and (154)Eu may be detected in fuel assemblies with different cooling times varying between 1.67 and 7.53 years. Burnup calculations using the MCNPX Monte Carlo code data showed good agreement with measurements, though some discrepancies were observed in certain regions. These discrepancies are attributed to the evaluation of irradiation history, reactor regulation pattern and buildup schemes.

  2. The search for sterile neutrinos with SOX-Borexino

    Energy Technology Data Exchange (ETDEWEB)

    Altenmüller, K., E-mail: konrad.altenmueller@ph.tum.de; Agostini, M.; Appel, S. [Technische Universität München, Physik-Department and Excellence Cluster Universe (Germany); Bellini, G. [Università degli Studi e INFN, Dipartimento di Fisica (Italy); Benziger, J. [Princeton University, Chemical Engineering Department (United States); Berton, N. [Centre de Saclay, IRFU, Commissariat a l’Energie Atomique et aux Energies Alternatives (France); Bick, D. [Universität Hamburg, Institut für Experimentalphysik (Germany); Bonfini, G. [INFN Laboratori Nazionali del Gran Sasso (Italy); Bravo, D. [Virginia Polytechnic Institute and State University, Physics Department (United States); Caccianiga, B. [Università degli Studi e INFN, Dipartimento di Fisica (Italy); Calaprice, F. [Princeton University, Physics Department (United States); Caminata, A. [Università degli Studi e INFN, Dipartimento di Fisica (Italy); Cavalcante, P. [INFN Laboratori Nazionali del Gran Sasso (Italy); Chepurnov, A. [Moscow State University Skobeltsyn Institute of Nuclear Physics (Russian Federation); Cribier, M. [Centre de Saclay, IRFU, Commissariat a l’Energie Atomique et aux Energies Alternatives (France); D’Angelo, D. [Università degli Studi e INFN, Dipartimento di Fisica (Italy); Davini, S. [Gran Sasso Science Institute (INFN) (Italy); Derbin, A. [St. Petersburg Nuclear Physics Institute (Russian Federation); Noto, L. di [Università degli Studi e INFN, Dipartimento di Fisica (Italy); Drachnev, I. [Gran Sasso Science Institute (INFN) (Italy); and others

    2016-12-15

    The aim of the SOX-Borexino project is to verify or falsify the existence of eV-scale sterile neutrinos. The existence of sterile neutrinos is suspected because of several anomalies, which were observed in previous experiments. A ~3.7 PBq electron antineutrino source made of {sup 144}Ce will be installed below the Borexino detector at LNGS, Italy, to search for short-baseline oscillations of active-to-sterile neutrinos within the detector volume. Source delivery and beginning of data acquisition is planned for end of 2016, preliminary results are expected already in 2017.

  3. Gamma emitting fission products in surface sediments of the Ravenglass estuary

    Energy Technology Data Exchange (ETDEWEB)

    Aston, S.R.; Stanners, D.A. (Lancaster Univ. (UK))

    1982-04-01

    The occurrence of some fission products from the Sellafield (formerly Windscale) nuclear fuel reprocessing facility has been determined for surface sediments from forty locations in the Ravenglass estuary, North-West England. The influence of the silt-sized fraction in the sediments on the geographic distribution of /sup 137/Cs is clearly important, and to a lesser extent also influences the distributions of /sup 106/Ru, /sup 134/Cs + /sup 95/Zr/Nb and /sup 144/Ce. The data are compared with recently published results reported by the Ministry of Agriculture, Fisheries and Food for a monitoring site in this estuary.

  4. Solar neutrino detectors as sterile neutrino hunters

    Science.gov (United States)

    Pallavicini, Marco; Borexino-SOX Collaboration; Agostini, M.; Altenmüller, K.; Appel, S.; Atroshchenko, V.; Bellini, G.; Benziger, J.; Berton, N.; Bick, D.; Bonfini, G.; Bravo, D.; Caccianiga, B.; Calaprice, F.; Caminata, A.; Carlini, M.; Cavalcante, P.; Chepurnov, A.; Choi, K.; Cloué, O.; Cribier, M.; D’Angelo, D.; Davini, S.; Derbin, A.; Di Noto, L.; Drachnev, I.; Durero, M.; Etenko, A.; Farinon, S.; Fischer, V.; Fomenko, K.; Franco, D.; Gabriele, F.; Gaffiot, J.; Galbiati, C.; Gschwender, M.; Ghiano, C.; Giammarchi, M.; Goeger-Neff, M.; Goretti, A.; Gromov, M.; Hagner, C.; Houdy, Th.; Hungerford, E.; Ianni, Aldo; Ianni, Andrea; Jany, A.; Jedrzejczak, K.; Jeschke, D.; Jonquères, N.; Kobychev, V.; Korablev, D.; Korga, G.; Kornoukhov, V.; Kryn, D.; Lachenmaier, T.; Lasserre, T.; Laubenstein, M.; Lehnert, B.; Link, J.; Litvinovich, E.; Lombardi, F.; Lombardi, P.; Ludhova, L.; Lukyanchenko, G.; Machulin, I.; Manecki, S.; Maneschg, W.; Marcocci, S.; Maricic, J.; Mention, G.; Meroni, E.; Meyer, M.; Miramonti, L.; Misiaszek, M.; Montuschi, M.; Mosteiro, P.; Muratova, V.; Musenich, R.; Neumair, B.; Oberauer, L.; Ortica, F.; Papp, L.; Pocar, A.; Ranucci, G.; Razeto, A.; Re, A.; Reinert, Y.; Romani, A.; Roncin, R.; Rossi, N.; Schönert, S.; Scola, L.; Semenov, D.; Skorokhvatov, M.; Smirnov, O.; Sotnikov, A.; Suvorov, Y.; Tartaglia, R.; Testera, G.; Thurn, J.; Toropova, M.; Unzhakov, E.; Veyssière, C.; Vishneva, A.; Vivier, M.; Vogelaar, R. B.; von Feilitzsch, F.; Wang, H.; Weinz, S.; Winter, J.; Wojcik, M.; Wurm, M.; Yokley, Z.; Zaimidoroga, O.; Zavatarelli, S.; Zuber, K.; Zuzel, G.

    2017-09-01

    The large size and the very low radioactive background of solar neutrino detectors such as Borexino at the Gran Sasso Laboratory in Italy offer a unique opportunity to probe the existence of neutrino oscillations into new sterile components by means of carefully designed and well calibrated anti-neutrino and neutrino artificial sources. In this paper we briefly summarise the key elements of the SOX experiment, a program for the search of sterile neutrinos (and other short distance effects) by means of a 144Ce-144Pr anti-neutrino source and, possibly in the medium term future, with a 51Cr neutrino source.

  5. The search for sterile neutrinos with SOX-Borexino

    Science.gov (United States)

    Altenmüller, K.; Agostini, M.; Appel, S.; Bellini, G.; Benziger, J.; Berton, N.; Bick, D.; Bonfini, G.; Bravo, D.; Caccianiga, B.; Calaprice, F.; Caminata, A.; Cavalcante, P.; Chepurnov, A.; Cribier, M.; D'Angelo, D.; Davini, S.; Derbin, A.; di Noto, L.; Drachnev, I.; Durero, M.; Empl, A.; Etenko, A.; Farinon, S.; Fischer, V.; Fomenko, K.; Franco, D.; Gabriele, F.; Gaffiot, J.; Galbiati, C.; Ghiano, C.; Giammarchi, M.; Göger-Neff, M.; Goretti, A.; Gromov, M.; Hagner, C.; Houdy, Th.; Hungerford, E.; Ianni, Aldo; Ianni, Andrea; Jonqures, N.; Kaiser, M.; Kobychev, V.; Korablev, D.; Korga, G.; Kryn, D.; Lachenmaier, T.; Lasserre, T.; Laubenstein, M.; Lehnert, B.; Link, J.; Litvinovich, E.; Lombardi, F.; Lombardi, P.; Ludhova, L.; Lukyanchenko, G.; Machulin, I.; Maneschg, W.; Marcocci, S.; Maricic, J.; Mention, G.; Meroni, E.; Meyer, M.; Miramonti, L.; Misiaszek, M.; Montuschi, M.; Muratova, V.; Musenich, R.; Neumair, B.; Oberauer, L.; Obolensky, M.; Ortica, F.; Pagani, L.; Pallavicini, M.; Papp, L.; Perasso, L.; Pocar, A.; Ranucci, G.; Razeto, A.; Re, A.; Roncin, R.; Romani, A.; Rossi, N.; Schönert, S.; Scola, L.; Semenov, D.; Simgen, H.; Skorokhvatov, M.; Smirnov, O.; Sotnikov, A.; Sukhotin, S.; Suvorov, Y.; Tartaglia, R.; Testera, G.; Toropova, M.; Unzhakov, E.; Veyssière, C.; Vivier, M.; Vogelaar, R. B.; von Feilitzsch, F.; Wang, H.; Winter, J.; Wojcik, M.; Wurm, M.; Yokley, Z.; Zaimidoroga, O.; Zavatarelli, S.; Zuber, K.; Zuzel, G.

