Evaluation of systems interactions in nuclear power plants: Technical findings related to Unresolved Safety Issue A-17

International Nuclear Information System (INIS)

Thatcher, D.

1989-05-01

This report presents a summary of the activities related to Unresolved Safety Issue (USI)A-17, ''Systems Interactions in Nuclear Power Plants,'' and also includes the NRC staff's conclusions based on those activities. The staff's technical findings provide the framework for the final resolution of this unresolved safety issue. The final resolution will be published later as NUREG-1229. 52 refs., 4 tabs

Interleukin (IL)-17A and IL-17F and asthma in Saudi Arabia: mRNA ...

African Journals Online (AJOL)

Win-07

IL17A and IL17F were significantly higher in asthma patients compared to controls [IL17A: 1.112 (2.088) vs 0.938 ... Asthma is a frequently encountered chronic airway in- ... transcription was performed, in 20 μl reaction volume using the.

Investigation of {sup 17}F+p elastic scattering at near-barrier energies

Energy Technology Data Exchange (ETDEWEB)

El-Azab Farid, M. [Assiut University, Physics Department, Assiut (Egypt); Ibraheem, Awad A. [Al-Azhar University, Physics Department, Assiut (Egypt); King Khalid University, Physics Department, Abha (Saudi Arabia); Al-Hajjaji, Arwa S. [Taiz University, Physics Department, Taiz (Yemen)

2015-10-15

The {sup 17}F +p elastic scattering at two near-barrier energies of 3.5 and 4.3 MeV/nucleon, have been analyzed in the framework of the single folding approach. The folded potentials are constructed by folding the density-dependent (DDM3Y) effective nucleon-nucleon interaction over the nuclear density of the one-proton halo nucleus {sup 17}F. Two versions of the density are considered. In addition, two versions of the one-nucleon knock-on exchange potentials are introduced to construct the real microscopic potentials. The derived potentials supplemented by phenomenological Woods-Saxon imaginary and spin-orbit potentials produced excellent description of the differential elastic scattering cross sections at the higher energy without need to introduce any renormalization. At the lower energy, however, in order to successfully reproduce the data, it is necessary to reduce the strength of the constructed real DDM3Y potential by about 25% of its original value. Furthermore, good agreement with data is obtained using the extracted microscopic DDM3Y potentials for both real and imaginary parts. Moreover, the interesting notch test is applied to investigate the sensitivity of the elastic scattering cross section to the radial distribution of the constructed microscopic potentials. The extracted reaction (absorption) cross sections are, also, investigated. (orig.)

Thermonuclear reaction rate of 17O(p,γ)18F

International Nuclear Information System (INIS)

Fox, C.; Iliadis, C.; Champagne, A.E.; Fitzgerald, R.P.; Longland, R.; Newton, J.; Pollanen, J.; Runkle, R.

2005-01-01

The 17 O(p,γ) 18 F and 17 O(p,α) 14 N reactions have a profound influence on hydrogen-burning nucleosynthesis in a number of stellar sites, including red giants, asymptotic giant branch (AGB) stars, massive stars, and classical novae. Previously evaluated thermonuclear rates for both reactions carry large uncertainties. We investigated the proton-capture reaction on 17 O in the bombarding energy range of E p lab = 180-540 keV. We observed a previously undiscovered resonance at E R lab = 193.2 ± 0.9 keV. The resonance strength amounts to (ωγ) pγ (1.2±0.2)x10 -6 eV. With this value, the uncertainties of the 17 O(p,γ) 18 F reaction rates are reduced by orders of magnitude in the peak temperature range of classical novae (T=0.1-0.4 GK). We also report on a reevaluation of the 17 O(p,γ) 18 F reaction rates at lower temperatures that are pertinent to red giants, AGB stars, or massive stars. The present work establishes the 17 O(p,γ) 18 F reaction rates over a temperature range of T= 0.01-1.5 GK with statistical uncertainties of 10-50%. The new recommended reaction rates deviate from the previously accepted values by an order of magnitude around T≅0.2 GK and by factors of 2-3 at T < 0.1 GK

14N-trinucleon cluster states in 17F and 17O

International Nuclear Information System (INIS)

Merchant, A.C.

1984-01-01

A cluster model is used to calculate the energies of those states in 17 F and 17 O which have a 14 N-trinucleon cluster-core structure. The non-central terms in the cluster-core potential are deduced phenomenologically and also calculated microscopically. They are found to be intimately related to equivalent terms in the potentials for similar cluster-core decompositions of neighbouring nuclei. The results are compared with the spectrum of states excited in a recent experimental study of three-particle transfer onto 14 N. (Author) [pt

Automatic synthesis of 16α-[18F]fluoro-17β-estradiol using a cassette-type [18F]fluorodeoxyglucose synthesizer

International Nuclear Information System (INIS)

Mori, Tetsuya; Kasamatsu, Shingo; Mosdzianowski, Christoph; Welch, Michael J.; Yonekura, Yoshiharu; Fujibayashi, Yasuhisa

2006-01-01

16α-[ 18 F]fluoro-17β-estradiol ([ 18 F]FES) is a radiotracer for imaging estrogen receptors by positron emission tomography. We developed a clinically applicable automatic preparation system for [ 18 F]FES by modifying a cassette-type [ 18 F]fluorodeoxyglucose synthesizer. Two milligrams of 3-O-methoxymethyl-16,17-O-sulfuryl-16-epiestriol in acetonitrile was heated at 105 o C for 10 min with dried [ 18 F]fluoride. The resultant solution was evaporated and hydrolyzed with 0.2 N HCl in 90% acetonitrile/water at 95 o C for 10 min under pressurized condition. The neutralization was carried out with 2.8% NaHCO 3 , and then the high-performance liquid chromatography (HPLC) purification was performed. The desired radioactive fraction was collected and the solvent was replaced by 10 ml of saline, and then passed through a 0.22-μm filter into a pyrogen-free vial as the final product. The HPLC purification data demonstrated that [ 18 F]FES was synthesized with a yield of 76.4±1.9% (n=5). The yield as the final product for clinical use was 42.4±3.2% (n=5, decay corrected). The total preparation time was 88.2±6.4 min, including the HPLC purification and the solvent replacement process. The radiochemical purity of the final product was >99%, and the specific activity was more than 111 GBq/μmol. The final product was stable for more than 6 h in saline containing sodium ascorbate. This new preparation system enables us to produce [ 18 F]FES safe for clinical use with high and reproducible yield

Design of a partial inter-tube lancing system actuated by hydraulic power for type F model steam generator in nuclear power plant

International Nuclear Information System (INIS)

Kim, S. T.; Jeong, W. T.

2008-01-01

The sludge grown up in steam generators of nuclear power plants shortens the life-cycle of steam generators and reduces the output of power plants. So KHNP(Korea Hydro and Nuclear Power), the only nuclear power utility in Korea, removes it periodically using a steam generator lancing system during the outage of plants for an overhaul. KEPRI(Korea Electric Power Research Institute) has developed lancing systems with high pressured water nozzle for steam generators of nuclear power plants since 2001. In this paper, the design of a partial inter-tube lancing system for model F type steam generators will be described. The system is actuated without a DC motor inner steam generators because the motors in a steam generator make a trouble from high intensity of radioactivity as a break down

Preparation of 16α[18F] fluoro-17β-fluoroestradiol on domestic synthesis module

International Nuclear Information System (INIS)

Sun Chuanjin; Zhu Hong; Fang Keyuan

2012-01-01

To investigate the synthesis method of 16α-[ 18 F] fluoro-17β-fluoroestradiol on domestic synthesizing module, the automated synthesis was carried out through the reaction of 3-O-(methoxymethyl) -16,17-O-sulfuryl-16-epiestriol (MMSE, 1 mg) as precursor with 18 F- at 105 ℃ for 15 min in sealed system on domestic synthesizer, then 0.8 mL 1 mol/L HC1 dissolved in 7.2 mL acetonetrile was added in three parts to the reaction vessel for hydrolysis and hydrolysis reaction was performed at 105 ℃ for 6 min. The final reaction solution was purified by HPLC to give 18 F-FES. Preparation of 18 F-FES on domestic synthesis module was in the uncorrected synthesis yield of 8.2% (corrected synthesis yield 12.8%). Total synthesis time was about 70 min and radiochemical purity was higher than 98%. The product had good stability at room temperature. 18 F-FES injection can be prepared on domes- tic synthesis module and the quality can meet the requirements of radiopharmaceuticals for clinical use, (authors)

Nuclear astrophysics data at ORNL

International Nuclear Information System (INIS)

Smith, M.S.; Blackmon, J.C.