    2016-12-01

    The aim of the SOX-Borexino project is to verify or falsify the existence of eV-scale sterile neutrinos. The existence of sterile neutrinos is suspected because of several anomalies, which were observed in previous experiments. A 3.7 PBq electron antineutrino source made of 144Ce will be installed below the Borexino detector at LNGS, Italy, to search for short-baseline oscillations of active-to-sterile neutrinos within the detector volume. Source delivery and beginning of data acquisition is planned for end of 2016, preliminary results are expected already in 2017.

  6. Evaluation of fission product yields from fission spectrum n+239Pu using a meta analysis of benchmark data

    Science.gov (United States)

    Chadwick, Mark B.

    2009-10-01

    Los Alamos conducted a dual fission-chamber experiment in the 1970s in the Bigten critical assembly to determine fission product data in a fast (fission neutron spectrum) environment, and this defined the Laboratory's fission basis today. We describe how the data from this experiment are consistent with other benchmark fission product yield measurements for 95,97Zr, 140Ba, 143,144Ce, 137Cs from the NIST-led ILRR fission chamber experiments, and from Maeck's mass-spectrometry data. We perform a new evaluation of the fission product yields that is planned for ENDF/B-VII.1. Because the measurement database for some of the FPs is small—especially for 147Nd and 99Mo—we use a meta-analysis that incorporates insights from other accurately-measured benchmark FP data. The %-relative changes compared to ENDF/B-VI are small for some FPs (less than 1% for 95Zr, 140Ba, 144Ce), but are larger for 99Mo (3%) and 147Nd (5%). We suggest an incident neutron energy dependence to the 147Nd fission product yield that accounts for observed differences in the FPY at a few-hundred keV average energy in fast reactors versus measurements made at higher average energies.

  7. Development of analytical methods and survey of radioactive contamination of foodstuffs

    Energy Technology Data Exchange (ETDEWEB)

    Lee, W. N.; Lee, C. W.; Choi, G. S.; Chung, G. H.; Kang, M. J.; Kim, H. R.; Park, D. W.; Choi, C. S.; Kwak, J. H.; Kwak, S. Y.

    2008-11-15

    After the Chernobyl nuclear accident in 1986, a survey of the radioactive contamination for foodstuffs have been investigated by many countries such as EU, Japan, USA. Concerns about the radioactive contamination of foodstuffs are increased because of the recently special situation (Nuclear test of North Korea). Recently, CODEX added and departmentalised new monitoring radionuclides including alpha and beta radionuclides. The purpose and scope of this study is 1) the development of analysis method for gamma emitting radionuclides({sup 60}Co, {sup 103}Ru, {sup 106}Ru, {sup 144}Ce, {sup 192}Ir) and tritium radionuclides added at new CODEX version. 2) survey and analysis of radioactive contamination for foodstuffs collected from the open markets (the imported and domestic products including North Korea products). Based on deeply examination of the various international standard procedures, the new method for analyzing gamma emitting radionuclides({sup 60}Co, {sup 103}Ru, {sup 106}Ru, {sup 144}Ce, {sup 192}Ir) was developed and applied to radioactive analysis of the foodstuffs. 200 foodstuffs were analyzed(150 imported foodstuffs including 11 samples of North Korea product and 50 domestic foodstuffs). The 137Cs radionuclide among the regulation radionuclides({sup 137}Cs, {sup 134}Cs, {sup 131}I) of the Korea food code and the added radionuclides({sup 60}Co, {sup 103}Ru, {sup 106}Ru, {sup 144}Ce, {sup 192}Ir) at new CODEX version is only detected in the imported foodstuffs but its level is far below the maximum permitted level. This study also developed analytical methods for additional radionuclides(3H) of CODEX. In the normal case, it will be enough only to survey the radioactive contamination for foodstuffs using the regulation radionuclides ({sup 137}Cs, {sup 134}Cs, {sup 131}I) of the Korea food code without the analysis of the added radionuclides at new CODEX version. However, when the radioactivity more than the regulation level is measured, the added

  8. Lifetime tumor risk coefficients for beagle dogs that inhaled cerium-144 chloride

    Energy Technology Data Exchange (ETDEWEB)

    Boecker, B.B.; Hahn, F.F.; Griffith, W.C. [and others

    1995-12-01

    Reported here is one of the life-span radionuclide toxicology studies being conducted at ITRI in Beagle dogs. These studies are examining the life-span health risks of inhaled {Beta}-, {gamma}- and {alpha}-emitting radionuclides to expand available knowledge on these risks especially for the many cases for which human data are not available. The outcomes of these studies are providing important information on dosimetry and dose-response relationships for these inhaled radionuclides and the relative importance of a broad range of dose- and effect-modifying factors. A number of these studies are currently coming to completion. Much of the ITRI effort is being directed to final reviews of the dosimetric, clinical, and pathologic results and writing summary manuscripts. Radiation doses and effects in tissues adjacent to bone, specifically those of epithelial or marrow origin, should be considered when determining risks from internally deposited, bone-seeking radionuclides such as {sup 144}Ce.

  9. Improved estimate of the cross section for inverse beta decay

    CERN Document Server

    Ankowski, Artur M

    2016-01-01

    The hypothesis of the conserved vector current, relating the vector weak and isovector electromagnetic currents, plays a fundamental role in quantitative description of neutrino interactions. Despite being experimentally confirmed with great precision, it is not fully implemented in existing calculations of the cross section for inverse beta decay, the dominant mechanism of antineutrino scattering at energies below a few tens of MeV. In this article, I estimate the corresponding cross section and its uncertainty, ensuring conservation of the vector current. While converging to previous calculations at energies of several MeV, the obtained result is appreciably lower and predicts more directional positron production near the reaction threshold. These findings suggest that in the current estimate of the flux of geologically produced antineutrinos the 232Th and 238U components may be underestimated by 6.1 and 3.7%, respectively. The proposed search for light sterile neutrinos using a 144Ce--144Pr source is predi...

  10. Source self-attenuation in ionization chamber measurements of (57)Co solutions.

    Science.gov (United States)

    Cessna, Jeffrey T; Golas, Daniel B; Bergeron, Denis E

    2016-03-01

    Source self-attenuation for solutions of (57)Co of varying density and carrier concentration was measured in nine re-entrant ionization chambers maintained at NIST. The magnitude of the attenuation must be investigated to determine whether a correction is necessary in the determination of the activity of a source that differs in composition from the source used to calibrate the ionization chamber. At our institute, corrections are currently made in the measurement of (144)Ce, (109)Cd, (67)Ga, (195)Au, (166)Ho, (177)Lu, and (153)Sm. This work presents the methods used as recently applied to (57)Co. A range of corrections up to 1% were calculated for dilute to concentrated HCl at routinely used carrier concentrations.