1998-01-01

There is a new program of evaluation and dissemination of nuclear data of critical importance for nuclear astrophysics within the Physics Division of Oak Ridge National Laboratory. Recent activities include determining the rates of the important 14 O(α,p) 17 F and 17 F(p,γ) 18 Ne reactions, disseminating the Caughlan and Fowler reaction rate compilation on the World Wide Web, and evaluating the 17 O(p,α) 14 N reaction rate. These projects, which are closely coupled to current ORNL nuclear astrophysics research, are briefly discussed along with future plans

Quadrupole moment and a proton halo structure in 17F (Iπ = 5/2+)

International Nuclear Information System (INIS)

Zhou Dongmei; Zheng Yongnan; Yuan Daqing; Xizhen, Zhang; Zuo Yi; Minamisono, T; Matsuta, M; Fukuda, M; Mihara, M; Zhang Chunlei; Zhiqiang, Wang; Du Enpeng; Luo Hailong; Xu Guoji; Zhu Shengyun

2007-01-01

The quadrupole moment of light nuclei 17 F in the ground state (I π = 5/2 + ) is measured by the β-NMR method. The effective charge of the last proton in a d 5/2 orbit for 17 F is extracted from the measured quadrupole moment Q( 17 F) divided by the quadrupole moment Q sp calculated with a single particle model. A proton effective charge of e eff p = 1.12 ± 0.07e is obtained, which is in agreement with that given by a particle-vibration coupling model calculation within the experimental error. The present value of the proton effective charge is strong evidence for the existence of a proton skin in 17 F (I π = 5/2 + )

Nuclear Data Newsletter. No. 17

International Nuclear Information System (INIS)

1992-09-01

This issue of the Nuclear Data Newsletter dated September 1992, gives information on the following topics: Data indexes and bibliographies, IAEA Nuclear Data Information System-on-line access, nuclear data processing computer codes, new data libraries, multigroup nuclear data, selected new publication on nuclear data, the network of nuclear data service centers which are all related to the activity of the Nuclear Data Section (NDS) of the IAEA

IAEA: 17 countries are candidates for nuclear energy

International Nuclear Information System (INIS)

Anon.

2011-01-01

In january 2011 IAEA announced that 17 countries had officially expressed their willingness to home nuclear power plants, they have filed applications for the construction of nuclear power plants. Among the countries concerned we find: Poland, Kuwait, Jordan, Morocco, Tunisia, Nigeria, Bangladesh, Thailand, Vietnam, Chile and Uruguay

Polymorphisms in interleukins 17A and 17F genes and periodontitis: results from a meta-analysis.

Science.gov (United States)

da Silva, Felipe Rodolfo Pereira; Pessoa, Larissa Dos Santos; Vasconcelos, Any Carolina Cardoso Guimarães; de Aquino Lima, Weberson; Alves, Even Herlany Pereira; Vasconcelos, Daniel Fernando Pereira

2017-12-01

Polymorphisms in inflammatory genes such as interleukins 17A and 17F are associated with the risk of development of periodontitis, although the results remain contradictory. Hence, the aim of this study was perform a meta-analysis focusing on two polymorphisms (rs2275913 and rs763780) in interleukins 17A and 17F genes, respectively, in both chronic (CP) and aggressive periodontitis (AgP). A review in literature was performed in several databases for studies published before 25, September 2016. The meta-analysis was obtained through the review manager statistical software (version 5.2) with odds ratio (OR) calculation and funnel plot (P < 0.05) for heterogeneity, as well as the comprehensive meta-analysis software (version 3.3.070) for the assessment of publication bias. Seven articles with 1540 participants composed the results in which the mutant allele in the rs2275913 polymorphism did not present significant association with the risk of CP or AgP (OR 1.56, 95% CI 0.77, 3.15, P = 0.21; OR 1.12, 95% CI 0.05, 23.44, P = 0.94, respectively) nor was the mutant allele in rs763780 associated with the risk of CP (OR 1.19, 95% CI 0.80, 1.76, P = 0.39) or AgP (OR 1.07, 95% CI 0.63, 1.84, P = 0.79). No bias of publication was observed by Egger's and Begg's tests in any allelic evaluation. This meta-analysis showed a non-significant association between the polymorphisms rs2275913 and rs763780 in interleukins 17A and 17F genes and chronic and aggressive periodontitis in the allelic evaluation.

Inelastic Branch of the Stellar Reaction $^{14}$O$(\\alpha,p)^{17}$F

CERN Multimedia

Hass, M; Van duppen, P L E

2002-01-01

We propose to use the upgraded REX-ISOLDE beam energy to study the astrophysically important $^{14}$O($\\alpha$, p)$^{17}$F reaction in time reverse kinematics. In particular, we will use the highly efficient miniball + CD detection system to measure the previously undetermined inelastic proton branch of the 1$^-$ state at 6.15 MeV in $^{18}$Ne. This state dominates the reaction rate under X-ray burster conditions.

High-precision half-life measurements of the T =1 /2 mirror β decays 17F and 33Cl

Science.gov (United States)

Grinyer, J.; Grinyer, G. F.; Babo, M.; Bouzomita, H.; Chauveau, P.; Delahaye, P.; Dubois, M.; Frigot, R.; Jardin, P.; Leboucher, C.; Maunoury, L.; Seiffert, C.; Thomas, J. C.; Traykov, E.

2015-10-01

Background: Measurements of the f t values for T =1 /2 mirror β+ decays offer a method to test the conserved vector current hypothesis and to determine Vud, the up-down matrix element of the Cabibbo-Kobayashi-Maskawa matrix. In most mirror decays used for these tests, uncertainties in the f t values are dominated by the uncertainties in the half-lives. Purpose: Two precision half-life measurements were performed for the T =1 /2 β+ emitters, 17F and 33Cl, in order to eliminate the half-life as the leading source of uncertainty in their f t values. Method: Half-lives of 17F and 33Cl were determined using β counting of implanted radioactive ion beam samples on a moving tape transport system at the Système de Production d'Ions Radioactifs Accélérés en Ligne low-energy identification station at the Grand Accélérateur National d'Ions Lourds. Results: The 17F half-life result, 64.347 (35) s, precise to ±0.05 % , is a factor of 5 times more precise than the previous world average. The half-life of 33Cl was determined to be 2.5038 (22) s. The current precision of ±0.09 % is nearly 2 times more precise compared to the previous world average. Conclusions: The precision achieved during the present measurements implies that the half-life no longer dominates the uncertainty of the f t values for both T =1 /2 mirror decays 17F and 33Cl.

Nuclear effects in the F3 structure function for finite and asymptotic Q2

International Nuclear Information System (INIS)

Kulagin, S.A.

1998-01-01

We study nuclear effects in the structure function F 3 which describes the parity violating part of the charged-current neutrino nucleon deep inelastic scattering. Starting from a covariant approach we derive a factorized expression for the nuclear structure function in terms of the nuclear spectral function and off-shell nucleon structure functions valid for arbitrary momentum transfer Q and in the limit of weak nuclear binding, i.e. when a nucleus can be treated as a non-relativistic system. We develop a systematic expansion of nuclear structure functions in terms of a Q -2 series caused by nuclear effects (''nuclear twist'' series). Basing ourselves on this expansion we calculate nuclear corrections to the Gross-Llewellyn-Smith sum rule as well as to higher moments of F 3 . We show that corrections to the GLS sum rule due to nuclear effects cancel out in the Bjorken limit and calculate the corresponding Q -2 correction. Special attention is paid to the discussion of the off-shell effects in the structure functions. A sizable impact of these effects both on the Q 2 and x dependence of nuclear structure functions is found. (orig.)

46 CFR 148.04-17 - Petroleum coke, calcined, at 130 °F or above.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false Petroleum coke, calcined, at 130 °F or above. 148.04-17...-17 Petroleum coke, calcined, at 130 °F or above. (a) The requirements of this part do not apply to bulk shipments of petroleum coke, calcined, on any vessel when the material is less than 130 °F. (b...

G.D.F. Suez view on the nuclear energy production

International Nuclear Information System (INIS)

Rorive, P.

2009-01-01

G.D.F. Suez was a pioneer of nuclear energy in Europe. It masters competencies internationally recognized on any part of this sector of energy production ( engineering, services, exploitation, maintenance, nuclear fuels, radioactive waste management, dismantling). it has and exploits 7 units in Belgium, and have capabilities in French nuclear power plants of Chooz and Tricastin. G.D.F. Suez has today ambitious goals in terms of nuclear projects development: to own and operate nuclear power plants of third generation in 2020, to maintain in Europe the share of nuclear in a balanced energy mix and to develop out of Europe a significant capability on several key-markets. To reach these objectives, the group develops an active policy of human resources, research and development and communication in matter of nuclear energy. (N.C.)