  11. Study of systematics for the SOX experiment

    Energy Technology Data Exchange (ETDEWEB)

    Neumair, Birgit [Technische Univ. Muenchen, Garching bei Muenchen (Germany); Collaboration: BOREXINO-Collaboration

    2016-07-01

    In the last years, several neutrino oscillation experiments reported results not compatible within the 3-neutrino model, which hint at the existence of light sterile neutrinos. To test this hypothesis, the SOX (Short distance neutrino Oscillations in BoreXino) experiment will search for oscillations from active to sterile neutrinos by placing radioactive electron (anti-)neutrino sources underneath the Borexino detector. Oscillations will be observed via a reduction of the detected interaction rate of the electron(anti-)neutrinos and an oscillatory pattern as a function of the neutrino energy and travelled distance. The talk gives an overview of the experiment with the focus on the systematics and their impact on the sensitivity for a 100kCi {sup 144}Ce source.

  12. SOX sensitivity study

    Energy Technology Data Exchange (ETDEWEB)

    Martyn, Johann [Johannes Gutenberg-Universitaet, Mainz (Germany); Collaboration: BOREXINO-Collaboration

    2016-07-01

    To this day most experimental results on neutrino oscillations can be explained in the standard three neutrino model. There are however a few experiments that show anomalous behaviour at a very short baselines. These anomalies can hypothetically be explained with the existence of one or additional more light neutrino states that do not take part in weak interactions and are thus called sterile. Although the anomalies only give a hint that such sterile neutrinos could exist the prospect for physics beyond the standard model is a major motivation to investigate the neutrino oscillations in new very short baseline experiments. The SOX (Short distance Oscillations in BoreXino) experiment will use the Borexino detector and a {sup 144}Ce source to search for sterile neutrinos via the occurance of an oscillation pattern at a baseline of several meters. This talk examines the impact of the Borexino detector systematics on the experimental sensitivity of SOX.

  13. Performance of a high-precision calorimeter for the measurement of the antineutrino-source strength in the SOX experiment

    Energy Technology Data Exchange (ETDEWEB)

    Altenmueller, Konrad [Technische Universitaet Muenchen (Germany); Collaboration: BOREXINO-Collaboration

    2016-07-01

    A calorimeter was developed to measure the thermal power and thus the antineutrino-generation rate of a {sup 144}Ce - {sup 144}Pr antineutrino-source with < 1% overall accuracy for the SOX experiment. SOX is searching for neutrino oscillations at short baselines with the Borexino detector to investigate the existence of eV-scale sterile neutrinos. The calorimeter design is based on a copper heat exchanger with integrated water lines for the heat extraction, mounted around the source. A high precision measurement is possible thanks to an elaborate thermal insulation. In this talk, the design of the calorimeter is reviewed and results of calibration measurements are presented. The thermal insulation of the system was examined and heat losses were quantified. The methods to reconstruct the source power and the decay rate from measurements are described.

  14. EML Surface Air Sampling Program, 1990--1993 data

    Energy Technology Data Exchange (ETDEWEB)

    Larsen, R.J.; Sanderson, C.G.; Kada, J.

    1995-11-01

    Measurements of the concentrations of specific atmospheric radionuclides in air filter samples collected for the Environmental Measurements Laboratory`s Surface Air Sampling Program (SASP) during 1990--1993, with the exception of April 1993, indicate that anthropogenic radionuclides, in both hemispheres, were at or below the lower limits of detection for the sampling and analytical techniques that were used to collect and measure them. The occasional detection of {sup 137}Cs in some air filter samples may have resulted from resuspension of previously deposited debris. Following the April 6, 1993 accident and release of radionuclides into the atmosphere at a reprocessing plant in the Tomsk-7 military nuclear complex located 16 km north of the Siberian city of Tomsk, Russia, weekly air filter samples from Barrow, Alaska; Thule, Greenland and Moosonee, Canada were selected for special analyses. The naturally occurring radioisotopes that the authors measure, {sup 7}Be and {sup 210}Pb, continue to be detected in most air filter samples. Variations in the annual mean concentrations of {sup 7}Be at many of the sites appear to result primarily from changes in the atmospheric production rate of this cosmogenic radionuclide. Short-term variations in the concentrations of {sup 7}Be and {sup 210}Pb continued to be observed at many sites at which weekly air filter samples were analyzed. The monthly gross gamma-ray activity and the monthly mean surface air concentrations of {sup 7}Be, {sup 95}Zr, {sup 137}Cs, {sup 144}Ce, and {sup 210}Pb measured at sampling sites in SASP during 1990--1993 are presented. The weekly mean surface air concentrations of {sup 7}Be, {sup 95}Zr, {sup 137}Cs, {sup 144}Ce, and {sup 210}Pb for samples collected during 1990--1993 are given for 17 sites.

  15. Concentration and depuration of some radionuclides present in a chronically exposed population of mussels (Mytilus edulis)

    Energy Technology Data Exchange (ETDEWEB)

    Clifton, R.J.; Stevens, H.E.; Hamilton, E.I.

    1983-03-01

    Factors are described which affect the concentration (p Ci g/sup -1/ dry wt) and loss of /sup 241/ Am, /sup 239 +240/Pu, /sup 238/Pu, /sup 144/Ce, /sup 137/Cs, /sup 134/Cs, /sup 106/Ru, /sup 95/Zr and /sup 95/Nb in an exposed population of mussels Mytilus edulis L. from Ravenglass on the Esk estuary, Cumbria, UK which receives radioeffluents from the British Nuclear Fuels Ltd. (BNFL) plant at Sellafield, some 10 km to the north. Tidal position and mussel body size have a negligible influence on the concentration of /sup 241/Am, /sup 137/Cs and /sup 106/Ru in the total soft tissue, but variation in soft tissue weight throughout the year has a considerable influence on the apparent concentration and depuration times of these radionuclides. Apart from the clearance (tsub(1/2) biol, 1 to 3 h) of sediment-associated activity from the digestive tract, the depuration rate profiles follow a single component clearance curve with a biological half-life in excess of 200 d for /sup 241/ Am, /sup 239 +240/Pu, /sup 238/Pu and /sup 144/Ce, and of 40 d for /sup 137/Cs. The clearance of /sup 106/Ru is more complex and consists of a 3 component depuration profile with biological half-lives of 6 h, 12 d and 260 d. The depuration profiles presented in this work are for chronically ingested isotopes under natural conditions; acute exposure will most likely result in different profiles, especially those derived from laboratory spiking experiments. Isotope ratio data support the hypothesis that the main route of entry into the mussel for the majority of the radionuclides studied is from the water.

  16. Il personaggio scontornato in Škola dlja Durakov. Dal romanzo di Saša Sokolov agli adattamenti teatrali

    Directory of Open Access Journals (Sweden)

    Irina Marchesini

    2012-12-01

    Full Text Available Sokolov’s Shkola dlya Durakov (A School for Fools, 1976 is an extremely complex novel, which “depicts [the] world”, as D. Barton Johnson (1986:640[1] poignantly observes, “through the eyes, and pure, if eccentric, language, of a schizophrenic youth”. How is it possible to translate such linguistic features and the effects they create into another medium? This question lies at the core of my proposal, which aims to approach the problem of intermedial translation from prose to theatre through the presentation of an individual case-study. In fact, A School for Fools has been staged by the director Andrey Moguchy (Formalny Theatre, Saint Petersburg, Russia. With the intention of reproducing Sokolov’s aesthetic construction of illusion, Moguchy introduces a new genre in the theatrical context, the so-called “vizualnaya associaciya” (“visual association”. As the director explained in a recent interview, this original genre recalls the Impressionists’ position in observing and representing nature, in order to obtain the same effect generated by the reading of the novel. To comprehend this process better, special attention is devoted to the construction of unusual, hybrid characters, highlighting their constitutive features both in the novel and in the theatrical adaptation. Moreover, this research seeks to enrich discussion of the work of Sokolov and Moguchy. [1] Johnson, D. Barton (1986 “Sasha Sokolov's Twilight Cosmos: Themes and Motifs”, in: Slavic Review, 45, 4 (Winter 1986, pp. 639-649.

  17. Classification of hot particles from the Chernobyl accident and nuclear weapons detonations by non-destructive methods.

    Science.gov (United States)

    Zheltonozhsky, V; Mück, K; Bondarkov, M

    2001-01-01

    Both after the Chernobyl accident and nuclear weapon detonations, agglomerates of radioactive material, so-called hot particles, were released or formed which show a behaviour in the environment quite different from the activity released in gaseous or aerosol form. The differences in their characteristic properties, in the radionuclide composition and the uranium and actinide contents are described in detail for these particles. While nuclear bomb hot particles (both from fission and fusion bombs) incorporate well detectable trace amounts of 60Co and 152Eu, these radionuclides are absent in Chernobyl hot particles. In contrast, Chernobyl hot particles contain 125Sb and 144Ce which are absent in atomic bomb HPs. Obvious differences are also observable between fusion and fission bombs' hot particles (significant differences in 152Eu/l55Eu, 154Eu/155Eu and 238Pu/239Pu ratios) which facilitate the identification of HPs of unknown provensence. The ratio of 239Pu/240Pu in Chernobyl hot particles could be determined by a non-destructive method at 1:1.5. A non-destructive method to determine the content of non-radioactive elements by Kalpha-emission measurements was developed by which inactive Zr, Nb, Fe and Ni could be verified in the particles.

  18. TMI-2 Reactor Building source term measurements: surfaces and basement water and sediment

    Energy Technology Data Exchange (ETDEWEB)

    McIsaac, C V; Keefer, D G

    1984-10-01

    Presented in this report are the results of radiochemical and elemental analyses performed on samples collected from the Three Mile Island Unit 2 Reactor Building from August 1979 to December 1983. The quantities of fission products and core materials that were measured on the external surfaces in the Reactor Building or in the water and sediment in its basement are summarized. Recent analysis results for access panels removed from the air cooling assembly and for liquid and particulate samples collected from the Reactor Building sump and reactor coolant drain tank are included in the report. Measurements show that 59% of the /sup 3/H, 2.7% of the /sup 90/Sr, 15% of the /sup 129/I, 20% of the /sup 131/I, and 42% of the /sup 137/Cs originally in the core at the time of the accident could be accounted for outside the core in the Reactor Building. With the exceptions of /sup 90/Sr and /sup 144/Ce, the vast majority of each radionuclide released was found dispersed in the water and sediment in the basement.

  19. Chemical and physical considerations of the use of nuclear fuel spikants for deterrence

    Energy Technology Data Exchange (ETDEWEB)

    Selle, J. E.

    1978-10-01

    One proposed method of inhibiting the diversion of nuclear fuel for clandestine purposes is to add to the fuel a highly gamma-active material of such intensity that remote handling equipment is necessary in all stages of handling and reprocessing. This is called spiking for deterrence. The present work sought to identify candidate spikants and identify potential materials problems that might occur as the result of incorporation of these spikants with the fuel. Potential spikants were identified and thermodynamic analysis was performed to determine their chemical and physical states. Phase relationships between spikants (and their decay products) and the fuel constituents were surveyed. According to criteria defined in this report, /sup 60/Co, /sup 106/Ru, and /sup 144/Ce appear to have the greatest potential as spikants. Cerium should be present as the oxide, soluble in the fuel, while cobalt and ruthenium should be present in the metallic state with very low solubility in the fuel. Experimental work on the distribution of fission products and their interactions with cladding was also surveyed to provide information on the distribution of spikants in the fuel and describe the probable effects of spikants on the fuel. Cobalt, ruthenium, and cerium should not present any problems due to reaction with stainless steel cladding.

  20. Standard test method for gamma energy emission from fission products in uranium hexafluoride and uranyl nitrate solution

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2005-01-01

    1.1 This test method covers the measurement of gamma energy emitted from fission products in uranium hexafluoride (UF6) and uranyl nitrate solution. It is intended to provide a method for demonstrating compliance with UF6 specifications C 787 and C 996 and uranyl nitrate specification C 788. 1.2 The lower limit of detection is 5000 MeV Bq/kg (MeV/kg per second) of uranium and is the square root of the sum of the squares of the individual reporting limits of the nuclides to be measured. The limit of detection was determined on a pure, aged natural uranium (ANU) solution. The value is dependent upon detector efficiency and background. 1.3 The nuclides to be measured are106Ru/ 106Rh, 103Ru,137Cs, 144Ce, 144Pr, 141Ce, 95Zr, 95Nb, and 125Sb. Other gamma energy-emitting fission nuclides present in the spectrum at detectable levels should be identified and quantified as required by the data quality objectives. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its us...

  1. Determination of gamma-emitting radionuclides in the inter-tidal sediments off Balochistan (Pakistan) Coast, Arabian Sea.

    Science.gov (United States)

    Akram, M; Qureshi, Riffat M; Ahmad, Nasir; Solaija, Tariq Jamal

    2007-01-01

    Natural radionuclide contents of 226Ra, 228Ra and (40)K were studied for inter-tidal sediments collected from selected locations off the745 km long Balochistan Coast using HPGe detector based gamma-spectrometry system. The sampling zone extends from the beaches of Sonmiani (near Karachi metropolis) through Jiwani (close to the border of Iran). The natural radioactivity levels detected in various sediment samples range from 14.4 +/- 2.5 to 36.6 +/- 3.8 Bq kg(-1) for 226Ra, 9.8 +/- 1.2 to 35.2 +/- 2.0 Bq kg(-1) for (228)Ra and 144.6 +/- 9.4 to 610.5 +/- 23.9 Bq kg(-1) for (40)K. No artificial radionuclide was detected in any of the marine coastal sediment samples. 137Cs, (60)Co, 106Ru and 144Ce contents in sediment samples were below the limit of detection. The measured radioactivity levels are compared with those reported in the literature for coastal sediments in other parts of the world. The information presented in this paper will serve as the first ever local radioactivity database for the Balochistan/Makran Coastal belt of Pakistan. The presented data will also contribute to the IAEA's, Asia-Pacific Marine Radioactivity Database (ASPAMARD) and the Global Marine Radioactivity Database (GLOMARD).

  2. Monte Carlo modeling of beta-radiometer device used to measure milk contaminated as a result of the Chernobyl accident

    Energy Technology Data Exchange (ETDEWEB)

    Khrutchinsky, A.; Kutsen, S. [Research Institute for Nuclear Problems, 11 Bobruiskaya Street, Minsk 220050 (Belarus); Minenko, V. [Belarusian Medical Academy of Post-Graduate Education, 3 Brovki Street, Minsk 220714 (Belarus); Zhukova, O. [Center of Radiation Control and Environment Monitoring, 110A Nezalezhnosti Avenue, Minsk 220023 (Belarus); Luckyanov, N.; Bouville, A. [DHHS, NIH, National Cancer Institute, Division of Cancer Epidemiology and Genetics, 6120 Executive Blvd, EPS 7100, Bethesda, MD 20892 (United States); Drozdovitch, V. [DHHS, NIH, National Cancer Institute, Division of Cancer Epidemiology and Genetics, 6120 Executive Blvd, EPS 7100, Bethesda, MD 20892 (United States)], E-mail: drozdovv@mail.nih.gov

    2009-06-15

    This paper presents results of Monte Carlo modeling of the beta-radiometer device with Geiger-Mueller detector used in Belarus and Russia to measure the radioactive contamination of milk after the Chernobyl accident. This type of detector, which is not energy selective, measured the total beta-activity of the radionuclide mix. A mathematical model of the beta-radiometer device, namely DP-100, was developed, and the calibration factors for the different radionuclides that might contribute to the milk contamination were calculated. The estimated calibration factors for {sup 131}I, {sup 137}Cs, {sup 134}Cs, {sup 90}Sr, {sup 144}Ce, and {sup 106}Ru reasonably agree with calibration factors determined experimentally. The calculated calibration factors for {sup 132}Te, {sup 132}I, {sup 133}I, {sup 136}Cs, {sup 89}Sr, {sup 103}Ru, {sup 140}Ba, {sup 140}La, and {sup 141}Ce had not been previously determined experimentally. The obtained results allow to derive the activity of specific radionuclides, in particular {sup 131}I, from the results of the total beta-activity measurements in milk. Results of this study are important for the purposes of retrospective dosimetry that uses measurements of radioactivity in environmental samples performed with beta-radiometer devices.