IL-17s adopt a cystine knot fold: structure and activity of a novel cytokine, IL-17F, and implications for receptor binding

Science.gov (United States)

Hymowitz, Sarah G.; Filvaroff, Ellen H.; Yin, JianPing; Lee, James; Cai, Liping; Risser, Philip; Maruoka, Miko; Mao, Weiguang; Foster, Jessica; Kelley, Robert F.; Pan, Guohua; Gurney, Austin L.; de Vos, Abraham M.; Starovasnik, Melissa A.

2001-01-01

The proinflammatory cytokine interleukin 17 (IL-17) is the founding member of a family of secreted proteins that elicit potent cellular responses. We report a novel human IL-17 homolog, IL-17F, and show that it is expressed by activated T cells, can stimulate production of other cytokines such as IL-6, IL-8 and granulocyte colony-stimulating factor, and can regulate cartilage matrix turnover. Unexpectedly, the crystal structure of IL-17F reveals that IL-17 family members adopt a monomer fold typical of cystine knot growth factors, despite lacking the disulfide responsible for defining the canonical ‘knot’ structure. IL-17F dimerizes in a parallel manner like neurotrophins, and features an unusually large cavity on its surface. Remarkably, this cavity is located in precisely the same position where nerve growth factor binds its high affinity receptor, TrkA, suggesting further parallels between IL-17s and neurotrophins with respect to receptor recognition. PMID:11574464

Operator support systems in nuclear power plants. Proceedings of a specialists meeting held in Moscow, Russian Federation, 17-21 May 1993

International Nuclear Information System (INIS)

1994-09-01

The 60 participants, representing 17 Member States, reviewed recent developments and discussed directions for future efforts in the area of computerized systems for operator support in nuclear power plants. During the meeting 31 papers were presented covering the wide spectrum of technical and scientific subjects including recent experience and benefits with operator support systems (OSS), design and implementation of OSSs, human aspects of introducing OSSs, qualification verification, validation and licensing, and international co-operation. Refs, figs and tabs

High IL-17E and low IL-17C dermal expression identifies a fibrosis-specific motif common to morphea and systemic sclerosis.

Directory of Open Access Journals (Sweden)

Paola Adele Lonati

Full Text Available BACKGROUND: High interleukin (IL-17A levels are characteristically found in the skin of systemic sclerosis (SSc individuals. Our aim was to investigate whether the dermal expression of IL-17A and related IL-17 family members (i.e. IL-17C, IL-17E and IL-17F could distinguish fibrotic from healthy skin and could show similarities in SSc and morphea, two disorders with presumed distinct pathogenesis, but characterized by skin fibrosis. METHODS: Biopsies were obtained from the involved skin of 14 SSc, 5 morphea and 8 healthy donors (HD undergoing plastic surgery. Immunohistochemistry/immunofluorescence techniques were coupled to a semi-automated imaging quantification approach to determine the presence of the IL-17 family members in the skin. The in vitro effects induced by the IL-17 family members on fibroblasts from normal and SSc individuals were assessed by ELISA and RIA. RESULTS: Positive cells for each of the IL-17 isoforms investigated were present in the dermis of all the individuals tested, though with variable frequencies. SSc individuals had increased frequency of IL-17A+ (p = 0.0237 and decreased frequency of IL-17F+ (p = 0.0127 and IL-17C+ cells (p = 0.0008 when compared to HD. Similarly, morphea individuals had less frequent IL-17C+ cells (p = 0.0186 in their skin but showed similar number of IL-17A+ and IL-17F+ cells when compared to HD. Finally, IL-17E+ cells were more numerous in morphea (p = 0.0109 and tended to be more frequent in SSc than in HD. Fibroblast production of IL-6, MMP-1 and MCP-1 was enhanced in a dose-dependent manner in the presence of IL-17E and IL-17F, but not in the presence of IL-17C. None of the cytokine tested had significant effect on type I collagen production. Of interest, in SSc the frequency of both IL-17A and IL-17F positive cells increased with disease duration. CONCLUSIONS: The frequency of IL-17A and IL-17F distinguish SSc to morphea individuals while dermal expression of IL-17C (low and IL-17E (high

Angular distribution of elastic scattering of 17F and 18Ne on proton

International Nuclear Information System (INIS)

Lu Zhaohui; Wu Heyu; Hu Rongjiang; Zhu Yongtai; Zhang Baoguo; Li Zuyu; Wei Zhiyong; Duan Liming; Wang Hongwei; Xiao Zhigang; Wang Sufang; Jin Genming; Guo Zhongyan; Xiao Guoqing; Zhu Haidong; Liu Yongying; Chen Keliang; Chen Tao; Li Xiangqing; Li Zhihuan

2002-01-01

Under reverse kinematics, elastic scattering of 17 F and 18 Ne on proton is studied. The experimental differential cross sections were measured. A kind of global optical potential with the CH89 parameters is used to describe the radioactive nucleus as an initial optical potential parameters. The experimental differential cross section data are analyzed by using the theoretical calculation code DWUCK4 with the distorted-wave Born approximation and parameter search subroutine ABOD which automatically searches the suitable parameters. Then the optical potential parameters of scattering 17 F and 18 Ne on proton are obtained. From the analyses of the optimized parameters, the real central potential mean-square radii of 17 F and 18 Ne, 3.239 fm and 3.317 fm are deduced, respectively

International Nuclear Information System 25 years

International Nuclear Information System (INIS)

Behrens, H.; Prinz, H.

1996-01-01

In May 1970, the first information was published in the International Nuclear Information System (Inis). This makes Inis the first system in the world to establish a decentralized international database. In creating Inis, the International Atomic Energy Agency wanted to promote the exchange of information about the peaceful uses of nuclear energy among its members. References to the nuclear literature were to be compiled in the most complete way possible. The number of IAEA member countries participating in Inis has increased from an original 38 to 90, that of international organizations, from 12 to 17. The database holds more than 1.8 million documentation units; stocks grow by some 75,000 units annually. The German literature about nuclear research and nuclear technology is collected, evaluated and entered into Inis by the Fachinformationszentrum Karlsruhe. (orig.) [de

Influence of intramolecular f-f interactions on nuclear spin driven quantum tunneling of magnetizations in quadruple-decker phthalocyanine complexes containing two terbium or dysprosium magnetic centers.

Science.gov (United States)

Fukuda, Takamitsu; Matsumura, Kazuya; Ishikawa, Naoto

2013-10-10

Nuclear spin driven quantum tunneling of magnetization (QTM) phenomena, which arise from admixture of more than two orthogonal electronic spin wave functions through the couplings with those of the nuclear spins, are one of the important magnetic relaxation processes in lanthanide single molecule magnets (SMMs) in the low temperature range. Although recent experimental studies have indicated that the presence of the intramolecular f-f interactions affects their magnetic relaxation processes, little attention has been given to their mechanisms and, to the best of our knowledge, no rational theoretical models have been proposed for the interpretations of how the nuclear spin driven QTMs are influenced by the f-f interactions. Since quadruple-decker phthalocyanine complexes with two terbium or dysprosium ions as the magnetic centers show moderate f-f interactions, these are appropriate to investigate the influence of the f-f interactions on the dynamic magnetic relaxation processes. In the present paper, a theoretical model including ligand field (LF) potentials, hyperfine, nuclear quadrupole, magnetic dipolar, and the Zeeman interactions has been constructed to understand the roles of the nuclear spins for the QTM processes, and the resultant Zeeman plots are obtained. The ac susceptibility measurements of the magnetically diluted quadruple-decker monoterbium and diterbium phthalocyanine complexes, [Tb-Y] and [Tb-Tb], have indicated that the presence of the f-f interactions suppresses the QTMs in the absence of the external magnetic field (H(dc)) being consistent with previous reports. On the contrary, the faster magnetic relaxation processes are observed for [Tb-Tb] than [Tb-Y] at H(dc) = 1000 Oe, clearly demonstrating that the QTMs are rather enhanced in the presence of the external magnetic field. Based on the calculated Zeeman diagrams, these observations can be attributed to the enhanced nuclear spin driven QTMs for [Tb-Tb]. At the H(dc) higher than 2000 Oe, the

Pluronic F127 nanomicelles engineered with nuclear localized functionality for targeted drug delivery

International Nuclear Information System (INIS)