  3. Amchitka Radiobiological Program. Final report, July 1970-December 1979

    Energy Technology Data Exchange (ETDEWEB)

    Sibley, T.H.; Tornberg, L.D.

    1982-11-01

    The Amchitka Radiobiological Program, to collect biological and environmental samples for radiological analyses, began in 1970 and continued through 1979. The principal objective was to determine the extent of radionuclide contamination from worldwide atmospheric fallout and from the detonation of three underground nuclear tests on Amchitka. Leakage of radionuclides from the underground test sites would be suspected if the amount of contamination was significantly greater than could be attributed to worldwide fallout or if an unexpected assemblage of radionuclides was detected. No radionuclides from the underground sites were detected, except for tritium from the Long Shot test (1965) which produced increased tritium concentrations in surface water and freshwater plants near the test site. This final report compiles all previous data into one report and considers the temporal trends in these data. Two naturally occurring radionuclides, /sup 40/K and /sup 7/Be, were the most abundantly occurring radionuclides in most samples; in lichen samples either /sup 137/Cs or /sup 144/Ce had the highest activity. All samples were below applicable Radiation Protection Guides and by 1979 most samples were near or below the statistical detection limits. Increased concentrations of short-lived fallout radionuclides following the Chinese atmospheric tests were found in freshwater and seawater samples and in most indicator organisms.

  4. Transfer of radionuclides to man from greylag geese Anser anser and wigeon Anas penelope grazing the saltmarshes at Ravenglass

    Energy Technology Data Exchange (ETDEWEB)

    Lowe, V.P.W.; Horrill, A.D.

    1986-01-01

    The greylag goose and wigeon are both traditional quarry of wildfowlers. Populations of these birds in the Ravenglass estuary feed and roost on saltmarshes containing radioactivity originating from the Sellafield reprocessing plant. There is therefore, via the meat, a potential pathway for the transfer of radionuclides to man. The birds' intake of gamma-emitting fission and activation products, including /sup 60/Co, /sup 95/Nb, /sup 95/Zr, /sup 106/Ru, /sup 144/Ce, /sup 134/Cs, /sup 137/Cs, /sup 154/Eu, /sup 155/Eu and /sup 241/Am, was investigated by examining their concentrations in vegetation from the feeding areas and in their faeces. Muscle and liver tissues were also analysed. Only /sup 134/Cs and /sup 137/Cs were detected and quantified in breast muscle. Estimated transfer coefficients for /sup 137/Cs were very similar for both species. A single person would have had to consume in excess of the total number of wigeon shot or the total population of geese to obtain even 1% of his or her Annual Limit on Intake.

  5. Development of a CMPO based extraction process for partitioning of minor actinides and demonstration with genuine fast reactor fuel solution (155 GWd/Te)

    Energy Technology Data Exchange (ETDEWEB)

    Antony, M.P.; Kumaresan, R.; Suneesh, A.S. [Indira Gandhi Centre for Atomic Research, Kalpakkam (IN). Fuel Chemistry Div.] (and others)

    2011-07-01

    A method has been developed for partitioning of minor actinides from fast reactor (FR) fuel solution by a TRUEX solvent composed of 0.2 M n-octyl(phenyl)-N,N-diisobutylcarbamoyl-methylphosphine oxide (CMPO)-1.2 M tri-n-butylphosphate (TBP) in n-dodecane (n-DD), and subsequently demonstrated with genuine fast reactor dissolver solution (155 GWd/Te) using a novel 16-stage ejector mixer settler in hot cells. Cesium, plutonium and uranium present in the dissolver solution were removed, prior to minor actinide partitioning, by using ammonium molybdophosphate impregnated XAD-7 (AMP-XAD), methylated poly(4-vinylpyridine) (PVP-Me), and macroporous bifunctional phosphinic acid (MPBPA) resins respectively. Extraction of europium(III) and cerium(III) from simulated and real dissolver solution, and their stripping behavior from loaded organic phase was studied in batch method using various citric acid-nitric acid formulations. Based on these results, partitioning of minor actinides from fast reactor dissolver solution was demonstrated in hot cells. The extraction and stripping profiles of {sup 154}Eu, {sup 144}Ce, {sup 106}Ru and {sup 137}Cs, and mass balance of {sup 241}Am(III) achieved in the demonstration run have been reported in this paper. (orig.)

  6. Experimental model of osteosarcomas in rats

    Energy Technology Data Exchange (ETDEWEB)

    Jasmin, C.; Allouche, M.; Jude, J.G.; Klein, B. (Institut de Cancerologie et d' Immunogenetique, Villejuif (France)); Thiery, J.P.; Perdereau, B.; Gongora, R.; Gongora, G.; Mazabraud, A. (Institut Curie, Paris (France))

    1982-07-08

    Satisfactory experimental models for preclinical prediction in cancerology must answer the following criteria: reproducibility of the method used for inducing tumors; clinical, pathological and kinetic similarity with the corresponding human tumors. We have developed a model of osteosarcoma locally induced by insoluble radioactive cerium chloride (/sup 144/Ce Cl/sub 3/) in Sprague Dawley rats. This method yields over 80% of bone tumors at the injection site, of which approximately half are histologically similar to human tumors. These tumors double their volume fairly slowly (in approximately 20 days); lung metastases occur both early and frequently (80% of animals). A transplantable tumor was developed from an induced osteosarcoma and adapted to the Curie strain. Transplantation in the bone, next to the bone, or under the skin is followed by widespread metastatic dissemination. The kinetics and histological features of the primary tumor are maintained. Tumor /sup 85/strontium uptake is similar to that seen in human osteosarcomas. These new models of osteosarcomas are being used for evaluating new cancer chemotherapeutic agents and interferon, etc.

  7. Dynamic model for radionuclide uptake in lichen

    Energy Technology Data Exchange (ETDEWEB)

    Ellis, K.M.; Smith, J.N.

    1987-01-01

    Samples of atmospheric particulate material and terrestrial plants, including lichens, were collected in New Brunswick, Canada between 1980 and 1983 and analyzed for a wide range of artificial and naturally-occurring radionuclides, including fission products (/sup 141/Ce, /sup 144/Ce, /sup 103/Ru, /sup 106/Ru, /sup 95/Zr and /sup 137/Cs) derived from the 16 October 1980 Chinese nuclear test. Activity ratios of some of the short-lived fission products in air particulates and lichens are in reasonable agreement with those predicted from fission product yields for nuclear weapons tests, indicating that only minor fractionation occurred for these radionuclides during their transport through air particulate and lichen environmental phases. The /sup 7/Be inventories measured in a suite of lichen (Cladonia rangiferina) samples were used to calibrate each lichen plant for its collection efficiency for atmospheric particulates and fallout radioactivity. A lichen model has been developed to predict lichen inventories of radioactivity for different lichen growth functions and bio-elimination rates. Assuming that lichen growth results in a linear increase in surface area with time, the experimental results yield biological residence times of 1-2 years for /sup 210/Pb and Pu and 5-8 years for /sup 137/Cs.

  8. Fission-Product Development Laboratory cell-decommissioning project plan

    Energy Technology Data Exchange (ETDEWEB)

    Myrick, T.E.; Schaich, R.W.; Williams, F.V.

    1983-08-01

    The Fission Product Development Laboratory (FPDL) at Oak Ridge National Laboratory (ORNL) was a full-scale processing facility for separating megacurie quantities of /sup 90/Sr, /sup 137/Cs, and /sup 144/Ce for a variety of source applications, operating at full capacity from 1958 to 1975. Since facility shutdown, the inactive portions of the FPDL have been maintained in a protective storage mode as part of the ORNL Surplus Facilities Management Program (SFMP). Due to the significant radio-nuclide inventory remaining in the facility, the high surveillance and maintenance costs necessary to assure radionuclide containment, and the potential for reuse of the facility by other programs, the decommissioning of the inactive portions of the FPDL has been given a high priority by the SFMP. In response to this program direction, plans are being made for initiation of these activities in late FY 1983. This project plan has been prepared to satisfy the program documentation requirements for SFMP project planning. The plan outlines the scope of the proposed effort, describes the proposed methods of project accomplishment, and provides estimates of the project resource needs and schedule.