Li, Yong-Yong; Li, Lan; Dong, Hai-Qing; Cai, Xiao-Jun; Ren, Tian-Bin

2013-01-01

PKKKRKV (Pro-Lys-Lys-Lys-Arg-Lys-Val, PV7), a seven amino acid peptide, has emerged as one of the primary nuclear localization signals that can be targeted into cell nucleus via the nuclear import machinery. Taking advantage of chemical diversity and biological activities of this short peptide sequence, in this study, Pluronic F127 nanomicelles engineered with nuclear localized functionality were successfully developed for intracellular drug delivery. These nanomicelles with the size ∼ 100 nm were self-assembled from F127 polymer that was flanked with two PV7 sequences at its both terminal ends. Hydrophobic anticancer drug doxorubicin (DOX) with inherent fluorescence was chosen as the model drug, which was found to be efficiently encapsulated into nanomicelles with the encapsulation efficiency at 72.68%. In comparison with the non-functionalized namomicelles, the microscopic observation reveals that PV7 functionalized nanomicelles display a higher cellular uptake, especially into the nucleus of HepG2 cells, due to the nuclear localization signal effects. Both cytotoxicity and apoptosis studies show that the DOX-loaded nanomicelles were more potent than drug nanomicelles without nuclear targeting functionality. It was thus concluded that PV7 functionalized nanomicelles could be a potentially alternative vehicle for nuclear targeting drug delivery. - Highlights: ► A new nuclear targeted drug delivery system based on micelles is developed. ► This micellar system features a core-shell structure with the size peaked at 100 nm. ► PV7, a short peptide sequence, is adopted as a nuclear targeting ligand. ► PV7 functionalized drug loaded micelles are more potent in killing tumor cells

RCC-F: Design and construction rules for PWR fire protection systems

International Nuclear Information System (INIS)

2013-01-01

The RCC-F code defines the rules for designing, building and installing the fire protection systems used to manage the nuclear hazards inherent in the outbreak of a fire inside the facility and thereby control the fundamental nuclear functions. The code provides fire protection recommendations in terms of: the industrial risk (loss of assets and/or operation), personnel safety, the environment. The code is divided into five main sections: generalities, design safety principles, fire protection design bases, construction provisions, rules for installing the fire protection components and equipment. The RCC-F code is available as an ETC-F version specifically for EPR projects (European pressurized reactor). Contents of the 2013 edition of the ETC-F code: Volume A - Generalities: Structure of ETC-F general points, documentation (in progress), chapter (provision) quality assurance; Volume B - Design safety principles: design nuclear safety principles; Volume C - Fire protection design bases: fire protection design bases; Volume D - Construction provisions: construction provisions; Volume E - Installation rules for fire protection: rules for installing the fire protection, components and equipment

High IL-17E and Low IL-17C Dermal Expression Identifies a Fibrosis-Specific Motif Common to Morphea and Systemic Sclerosis

OpenAIRE

Lonati, Paola Adele; Brembilla, Nicolò Costantino; Montanari, Elisa; Fontao, Lionel; Gabrielli, Armando; Vettori, Serena; Valentini, Gabriele; Laffitte, Emmanuel; Kaya, Gurkan; Meroni, Pier-Luigi; Chizzolini, Carlo

2014-01-01

BACKGROUND: High interleukin (IL)-17A levels are characteristically found in the skin of systemic sclerosis (SSc) individuals. Our aim was to investigate whether the dermal expression of IL-17A and related IL-17 family members (i.e. IL-17C, IL-17E and IL-17F) could distinguish fibrotic from healthy skin and could show similarities in SSc and morphea, two disorders with presumed distinct pathogenesis, but characterized by skin fibrosis. METHODS: Biopsies were obtained from the involved skin of...

Mechanism for G2 phase-specific nuclear export of the kinetochore protein CENP-F.

Science.gov (United States)

Loftus, Kyle M; Cui, Heying; Coutavas, Elias; King, David S; Ceravolo, Amanda; Pereiras, Dylan; Solmaz, Sozanne R

2017-08-03

Centromere protein F (CENP-F) is a component of the kinetochore and a regulator of cell cycle progression. CENP-F recruits the dynein transport machinery and orchestrates several cell cycle-specific transport events, including transport of the nucleus, mitochondria and chromosomes. A key regulatory step for several of these functions is likely the G2 phase-specific export of CENP-F from the nucleus to the cytosol, where the cytoplasmic dynein transport machinery resides; however, the molecular mechanism of this process is elusive. Here, we have identified 3 phosphorylation sites within the bipartite classical nuclear localization signal (cNLS) of CENP-F. These sites are specific for cyclin-dependent kinase 1 (Cdk1), which is active in G2 phase. Phosphomimetic mutations of these residues strongly diminish the interaction of the CENP-F cNLS with its nuclear transport receptor karyopherin α. These mutations also diminish nuclear localization of the CENP-F cNLS in cells. Notably, the cNLS is phosphorylated in the -1 position, which is important to orient the adjacent major motif for binding into its pocket on karyopherin α. We propose that localization of CENP-F is regulated by a cNLS, and a nuclear export pathway, resulting in nuclear localization during most of interphase. In G2 phase, the cNLS is weakened by phosphorylation through Cdk1, likely resulting in nuclear export of CENP-F via the still active nuclear export pathway. Once CENP-F resides in the cytosol, it can engage in pathways that are important for cell cycle progression, kinetochore assembly and the faithful segregation of chromosomes into daughter cells.

Search for Physics Beyond the Standard Model via Positron Polarization Measurements with Polarized $ ^{17} $F.

CERN Multimedia

Versyck, S

2002-01-01

This proposal aims at measuring the longitudinal polarization of positrons emitted from polarized $^{17} $F~nuclei. The experiment will have a comparable sensitivity to possible right-handed current contributions in the weak interaction as the experiment which was recently carried out with $ ^{107} $In in Louvain-la-Neuve, but will provide a more stringent limit due to the fact that, since $ ^{17} $F decays through a superallowed $\\beta$ -transition, the recoil-order corrections to the allowed approximation can be taken into account very precisely. Furthermore, because $ ^{17} $F decays via a mixed Fermi/Gamow-Teller $\\beta$ -transition, this experiment will also yield a new limit on possible scalar contributions to the weak interaction. While the $^{17}$F beam is being developed, part of the beamtime was used to perform a similar experiment with $^{118}$ Sb. As this isotope decays via a pure GT $\\beta$ -transition, this experiment will yield new limits on the possible presence of both right-handed and tensor...

17 CFR 240.15c3-1f - Optional market and credit risk requirements for OTC derivatives dealers (Appendix F to 17 CFR...

Science.gov (United States)

2010-04-01

... charges for market and credit risk pursuant to this Appendix F in lieu of computing securities haircuts...)(2)(vi). Credit Risk (d) The capital charge for credit risk arising from an OTC derivatives dealer's... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Optional market and credit...

A computer - aided system for the the E.D.F. 1400 MW. Nuclear power plants control

International Nuclear Information System (INIS)

Beltranda, G.; Philipps, C.

1988-01-01

The future E.D.F. 1400 MW nuclear power plants (due to be commissioned in 1991 at CHOOZ) are provided with a control and instrumentation system including the following levels: - sensors and actuators (LEVEL 0): this is the interface of the elementary acquisition and control signals; - the programmable logical and numerical controllers (LEVEL 1) for the logical control sequences and analog adjustment sequences for the whole equipment of the facilities; - the control room (LEVEL 2) including the computer-aided operation system as well as the wall mimic diagram and the auxiliary panel directly connected to the controllers. This is the processing and control conversational level; - the maintenance and site computer-aided systems (LEVEL 3). This paper aims at describing the computer-aided operation system (called KIC N4), its main functions, its architecture and the solutions retained as regards its softwares and the high-quality of data required. The achievement of this system has been entrusted by EDF to the SEMA. METRA/CIMSA-SINTRA grouping, among which SEMA.METRA is the leading company

Exclusive measurements of nuclear breakup reactions of 17Ne

International Nuclear Information System (INIS)

Wamers, F.; Marganiec, J.; Aksouh, F.; Aksyutina, Y.; Boretzky, K.; Chatillon, A.; Emling, H.; Geissel, H.; Heil, M.; Hoffmann, J.; Karagiannis, C.; Kiselev, O.A.; Kurz, N.; Larsson, K.; Litvinov, Y.A.; Nociforo, C.; Ott, W.; Simon, H.; Suemmerer, K.; Weick, H.; Alvarez-Pol, H.; Beceiro-Novo, S.; Cortina-Gil, D.; Rodriguez-Tajes, C.; Aumann, T.; Panin, V.; Bertulani, C.A.; Borge, M.J.G.; Galaviz, D.; Perea, A.; Tengblad, O.; Chartier, M.; Taylor, J.; Chulkov, L.V.; Egorova, I.A.; Ershova, O.; Langer, C.; Plag, R.; Reifarth, R.; Wimmer, C.; Forssen, C.; Johansson, H.; Jonson, B.; Nilsson, T.; Nyman, G.; Tengborn, E.; Zhukov, M.V.; Fraile, L.M.; Fynbo, H.; Riisager, K.; Grigorenko, L.V.; Hoffmann, D.H.; Richter, A.; Schrieder, G.; Karakoc, M.; Kratz, J.V.; Kulessa, R.; Lantz, M.; Le Bleis, T.; Lemmon, R.; Mahata, K.; Muentz, C.; Stroth, J.; Parfenova, Y.L.; Paschalis, S.; Rossi, D.; Savran, D.; Shul'gina, N.B.