  9. Linear free energy correlations for fission product release from the Fukushima-Daiichi nuclear accident.

    Science.gov (United States)

    Abrecht, David G; Schwantes, Jon M

    2015-03-03

    This paper extends the preliminary linear free energy correlations for radionuclide release performed by Schwantes et al., following the Fukushima-Daiichi Nuclear Power Plant accident. Through evaluations of the molar fractionations of radionuclides deposited in the soil relative to modeled radionuclide inventories, we confirm the initial source of the radionuclides to the environment to be from active reactors rather than the spent fuel pool. Linear correlations of the form In χ = −α ((ΔGrxn°(TC))/(RTC)) + β were obtained between the deposited concentrations, and the reduction potentials of the fission product oxide species using multiple reduction schemes to calculate ΔG°rxn (TC). These models allowed an estimate of the upper bound for the reactor temperatures of TC between 2015 and 2060 K, providing insight into the limiting factors to vaporization and release of fission products during the reactor accident. Estimates of the release of medium-lived fission products 90Sr, 121mSn, 147Pm, 144Ce, 152Eu, 154Eu, 155Eu, and 151Sm through atmospheric venting during the first month following the accident were obtained, indicating that large quantities of 90Sr and radioactive lanthanides were likely to remain in the damaged reactor cores.

  10. Study of various decontamination processes for evaporation concentrates; Etude de differents traitements de decontamination sur des concentrats d'evaporation

    Energy Technology Data Exchange (ETDEWEB)

    Lefillatre, G.; Cudel, Y.; Rodi, L. [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1968-07-01

    Generally speaking, the evaporation concentrates are in the form of acid solutions of high salt content, about 400 g/l. The specific activity is very variable: from 0.5 mCi/l to many hundreds of Ci/l. Because of the high solubility of these salts, an attempt has been made to render the radio-elements insoluble in the concentrates before their possible coating with bitumen. With this in view, the possibility of fixing them on inorganic products, of precipitating them in the form of insoluble salts, or of adsorbing them on co-precipitates has been considered. In the case of a fixation of radio-elements by natural or synthetic inorganic products with a high absorptive capacity such as clays, diatomaceous earths, synthetic silicates and alumina, 48 products have been tried. Their selective efficiency with respect to {sup 137}Cs, {sup 90}Sr, {sup 106}Ru-Rh, {sup 144}Ce-Pr, {sup 95}Zr-Nb has been determined both with acid concentrates and with neutralized concentrates (precipitation of hydroxides). In the case of the fixation of radio-elements as insoluble salts or their adsorption on co-precipitates, the choice of treatments involved the two most dangerous radio-elements: {sup 137}Cs and {sup 90}Sr. The conventional processing methods were tried. For {sup 90}Sr. calcium carbonate, calcium oxalate, calcium phosphate, strontium phosphate, manganese oxides, barium sulfate. For {sup 137}Cs: the ferrocyanides of nickel, copper, zinc, cobalt and manganese. The technique consists in carrying out the precipitations (hydroxides, specific processes for {sup 90}Sr and {sup 137}Cs) one after the other without separating the precipitates. (authors) [French] D'une facon generale, les concentrats d'evaporation se presentent sous forme de solutions acides de mineralisation elevee, de l'ordre de 400 g/l. Leur activite specifique est tres variable: de 0.5 mCi/l a plusieurs centaines de Ci/l. En raison de la tres grande solubilite de ces sels, il a paru interessant de

  11. Irradiated-Microsphere Gamma Analyzer (IMGA): an integrated system for HTGR coated particle fuel performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Kania, M.J.; Valentine, K.H.

    1980-02-01

    The Irradiated-Microsphere Gamma Analyzer (IMGA) System, designed and built at ORNL, provides the capability of making statistically accurate failure fraction measurements on irradiated HTGR coated particle fuel. The IMGA records the gamma-ray energy spectra from fuel particles and performs quantitative analyses on these spectra; then, using chemical and physical properties of the gamma emitters it makes a failed-nonfailed decision concerning the ability of the coatings to retain fission products. Actual retention characteristics for the coatings are determined by measuring activity ratios for certain gamma emitters such as /sup 137/Cs//sup 95/Zr and /sup 144/Ce//sup 95/Zr for metallic fission product retention and /sup 134/Cs//sup 137/Cs for an indirect measure of gaseous fission product retention. Data from IMGA (which can be put in the form of n failures observed in N examinations) can be accurately described by the binomial probability distribution model. Using this model, a mathematical relationship between IMGA data (n,N), failure fraction, and confidence level was developed. To determine failure fractions of less than or equal to 1% at confidence levels near 95%, this model dictates that from several hundred to several thousand particles must be examined. The automated particle handler of the IMGA system provides this capability. As a demonstration of failure fraction determination, fuel rod C-3-1 from the OF-2 irradiation capsule was analyzed and failure fraction statistics were applied. Results showed that at the 1% failure fraction level, with a 95% confidence level, the fissile particle batch could not meet requirements; however, the fertile particle exceeded these requirements for the given irradiation temperature and burnup.

  12. Passive gamma analysis of the boiling-water-reactor assemblies

    Science.gov (United States)

    Vo, D.; Favalli, A.; Grogan, B.; Jansson, P.; Liljenfeldt, H.; Mozin, V.; Schwalbach, P.; Sjöland, A.; Tobin, S.; Trellue, H.; Vaccaro, S.

    2016-09-01

    This research focused on the analysis of a set of stationary passive gamma measurements taken on the spent nuclear fuel assemblies from a boiling water reactor (BWR) using pulse height analysis data acquisition. The measurements were performed on 25 different BWR assemblies in 2014 at Sweden's Central Interim Storage Facility for Spent Nuclear Fuel (Clab). This study was performed as part of the Next Generation of Safeguards Initiative-Spent Fuel project to research the application of nondestructive assay (NDA) to spent fuel assemblies. The NGSI-SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay (NDA) measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins, (3) estimate the plutonium mass, (4) estimate the decay heat, and (5) determine the reactivity of spent fuel assemblies. The final objective of this project is to quantify the capability of several integrated NDA instruments to meet the aforementioned goals using the combined signatures of neutrons, gamma rays, and heat. This report presents a selection of the measured data and summarizes an analysis of the results. Specifically, trends in the count rates measured for spectral lines from the following isotopes were analyzed as a function of the declared burnup and cooling time: 137Cs, 154Eu, 134Cs, and to a lesser extent, 106Ru and 144Ce. From these measured count rates, predictive algorithms were developed to enable the estimation of the burnup and cooling time. Furthermore, these algorithms were benchmarked on a set of assemblies not included in the standard assemblies set used by this research team.

  13. Determining initial enrichment, burnup, and cooling time of pressurized-water-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Favalli, A., E-mail: afavalli@lanl.gov [Los Alamos National Laboratory, Los Alamos, NM (United States); Vo, D. [Los Alamos National Laboratory, Los Alamos, NM (United States); Grogan, B. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Jansson, P. [Uppsala University, Uppsala (Sweden); Liljenfeldt, H. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Mozin, V. [Lawrence Livermore National Laboratory, Livermore, CA (United States); Schwalbach, P. [European Commission, DG Energy, Euratom Safeguards Luxemburg, Luxemburg (Luxembourg); Sjöland, A. [Swedish Nuclear Fuel and Waste Management Company, Stockholm (Sweden); Tobin, S.J.; Trellue, H. [Los Alamos National Laboratory, Los Alamos, NM (United States); Vaccaro, S. [European Commission, DG Energy, Euratom Safeguards Luxemburg, Luxemburg (Luxembourg)

    2016-06-01

    The purpose of the Next Generation Safeguards Initiative (NGSI)–Spent Fuel (SF) project is to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. The NGSI–SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)]; (4) estimate the decay heat; and (5) determine the reactivity of spent fuel assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). One purpose of the measurement campaigns was to acquire passive gamma spectra with high-purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute {sup 137}Cs count rate and the {sup 154}Eu/{sup 137}Cs, {sup 134}Cs/{sup 137}Cs, {sup 106}Ru/{sup 137}Cs, and {sup 144}Ce/{sup 137}Cs isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity’s behavior over various combinations of burnup, cooling time, and initial enrichment) and then were used to determine those same quantities in each measured spent fuel assembly. The results obtained in comparison with the operator declared values, as well as the methodology developed, are discussed in detail in the paper.