2014-01-01

We have studied one-proton-removal reactions of about 500 MeV/u 17 Ne beams on a carbon target at the R 3 B/LAND setup at GSI by detecting beam-like 15 O-p and determining their relative-energy distribution. We exclusively selected the removal of a 17 Ne halo proton, and the Glauber-model analysis of the 16 F momentum distribution resulted in an s 2 contribution in the 17 Ne ground state of about 40 %. (authors)

IAEA: 17 countries are candidates for nuclear energy; AIEA: 17 pays candidats a l'energie nucleaire

Energy Technology Data Exchange (ETDEWEB)

Anon.

2011-01-15

In january 2011 IAEA announced that 17 countries had officially expressed their willingness to home nuclear power plants, they have filed applications for the construction of nuclear power plants. Among the countries concerned we find: Poland, Kuwait, Jordan, Morocco, Tunisia, Nigeria, Bangladesh, Thailand, Vietnam, Chile and Uruguay

Interleukin 17A and interleukin 17F polymorphisms are associated with oral squamous cell carcinoma susceptibility in a Chinese population.

Science.gov (United States)

Li, Ning; Zhang, Chao; Chen, Zhaoquan; Bai, Lilu; Nie, Min; Zhou, Bin; Xu, Huanxi

2015-02-01

Several studies have investigated the association of the interleukin (IL) 17A and IL-17F polymorphisms and cancer of various organs. However, the role of the IL-17A and IL-17F polymorphisms in oral squamous cell carcinoma (OSCC) remains unclear. Thus we sought to clarify the association of the rs2275913, rs763780, and rs2397084 polymorphisms with OSCC in a Chinese population. A TaqMan single-nucleotide polymorphism Genotyping Assay (ABI, Foster, CA) was used to measure the distributions of the IL-17A (rs2275913) and IL-17F (rs763780, rs2397084) polymorphisms in 121 OSCC patients and 103 healthy controls. The association of those polymorphisms and clinical OSCC patient characteristic also was evaluated. Individuals carrying the rs2275913 A allele and AA genotype had an increased risk of OSCC (odds ratio [OR], 1.463; 95% confidence interval [CI], 0.807 to 2.652; and OR, 2.713; 95% CI, 1.250 to 5.889, respectively). The frequency of the rs2397084 T allele was significantly associated with a higher risk of OSCC than the G allele (OR, 1.501; 95% CI, 1.026 to 2.196). No difference in rs763780 frequencies was observed. The rs2275913 AA and rs2397084 TT genotypes also were associated with late clinical stages and poor tumor differentiation. In addition, stratification analysis indicated that the rs2275913 AA genotype increased OSCC risk among smoking and drinking populations (OR, 4.000; 95% CI, 1.404 to 11.394; and OR, 3.500; 95% CI, 1.018 to 12.030, respectively). In a smoking population, an rs9382084 T-allele carrier has a greater potential risk of OSCC than the overall population (OR, 2.200; 95% CI, 1.009 to 4.797). The results of this study suggest a significant association of rs2275913 and rs2397084 but not rs763780 with OSCC risk, and this was related to tumor stage and differentiation. In addition, the IL-17A and IL-17F polymorphisms can interact with smoking and drinking to enhance the risk of OSCC developing. Copyright © 2015 American Association of Oral and

Overexpression of heterogeneous nuclear ribonucleoprotein F stimulates renal Ace-2 gene expression and prevents TGF-β1-induced kidney injury in a mouse model of diabetes.

Science.gov (United States)

Lo, Chao-Sheng; Shi, Yixuan; Chang, Shiao-Ying; Abdo, Shaaban; Chenier, Isabelle; Filep, Janos G; Ingelfinger, Julie R; Zhang, Shao-Ling; Chan, John S D

2015-10-01

We investigated whether heterogeneous nuclear ribonucleoprotein F (hnRNP F) stimulates renal ACE-2 expression and prevents TGF-β1 signalling, TGF-β1 inhibition of Ace-2 gene expression and induction of tubulo-fibrosis in an Akita mouse model of type 1 diabetes. Adult male Akita transgenic (Tg) mice overexpressing specifically hnRNP F in their renal proximal tubular cells (RPTCs) were studied. Non-Akita littermates and Akita mice served as controls. Immortalised rat RPTCs stably transfected with plasmid containing either rat Hnrnpf cDNA or rat Ace-2 gene promoter were also studied. Overexpression of hnRNP F attenuated systemic hypertension, glomerular filtration rate, albumin/creatinine ratio, urinary angiotensinogen (AGT) and angiotensin (Ang) II levels, renal fibrosis and profibrotic gene (Agt, Tgf-β1, TGF-β receptor II [Tgf-βrII]) expression, stimulated anti-profibrotic gene (Ace-2 and Ang 1-7 receptor [MasR]) expression, and normalised urinary Ang 1-7 level in Akita Hnrnpf-Tg mice as compared with Akita mice. In vitro, hnRNP F overexpression stimulated Ace-2 gene promoter activity, mRNA and protein expression, and attenuated Agt, Tgf-β1 and Tgf-βrII gene expression. Furthermore, hnRNP F overexpression prevented TGF-β1 signalling and TGF-β1 inhibition of Ace-2 gene expression. These data demonstrate that hnRNP F stimulates Ace-2 gene transcription, prevents TGF-β1 inhibition of Ace-2 gene transcription and induction of kidney injury in diabetes. HnRNP F may be a potential target for treating hypertension and renal fibrosis in diabetes.

Development of Cytoplasmic Male Sterile IR24 and IR64 Using CW-CMS/Rf17 System.

Science.gov (United States)

Toriyama, Kinya; Kazama, Tomohiko

2016-12-01

A wild-abortive-type (WA) cytoplasmic male sterility (CMS) has been almost exclusively used for breeding three-line hybrid rice. Many indica cultivars are known to carry restorer genes for WA-CMS lines and cannot be used as maintainer lines. Especially elite indica cultivars IR24 and IR64 are known to be restorer lines for WA-CMS lines, and are used as male parents for hybrid seed production. If we develop CMS IR24 and CMS IR64, the combination of F1 pairs in hybrid rice breeding programs will be greatly broadened. For production of CMS lines and restorer lines of IR24 and IR64, we employed Chinese wild rice (CW)-type CMS/Restorer of fertility 17 (Rf17) system, in which fertility is restored by a single nuclear gene, Rf17. Successive backcrossing and marker-assisted selection of Rf17 succeeded to produce completely male sterile CMS lines and fully restored restorer lines of IR24 and IR64. CW-cytoplasm did not affect agronomic characteristics. Since IR64 is one of the most popular mega-varieties and used for breeding of many modern varieties, the CW-CMS line of IR64 will be useful for hybrid rice breeding.

Global evolution of storm-time effects in the-F region during 17-18 December 1971

International Nuclear Information System (INIS)

Alamelu, V.; Mukunda Rao, M.; Sethuraman, R.

1982-01-01

The latitudinal variation of the effect of the great storm of 17 Dec. 71 is investigated by choosing stations of varying latitudes but of approximately the same longitude. In addition, three stations, one each in the American, African and Indian zone, are chosen to find the longitudinal changes produced during this storm. It is seen that the storm is mainly a negative one in the southern hemisphere of this longitude sector. The noon biteout is enhanced on the major storm day, viz., 17 Dec. 71, at the American equator, with large evening peaks on both 17th and 18th. The northern hemisphere does not exhibit any large change in the critical frequency of the F layer. The reported changes in TEC measurements are not reflected in the parameter f 0 F 2 at Lindau

Nuclear science symposium, 26th and symposium on nuclear power systems, 11th, 1979

International Nuclear Information System (INIS)

Kerns, C.R.