  14. Passive gamma analysis of the boiling-water-reactor assemblies

    Energy Technology Data Exchange (ETDEWEB)

    Vo, D., E-mail: ducvo@lanl.gov [Los Alamos National Laboratory, Los Alamos, NM (United States); Favalli, A. [Los Alamos National Laboratory, Los Alamos, NM (United States); Grogan, B. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Jansson, P. [Uppsala University, Uppsala (Sweden); Liljenfeldt, H. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Mozin, V. [Lawrence Livermore National Laboratory, Livermore, CA (United States); Schwalbach, P. [European Atomic Energy Community (EURATOM), Luxemburg (Luxembourg); Sjöland, A. [Swedish Nuclear Fuel and Waste Management Company, Stockholm (Sweden); Tobin, S.; Trellue, H. [Los Alamos National Laboratory, Los Alamos, NM (United States); Vaccaro, S. [European Atomic Energy Community (EURATOM), Luxemburg (Luxembourg)

    2016-09-11

    This research focused on the analysis of a set of stationary passive gamma measurements taken on the spent nuclear fuel assemblies from a boiling water reactor (BWR) using pulse height analysis data acquisition. The measurements were performed on 25 different BWR assemblies in 2014 at Sweden's Central Interim Storage Facility for Spent Nuclear Fuel (Clab). This study was performed as part of the Next Generation of Safeguards Initiative–Spent Fuel project to research the application of nondestructive assay (NDA) to spent fuel assemblies. The NGSI–SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay (NDA) measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins, (3) estimate the plutonium mass, (4) estimate the decay heat, and (5) determine the reactivity of spent fuel assemblies. The final objective of this project is to quantify the capability of several integrated NDA instruments to meet the aforementioned goals using the combined signatures of neutrons, gamma rays, and heat. This report presents a selection of the measured data and summarizes an analysis of the results. Specifically, trends in the count rates measured for spectral lines from the following isotopes were analyzed as a function of the declared burnup and cooling time: {sup 137}Cs, {sup 154}Eu, {sup 134}Cs, and to a lesser extent, {sup 106}Ru and {sup 144}Ce. From these measured count rates, predictive algorithms were developed to enable the estimation of the burnup and cooling time. Furthermore, these algorithms were benchmarked on a set of assemblies not included in the standard assemblies set used by this research team.

  15. Determining initial enrichment, burnup, and cooling time of pressurized-water-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

    Science.gov (United States)

    Favalli, A.; Vo, D.; Grogan, B.; Jansson, P.; Liljenfeldt, H.; Mozin, V.; Schwalbach, P.; Sjöland, A.; Tobin, S. J.; Trellue, H.; Vaccaro, S.

    2016-06-01

    The purpose of the Next Generation Safeguards Initiative (NGSI)-Spent Fuel (SF) project is to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. The NGSI-SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)]; (4) estimate the decay heat; and (5) determine the reactivity of spent fuel assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). One purpose of the measurement campaigns was to acquire passive gamma spectra with high-purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute 137Cs count rate and the 154Eu/137Cs, 134Cs/137Cs, 106Ru/137Cs, and 144Ce/137Cs isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity's behavior over various combinations of burnup, cooling time, and initial enrichment) and then were used to determine those same quantities in each measured spent fuel assembly. The results obtained in comparison with the operator declared values, as well as the methodology developed, are discussed in detail in the paper.

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

    Science.gov (United States)

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

    2016-11-01

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

  17. Accumulation of transuranic elements in the aquatic biota of the Belarusian sector of contaminated area near the Chernobyl nuclear power plant - Accumulation of transuranic elements in aquatic biota of Belarusian sector of contaminated area of Chernobyl nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Golubev, Alexander; Mironov, Vladislav [International Sakharov Environmental University. Box 220070, 23 Dolgobrodskaya Street, Minsk, 220070 (Belarus)

    2014-07-01

    The evolution of nuclear contamination of Belarus territory after Chernobyl accident includes the four stages: 1. Iodine-neptunium stage, caused mainly by short-lived radionuclides {sup 131}I, {sup 239}Np and others with a half-life period of several weeks; II. Intermediate stage, caused by radionuclides with a half-life period of a year ({sup 144}Ce, {sup 106}Ru, {sup 134}Cs, etc.); III. Strontium-cesium stage, caused by {sup 90}Sr and {sup 137}Cs with a half-life period of about 30 years; IV. Plutonium-americium, caused by long-lived α-emitting radionuclides {sup 241}Am (period of half-life of 432 years) and {sup 239+240}Pu, having high radio and chemo-toxicity. According to forecasts, activity of {sup 241}Am to 2050 year will increase by 2.5 times and it will be the most important dose-related factor for the aquatic biota within the Chernobyl accident zone. In 2002 - 2008 years we have studied the accumulation of trans-uranic elements (TUE, {sup 241}Am, {sup 239+240}Pu) in basic components of water body ecosystems within the Chernobyl zone - non-flowing Perstok Lake, weak-flowing Borschevka flooding and small Braginka River. Among investigated components are water, bottom sediments, submerged macrophytes (Ceratophyllum submersum, Hydrocharis morsus-ranae, Lemna minor, Nuphar lutea, Stratiotes aloides), emergent macrophytes (Typha spp.), shellfish and fish. In the soil cover in the vicinity of the Perstok Lake activity of {sup 241}Am at present is equivalent to 300 - 600 Bq.kg{sup -1}, that is the basic source of its income to the lake. Radionuclides mobility in the water environment is higher than in the soil, that facilitates the rapid incorporation of {sup 241}Am to the trophic nets of water bodies and its removal by near-water animals in the terrestrial biotopes, including outside Chernobyl zone. Thus, the activity of {sup 241}Am in bottom sediments in the Perstok Lake and Borschevka flooding in 2008 year reach respectively 324 and 131 Bq.kg{sup -1}, and the

  18. Impact of {sup 134}Cs and {sup 137}Cs from the Chernobyl reactor accident on the Spanish Mediterranean marine environment

    Energy Technology Data Exchange (ETDEWEB)

    Molero, J.; Sanchez-Cabeza, J.A.; Merino, J. [Grup de Fisica de les Radiacions, Departament de Fisica, Facultat de Ciencies, Universitat Autonoma de Barcelona, 08193 Bellaterra (Spain); Mitchell, P.I. [Laboratory of Radiation Physics, University College, Dublin (Ireland); Vidal-Quadras, A. [Grup de Fisica de les Radiacions, Departament de Fisica, Facultat de Ciencies, Universitat Autonoma de Barcelona, 08193 Bellaterra (Spain)