1980-01-01

Proceedings include 163 of the papers presented at the combined meetings, as well as two papers delivered at the plenary session on plant control beyond the 1980's and ionizing radiation dose hazards. One-hundred-and-sixty-two papers are indexed separately. Nuclear Science symposium included calorimeters and specific ionization (17 papers); PWC and Drift Chambers (7 papers); photo/optical detectors (10 papers); semiconductor detectors (11 papers); nuclear circuits and systems (11 papers); space instrumentation (9 papers); medical instrumentation (30 papers); data preprocessing (6 papers); data acquisition (11 papers); environmental instrumentation (15 papers); reactor instrumentation (16 papers). Fifteen Nuclear Systems Symposium papers covered: safety, RFI effects, detectors, monitoring systems, reactor protection, multiplexing of circuits, standard application, emergency planning and preparedness and operator/instrumentation interactions

The IL-17A G-197A and IL-17F 7488T/C polymorphisms are associated with increased risk of cancer in Asians: a meta-analysis

Directory of Open Access Journals (Sweden)

Wang H

2015-09-01

Full Text Available Huifen Wang,1,* Yanli Zhang,1,* Zhaolan Liu,2 Yin Zhang,3 Hongchuan Zhao,1 Shiyu Du1 1Department of Gastroenterology, China-Japan Friendship Hospital, 2Center for Evidence-Based Chinese Medicine, Beijing University of Chinese Medicine, 3Institute of Basic Research in Clinical Medicine, China Academy of Chinese Medical Sciences, Beijing, People’s Republic of China *These authors contributed equally to this work Background: Interleukin-17 (IL-17 is a family of emerged pro-inflammatory cytokines. The IL-17A and IL-17F are two important members of IL-17 family. Previous studies have shown that the functional IL-17A G-197A and IL-17F 7488T/C polymorphisms may contribute to susceptibility to cancer but the results were inconclusive. This meta-analysis was performed to determine the exact association between IL-17 polymorphisms and cancer risk.Methods: Online databases were searched to identify eligible case–control studies. Pooled odds ratios (ORs and confidence intervals (CIs were calculated by fixed-effect models or random-effect models. Publication bias was detected by Egger’s test and Begg’s test.Results: Nine eligible case–control studies of IL-17A G-197A and seven studies of IL-17F 7488T/C, including 3,181 cases and 4,005 controls, were identified. Pooled analysis suggested the variant IL-17A-197A allele was associated with increased risk cancer (GA/AA vs GG, OR =1.27, 95% CI: 1.15, 1.41, Pheterogeneity =0.374; and A vs G, OR =1.30, 95% CI: 1.17, 1.45, Pheterogeneity =0.021. For IL-17F 7488T/C, the homozygote 7488CC genotype significantly increased risk of cancer (CC vs TC/TT, OR =1.36, 95% CI: 0.97, 1.91, Pheterogeneity =0.875; and CC vs TT, OR =1.39, 95% CI: 1.03, 1.88, Pheterogeneity =0.979, especially for gastric cancer.Conclusion: The variant IL-17A-197A allele and IL-17F 7488CC genotype were associated with increased risk of cancer, especially for gastric cancer. Keywords: interleukin-17, gene polymorphism, gastric cancer, risk

Operation status display and monitoring system for BWR nuclear power plant

International Nuclear Information System (INIS)

Wakabayashi, Yasuo; Hayakawa, Hiroyasu; Kawamura, Atsuo; Kaneda, Mitsunori.

1982-01-01

Lately, the development of the system has been made for BWR plants, which monitors the operating status not only in normal operation but also in abnormal state and also for plant safety. Recently, the improvement of man-machine interface has been tried through the practical use of technique which displays data collectively on a CRT screen relating them mutually. As one of those results, the practical use of an electronic computer and color CRT display for No. 1 unit in the Fukushima No. 2 Nuclear Power Station (2F-1), Tokyo Electric Power Co., is described. Also, new centralized control panels containing such systems were used for the 1100 MWe BWR nuclear power plants now under construction, No. 3 unit of the Fukushima No. 2 Power Station and No. 1 unit of Kashiwazaki-Kariwa Nuclear Power Station (2F-3 and K-1, respectively). The display and monitoring system in 2F-1 plant is the first one in which a computer and color CRTs were practically employed for a BWR plant in Japan, and already in commercial operation. The advanced operating status monitoring system, to which the result of evaluation of the above system was added, was incorporated in the new centralized control panels presently under production for 2F-3 and K-1 plants. The outline of the system, the functions of an electronic computer, plant operating status monitor, surveillance test guide, the automation of plant operation and auxiliary operation guide are reported for these advanced monitoring system. It was confirmed that these systems are useful means to improve the man-machine communication for plant operation minitoring. (Wakatsuki, Y.)

Thermal Aging Effect Analysis of 17-4PH Martensitic Stainless Steel Valves for Nuclear Power Plant

Institute of Scientific and Technical Information of China (English)

BAI; Bing; ZHANG; Chang-yi; TONG; Zhen-feng; YANG; Wen

2015-01-01

The valve stem used in the main steam system of nuclear power plant is usually martensitic stainless steel(such as 17.4ph16.4Mo etc.).When served in high temperature for a long time,the thermal aging embrittlement of valve stem will be significant,and even lead to the fracture.

Nuclear renaissance in Asia. Energy security and development of nuclear power generation system

International Nuclear Information System (INIS)

Nakasugi, Hideo

2009-01-01

The energy policy and strategy of development of nuclear power generation system of China, India and Korea are stated on the basis of use of light water reactors (LWRs). The conditions of power generation and introduction plans of nuclear energy of other Asian countries such as Vietnam, Thailand, Indonesia, Malaysia and Philippines are described. The power plant capacity of China increased from 50,500 MW in 2004, to 65,000 MW in 2005, and the target value is 40,000 MW of operating nuclear plants and 18,000 MW in building in 2020. China is lagging behind in peaceful use of nuclear energy technologies. A plan for the reform of nuclear industry and nuclear power generation projects of China are summarized. Total power plant capacity of India is 145,000 MW, but the nuclear plant capacity is 4,120 MW in 2008 and 63,000 MW of the target in 2032. Development of nuclear power, circumstance, and cooperation with other countries' industries are explained. 17,716 MW of nuclear power is in operation, 6,800 MW in building and 2,800 MW in the planning stage in Korea. History of development of national reactors and the subjects of development of the fourth generation reactor of Korea are stated. Management system of nuclear power plants in China, technical bases of nuclear power plants in China, development system of nuclear power generation in India, the conditions of power production of Korea in 2008, the capacity factor of Korea, Japan and world from 1998 to 2008, and comparison of nuclear industries in China, India and Korea are illustrated. (S.Y.)

Kinetics of Chronic Oxidation of NBG-17 Nuclear Graphite by Water Vapor

Energy Technology Data Exchange (ETDEWEB)

Contescu, Cristian I [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Burchell, Timothy D [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mee, Robert [Univ. of Tennessee, Knoxville, TN (United States)

2015-05-01

This report presents the results of kinetic measurements during accelerated oxidation tests of NBG-17 nuclear graphite by low concentration of water vapor and hydrogen in ultra-high purity helium. The objective is to determine the parameters in the Langmuir-Hinshelwood (L-H) equation describing the oxidation kinetics of nuclear graphite in the helium coolant of high temperature gas-cooled reactors (HTGR). Although the helium coolant chemistry is strictly controlled during normal operating conditions, trace amounts of moisture (predictably < 0.2 ppm) cannot be avoided. Prolonged exposure of graphite components to water vapor at high temperature will cause very slow (chronic) oxidation over the lifetime of graphite components. This behavior must be understood and predicted for the design and safe operation of gas-cooled nuclear reactors. The results reported here show that, in general, oxidation by water of graphite NBG-17 obeys the L-H mechanism, previously documented for other graphite grades. However, the characteristic kinetic parameters that best describe oxidation rates measured for graphite NBG-17 are different than those reported previously for grades H-451 (General Atomics, 1978) and PCEA (ORNL, 2013). In some specific conditions, certain deviations from the generally accepted L-H model were observed for graphite NBG-17. This graphite is manufactured in Germany by SGL Carbon Group and is a possible candidate for the fuel elements and reflector blocks of HTGR.

Quantitative Analysis of KF-LiF-ZrF4 Molten Salt by Probe Assisted in-situ LIBS Systems

International Nuclear Information System (INIS)

Kim, S.H.; Moon, J.H.; Kim, D.H.; Hwang, I.S.; Lee, J.H.