    1999-05-01

    As part of a study aiming to establish the distribution and bioavailability of man-made radionuclides in the marine environment, radiocaesium levels were determined in large volume sea water samples and in the sea-grass Posidonia oceanica collected along the Spanish Mediterranean coast. Results obtained from 1987 to 1991 showed the enhancement of radiocaesium levels in the Spanish Mediterranean marine environment after the Chernobyl accident. The well-known {sup 134}Cs/{sup 137}Cs isotopic ratio in Chernobyl fresh deposition was used to identify the weapon tests fall-out and Chernobyl deposition components. {sup 137}Cs and {sup 134}Cs mean concentrations in surface waters from the Spanish Mediterranean shoreline were 4.8{+-}0.2 and 0.27{+-}0.01 Bq m{sup -3}, respectively. {sup 137}Cs concentration incorporated into Mediterranean waters as a consequence of the post-Chernobyl deposition was estimated to be 1.16{+-}0.04 Bq m{sup -3}, which is a 33{+-}2% increase over the previous levels. {sup 137}Cs estimated inventory in the surface water layer (0-50 m) of the Catalan-Balearic basin was 17.4{+-}0.5 TBq for {sup 137}Cs, of which 4.3{+-}0.2 TBq must be attributed to post-Chernobyl deposition, and 1.00{+-}0.04 TBq for {sup 134}Cs. Activation and fission products such as {sup 106}Ru, {sup 110m}Ag, {sup 134}Cs, {sup 137}Cs and {sup 144}Ce, were detected in all samples of Posidonia oceanica. Mean radiocaesium levels in the bioindicator were 1.02{+-}0.25 and 0.20{+-}0.03 Bq kg{sup -1} for {sup 137}Cs and {sup 134}Cs, respectively, corresponding to a mean isotopic ratio {sup 134}Cs/{sup 137}Cs equal to 0.20{+-}0.04 (1987). {sup 137}Cs activity incorporated by Posidonia oceanica after the Chernobyl deposition over the Mediterranean Sea was estimated as 0.51{+-}0.08 Bq kg{sup -1}. Therefore, {sup 137}Cs specific activity had increased 100{+-}40% one year after the accident. Low level radioactive liquid effluents from the nuclear power plants located on the southern Catalan

  19. Fission Product Yields from Fission Spectrum n+ 239Pu for ENDF/B-VII.1

    Science.gov (United States)

    Chadwick, M. B.; Kawano, T.; Barr, D. W.; Mac Innes, M. R.; Kahler, A. C.; Graves, T.; Selby, H.; Burns, C. J.; Inkret, W. C.; Keksis, A. L.; Lestone, J. P.; Sierk, A. J.; Talou, P.

    2010-12-01

    We describe a new cumulated fission product yield (FPY) evaluation for fission spectrum neutrons on plutonium that updates the ENDF/B-VI evaluation by England and Rider, for the forthcoming ENDF/B-VII.1 database release. We focus on FPs that are needed for high accuracy burnup assessments; that is, for inferring the number of fissions in a neutron environment. Los Alamos conducted an experiment in the 1970s in the Bigten fast critical assembly to determine fission product yields as part of the Interlaboratory Reaction Rate (ILRR) collaboration, and this has defined the Laboratory's fission standard to this day. Our evaluation includes use of the LANL-ILRR measurements (not previously available to evaluators) as well as other Laboratory FPY measurements published in the literature, especially the high-accuracy mass spectrometry data from Maeck and others. Because the measurement database for some of the FPs is small — especially for 99Mo — we use a meta-analysis that incorporates insights from other accurately-measured benchmark FP data, using R-value ratio measurements. The meta-analysis supports the FP measurements from the LANL-ILRR experiment. Differences between our new evaluations and ENDF/B-VI are small for some FPs (less than 1-2%-relative for 95Zr, 140Ba, 144Ce), but are larger for 99Mo (4%-relative) and 147Nd (5%-relative, at 1.5 MeV) respectively. We present evidence for an incident neutron energy dependence to the 147Nd fission product yield that accounts for observed differences in the FPY at a few-hundred keV average energy in fast reactors versus measurements made at higher average neutron energies in Los Alamos' fast critical assemblies. Accounting for such FPY neutron energy dependencies is important if one wants to reach a goal of determining the number of fissions to accuracies of 1-2%. An evaluation of the energy-dependence of fission product yields is given for all A values based on systematical trends in the measured data, with a focus on

  20. Patterns of Cs-137 and Sr-90 distribution in conjugated landscape systems

    Science.gov (United States)

    Korobova, E.

    2012-04-01

    The main goal of the study was to reveal spatial patterns of 137Cs and 90Sr distribution in soils and plants of conjugated landscapes and to use 137Cs as a tracer for natural migration and accumulation processes in the environment. The studies were based on presumptions that: 1) the environment consisted of interrelated bio- and geochemical fields of hierarchical structure depending on the level and age of factors responsible for spatial distribution of chemical elements; 2)distribution of technogenic radionuclides in natural landscapes depended upon the location and type of the initial source and radionuclide involvement in natural pathways controlled by the state and mobility of the typomorphic elements and water migration. Case studies were undertaken in areas subjected to contamination after the Chernobyl accident and in the estuary zones of the Yenisey and Pechora rivers. First observations in the Chernobyl remote zone in 1987-1989 demonstrated relation between the dose rate, 137Cs, 134Cs, 144Ce, 106Ru, 125Sb in soil cover and the location of the measured plot in landscape toposequence. Later study of 137Cs and 90Sr concentration and speciation confirmed different patterns of their distribution dependent upon the radioisotope, soil features and vegetation cover corresponding to the local landscape and landuse structure. Certain patterns in distribution and migration of 137Cs and 90Sr in soils and local food chain were followed in private farms situated in different landscape position [1]. Detailed study of 137Cs activity in forested site with a pronounced relief 20 and 25 years after the Chernobyl accident showed its stable polycentric structure in soils, mosses and litter which was sensitive to meso- and micro-relief features [2]. Radionuclide contamination of the lower Yenisey and Pechora studied along meridian landscape transects proved both areas be subjected to global 137Cs pollution while the Yenisey floodplain received additional regional contamination

  1. A study on the Methodology for Integrated Safety Assessment for Accidental Analysis on LILW managed in Temporary Storage Facility (TSF) at NPP

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Min Ho; Lee, Kun Jai [Korea Advanced Institute of Science and Technology, 335 Gwahak-ro, yuseong-gu, Daejeon 305-701 (Korea, Republic of); Choi, Kyung Woo [Korea Institute of Nuclear Safety, 34 Gwahak-ro, yuseong-gu, Daejeon 305-338 (Korea, Republic of)

    2010-07-01

    dose assessment were considered: {sup 3}H, {sup 14}C, {sup 55}Fe, {sup 58}Co, {sup 60}Co, {sup 59}Ni, {sup 63}Ni, {sup 90}Sr, {sup 94}Nb, {sup 99}Tc, {sup 129}I, {sup 137}Cs, and {sup 144}Ce. According to the U.S. NRC Regulatory Guide 1.145, the atmospheric dispersion factors (?/Q) for workers and public were derived by meteorological data measured in Kori NPP: wind speed, wind direction, and atmospheric stability. For the evaluation of internal exposure, the breathing rate (m{sup 3}/sec) described in U.S. NRC Regulatory Guide 1.8 was considered. In conclusion: Based on the MLD method, the dropping of drums and fire were used to evaluate the exposure dose by arbitrary accidents originating in the TSF for LILW management. For the exposure dose assessment, a variety of parameters were considered: the amount of radionuclides released (Bq), the atmospheric dispersion factor for workers and public (sec/m{sup 3}), the breathing rate for internal exposure (m{sup 3}/sec), and the dose conversion factor for internal and external exposure (mSv/Bq, mSv/hr per Bq/m{sup 3}). Furthermore, an exposure dose assessment was conducted in terms of the effective dose and the thyroid equivalent dose for workers and public, considering the release rates of the radionuclides stemming from the dropping of drums and fire. The number of damaged drums was taken as 2 for the dropping of drums and 40 for fire relative to each waste stream. Seven waste streams were considered: the general DAW (200 L), the shielded DAW (200 L), the concentrated waste solidified by cement (200 L), the concentrated waste stabilized by paraffin (200 L), the general spent resin (200 L), the spent resin solidified by cement (200 L), and the general spent filter (200 L). The effective doses resulted from the dropping of drums were in the range of 4.95 E-15 to 2.19 E- 7 mSv for workers and 9.21 E-17 to 1.34 E-9 mSv for public. Also the thyroid equivalent doses originating from the dropping of drums were in the range of 3