2015-01-01

Full text of publication follows: Pyro-processing draws attention as a recycling process of spent nuclear fuel for future nuclear reactor. In the aspect of process control and safeguards of the pyro-processing, it requires a technology to measure the concentration of molten salt in real-time. The existing technologies measure the concentration by chemical analysis of sampled molten salt in the hot cell but it is disadvantageous in the aspects of cost, safety and time. The LIBS (Laser-Induced Breakdown Spectroscopy) is a form of atomic emission spectroscopy in which a pulsed laser is used as the excitation source. LIBS technology is appropriate to measure sensitive nuclear materials in hot cell because it is capable of measuring specimen quantitatively and qualitatively by exited atom by laser. Spectrum obtained from plasma is largely influenced by laser operation conditions and physical properties of specimens. Also, plasma induction is limited on the surface of specimen, so analysis of composition inside of the molten salt is extremely difficult. Thus, several restrictions should be overcome in order to apply LIBS for the measurement of molten salt (KF-LiF-ZrF 4 ) composition in real-time. In this study probe assisted LIBS system will be introduced with KF-LiF-ZrF 4 to quantitatively measure molten salt composition. Echelle spectrometer was used and the measurable wavelength area was 250-400 nm, the range of UV ray. NIST atomic spectra database measured the wavelength for molten salt composition, and each element was selected high signal intensity and wavelength range that is not overlapped by other elements. (authors)

New reactor technology: safety improvements in nuclear power systems.

Science.gov (United States)

Corradini, M L

2007-11-01

Almost 450 nuclear power plants are currently operating throughout the world and supplying about 17% of the world's electricity. These plants perform safely, reliably, and have no free-release of byproducts to the environment. Given the current rate of growth in electricity demand and the ever growing concerns for the environment, nuclear power can only satisfy the need for electricity and other energy-intensive products if it can demonstrate (1) enhanced safety and system reliability, (2) minimal environmental impact via sustainable system designs, and (3) competitive economics. The U.S. Department of Energy with the international community has begun research on the next generation of nuclear energy systems that can be made available to the market by 2030 or earlier, and that can offer significant advances toward these challenging goals; in particular, six candidate reactor system designs have been identified. These future nuclear power systems will require advances in materials, reactor physics, as well as thermal-hydraulics to realize their full potential. However, all of these designs must demonstrate enhanced safety above and beyond current light water reactor systems if the next generation of nuclear power plants is to grow in number far beyond the current population. This paper reviews the advanced Generation-IV reactor systems and the key safety phenomena that must be considered to guarantee that enhanced safety can be assured in future nuclear reactor systems.

IAEA: up to 17% of nuclear power by 2050

International Nuclear Information System (INIS)

Anon.

2010-01-01

At the end of 2009 the contribution of nuclear energy to the world production of electricity reached 13.8%. Nearly two thirds of this production came from conventional fossil-fueled power plants, 18% from hydroelectric power plants and only 1.4% from renewable energy sources. The IAEA foresees: -) that about 55% of the primary energy used in the world in 2050 will be used to produce electricity, today this ratio is 37%; -) that the world demand for electricity will have increased threefold by 2050; and -) that the contribution of nuclear energy for electricity production at the world scale will be somewhere between 7.1 and 17 per cent. (A.C.)

RSS SSMIS OCEAN PRODUCT GRIDS DAILY FROM DMSP F17 NETCDF V7

Data.gov (United States)

National Aeronautics and Space Administration — The RSS SSMIS Ocean Product Grids Daily from DMSP F17 netCDF dataset is part of the collection of Special Sensor Microwave/Imager (SSM/I) and Special Sensor...

Post-transcription cleavage generates the 3' end of F17R transcripts in vaccinia virus

International Nuclear Information System (INIS)

D'Costa, Susan M.; Antczak, James B.; Pickup, David J.; Condit, Richard C.

2004-01-01

Most vaccinia virus intermediate and late mRNAs possess 3' ends that are extremely heterogeneous in sequence. However, late mRNAs encoding the cowpox A-type inclusion protein (ATI), the second largest subunit of the RNA polymerase, and the late telomeric transcripts possess homogeneous 3' ends. In the case of the ATI mRNA, it has been shown that the homogeneous 3' end is generated by a post-transcriptional endoribonucleolytic cleavage event. We have determined that the F17R gene also produces homogeneous transcripts generated by a post-transcriptional cleavage event. Mapping of in vivo mRNA shows that the major 3' end of the F17R transcript maps 1262 nt downstream of the F17R translational start site. In vitro transcripts spanning the in vivo 3' end are cleaved in an in vitro reaction using extracts from virus infected cells, and the site of cleavage is the same both in vivo and in vitro. Cleavage is not observed using extract from cells infected in the presence of hydroxyurea; therefore, the cleavage factor is either virus-coded or virus-induced during the post-replicative phase of virus replication. The cis-acting sequence responsible for cleavage is orientation specific and the factor responsible for cleavage activity has biochemical properties similar to the factor required for cleavage of ATI transcripts. Partially purified cleavage factor generates cleavage products of expected size when either the ATI or F17R substrates are used in vitro, strongly suggesting that cleavage of both transcripts is mediated by the same factor

Nuclear instrumentation in VENUS-F

Science.gov (United States)

Wagemans, J.; Borms, L.; Kochetkov, A.; Krása, A.; Van Grieken, C.; Vittiglio, G.

2018-01-01

VENUS-F is a fast zero power reactor with 30 wt% U fuel and Pb/Bi as a coolant simulator. Depending on the experimental configuration, various neutron spectra (fast, epithermal, and thermal islands) are present. This paper gives a review of the nuclear instrumentation that is applied for reactor control and in a large variety of physics experiments. Activation foils and fission chambers are used to measure spatial neutron flux profiles, spectrum indices, reactivity effects (with positive period and compensation method or the MSM method) and kinetic parameters (with the Rossi-alpha method). Fission chamber calibrations are performed in the standard irradiation fields of the BR1 reactor (prompt fission neutron spectrum and Maxwellian thermal neutron spectrum).

NJOY nuclear data processing system. Volume IV. The ERRORR and COVR modules

International Nuclear Information System (INIS)

Muir, D.W.; MacFarlane, R.E.

1985-12-01

The NJOY nuclear data processing system is a comprehensive computer code package for producing cross sections and related nuclear parameters from ENDF/B evaluated nuclear data. This volume provides detailed descriptions of the NJOY modules ERRORR and COVR, which are concerned with the covariances (uncertainties and correlations) of multigroup cross sections and fission neutron yield (anti nu) values. 17 refs

Cloning, Expression, and Immunogenicity of Fimbrial-F17A Subunit Vaccine against Escherichia coli Isolated from Bovine Mastitis

Directory of Open Access Journals (Sweden)

Wei Chen

2017-01-01

Full Text Available There is a need to identify and select new promising immunodominant antigens that have the ability to provide protective immunity against E. coli causing bovine mastitis. Recently we showed that f17a was found to be the most prevalent and crucial virulent factor among the pathogenic E. coli isolated from bovine mastitis. Here, in this report, the recombinant F17A based subunit vaccine adjuvant with MF59 was tested for immunogenicity against E. coli in a murine model. The vaccinated mice did not show any abnormal behavioral changes and histopathological lesions after vaccination. The specific antibody level against F17A was significantly higher in MF59-adjuvant-group, and also lasted for longer duration with a significant (P<0.01 production level of IgG1 and IgG2a. Moreover, we noted higher survival rate in mice injected with F17A-MF59-adjuvant group after challenging with the clinical E. coli strain. Our findings of bacterial clearance test revealed that elimination rate from liver, spleen, and kidney in MF59-adjuvant-group was significantly higher than the control group. Finally, the proportion of CD4+T cells was increased, while CD8+ was decreased in MF59-adjuvant group. In conclusion, the current study reveals the capability of F17A-MF59 as a potential vaccine candidate against pathogenic E. coli causing mastitis in dairy animals.

Supersymmetry for nuclear cluster systems

International Nuclear Information System (INIS)

Levai, G.; Cseh, J.; Van Isacker, P.

2001-01-01

A supersymmetry scheme is proposed for nuclear cluster systems. The bosonic sector of the superalgebra describes the relative motion of the clusters, while its fermionic sector is associated with their internal structure. An example of core+α configurations is discussed in which the core is a p-shell nucleus and the underlying superalgebra is U(4/12). The α-cluster states of the nuclei 20 Ne and 19 F are analysed and correlations between their spectra, electric quadrupole transitions, and one-nucleon transfer reactions are interpreted in terms of U(4/12) supersymmetry. (author)

Fast accelerator driven subcritical system for energy production: nuclear fuel evolution

International Nuclear Information System (INIS)

Barros, Graiciany de P.; Pereira, Claubia; Veloso, Maria A.F.; Costa, Antonella L.

2011-01-01

Accelerators Driven Systems (ADS) are an innovative type of nuclear system, which is useful for long-lived fission product transmutation and fuel regeneration. The ADS consist of a coupling of a sub-critical nuclear core reactor and a proton beam produced by a particle accelerator. These particles are injected into a target for the neutrons production by spallation reactions. The neutrons are then used to maintain the fission chain in the sub-critical core. The aim of this study is to investigate the nuclear fuel evolution of a lead cooled accelerator driven system used for energy production. The fuel studied is a mixture based upon "2"3"2Th and "2"3"3U. Since thorium is an abundant fertile material, there is hope for the thorium-cycle fuels for an accelerator driven sub-critical system. The target is a lead spallation target and the core is filled with a hexagonal lattice. High energy neutrons are used to reduce the negative reactivity caused by the presence of protoactinium, since this effect is most pronounced in the thermal range of the neutron spectrum. For that reason, such material is not added moderator to the system. In this work is used the Monte Carlo code MCNPX 2.6.0, that presents the the depletion/ burnup capability. The k_e_f_f evolution, the neutron energy spectrum in the core and the nuclear fuel evolution using ADS source (SDEF) and kcode-mode are evaluated during the burnup. (author)

[7α-18F]fluoro-17α-methyl-5α-dihydrotestosterone: a ligand for androgen receptor-mediated imaging of prostate cancer

International Nuclear Information System (INIS)

Garg, Pradeep K.; Labaree, David C.; Hoyte, Robert M.; Hochberg, Richard B.

2001-01-01

We have synthesized a 18 F-labeled androgen, [7α- 18 F]fluoro-17α-methyl-5α-dihydrotestosterone, in a no-carrier-added radiosynthesis by exchange of 18 F- (tetrabutylammonium fluoride) with the 7β-tosyloxy of 17α-methyl-5α-dihydrotestosterone. The nonradioactive steroid binds with high affinity and specificity to the androgen receptor and binds poorly, if at all, to other steroid receptors and plasma sex hormone binding globulin. The 7α- 18 F-androgen concentrates markedly in the prostate of rats by an androgen receptor-dependent mechanism. It is likely that [7α- 18 F]fluoro-17α-methyl-5α-dihydrotestosterone will be an excellent positron emission tomography imaging agent for prostate cancer

Thermal analysis and phase diagrams of the LiF BiF3 e NaF BiF3 systems

International Nuclear Information System (INIS)

Nakamura, Gerson Hiroshi de Godoy

2013-01-01

Investigations of the binary systems LiF-BiF 3 and NaF-BiF 3 were performed with the objective of clarifying the thermal behavior and phase equilibria of these systems and their intermediary phases, an important requisite for high-quality crystal growth. Several samples in the entire range of compositions (0 to 100 mol% BiF 3 ) of both systems were subjected to experiments of differential thermal analysis (DTA) and thermogravimetry (TG), and also of differential scanning calorimetry (DSC). A few specific compositions were selected for X-ray diffraction to supplement the experimental data. Due to the high vulnerability of BiF 3 to oxygen contamination, its volatility and propensity to destroy metal parts upon heating, it was necessary to determine the optimal conditions for thermal analysis before investigating the systems themselves. Phase relations in the system LiF-BiF 3 were completely clarified and a phase diagram was calculated and evaluated via the commercial software Factsage. The diagram itself consists in a simple peritectic system in which the only intermediary compound, LiBiF 4 , decomposes into LiF and a liquid phase. The NaF-BiF 3 system could not be completely elucidated and the phase relations in the NaF poor side (> 50% BiF 3 ) are still unknown. In the NaF rich side, however, the possible peritectoid decomposition of the compound NaBiF 4 was identified. In both systems X-ray diffraction yielded crystal structures discrepant with the literature for the intermediary phases, LiBiF 4 , NaBiF 4 and a solid solution of NaF and BiF 3 called I. The observed structures remain unknown and explanations for the discrepancies were proposed. (author)

Investigation into the MgF2-NiF2, CaF2-NiF2, SrF2-NiF2 systems

International Nuclear Information System (INIS)

Ikrami, D.D.; Petrov, S.V.; Fedorov, P.P.; Ol'khovaya, L.A.; Luginina, A.A.; AN SSSR, Moscow. Inst. Fizicheskikh Problem; AN SSSR, Moscow. Inst. Kristallografii)

1984-01-01

Using the methods of differential thermal and X-ray phase analyses the systems MgF 2 -NiF 2 , CaF 2 -NiF 2 , SrF 2 -NiF 2 have been studied. In the system SrF 2 -NiF 2 the only orthorhombic compounds SrNiF 4 (a=14.43; b=3.93; c=5.66 (+-0.01 A)) is formed. SrNiF 4 density constitutes: dsub(X-ray)=4.60+-0.01 g/cm 3 , dsub(exp.)=4.60+-0.03 g/cm 3 . Refraction indices are as follows SrNiF 4 :Ng=1.500; Nsub(m)=1.497; Nsub(p)=1.479. SrNiF 4 magnetic ordering temperature Tsub(N) approximately 100 K

Shell model description of 16O(p,γ)17F and 16O(p,p)16O reactions

International Nuclear Information System (INIS)

Bennaceur, K.; Michel, N.; Okolowicz, J.; Ploszajczak, M.; Bennaceur, K.; Nowacki, F.; Okolowicz, J.

2000-01-01

We present shell model calculations of both the structure of 17 F and the reactions 16 O(p,γ) 17 F, 16 O(p,p) 16 O. We use the ZBM interaction which provides a fair description of the properties of 16 O and neighbouring nuclei and, in particular it takes account for the complicated correlations in coexisting low-lying states of 16 O. (authors)

Inflammatory Dietary Pattern, IL-17F Genetic Variant, and the Risk of Colorectal Cancer.

Science.gov (United States)

Cho, Young Ae; Lee, Jeonghee; Oh, Jae Hwan; Chang, Hee Jin; Sohn, Dae Kyung; Shin, Aesun; Kim, Jeongseon

2018-06-05

A proinflammatory diet may increase the risk of colorectal cancer, but its role may differ according to individuals' genetic variants. We aimed to examine whether a specific dietary pattern reflecting inflammation was associated with a risk of colorectal cancer and whether IL-17F genetic variant altered this association. In a study of 695 colorectal cancer cases and 1846 controls, we derived a reduced rank regression dietary pattern using 32 food groups as predictors and the plasma C-reactive protein (CRP) concentration as the response. High CRP levels were associated with a high risk of colorectal cancer (OR (95% CI) = 3.58 (2.65⁻4.82) for the highest quartile vs. lowest quartile). After adjusting for potential confounding factors, high pattern scores were associated with a high risk of colorectal cancer (OR (95% CI) = 9.98 (6.81⁻14.62) for the highest quartile vs. lowest quartile). When stratified by the IL-17F rs763780 genotype, this association was stronger for individuals carrying the C allele ( p for interaction = 0.034), particularly for individuals with rectal cancer ( p for interaction = 0.011). In conclusion, a dietary pattern reflecting inflammation was significantly associated with colorectal cancer risk. Moreover, this association could be modified according to the IL-17F rs763780 genotype and anatomic site.

Functional expression of BMP7 receptors in oral epithelial cells. Interleukin-17F production in response to BMP7.

Science.gov (United States)

Nishio, Kensuke; Ozawa, Yasumasa; Ito, Hisanori; Kifune, Takashi; Narita, Tatsuya; Iinuma, Toshimitsu; Gionhaku, Nobuhito; Asano, Masatake

2017-10-01

Bone morphogenetic proteins (BMPs) are members of the transforming growth factor-β (TGF-β) superfamily. Recently, BMP7 has been demonstrated to be produced by salivary glands and contribute to embryonic branching in mice. The BMP7 in saliva is thought to be delivered to the oral cavity and is expected to contact with stratified squamous epithelial cells which line the surface of oral mucosa. In this study, we attempted to investigate the effects of BMP7 on oral epithelial cells. The expression of BMP receptors was examined by reverse transcriptase-polymerase chain reaction (RT-PCR). OSCCs were stimulated with human recombinant BMP7 (hrBMP7) and the phosphorylation status of Smad1/5/8 was examined by western blotting. For microarray analysis, Ca9-22 cells were stimulated with 100 ng/mL of hrBMP7 and total RNA was extracted and subjected to real-time PCR. The 5'-untranslated region (5'-UTR) of IL-17 F gene was cloned to pGL4-basic vector and used for luciferase assay. Ca9-22 cells were pre-incubated with DM3189, a specific inhibitor of Smad1/5/8, for inhibition assay. All isoforms of type I and type II BMP receptors were expressed in both Ca9-22 and HSC3 cells and BMP7 stimulation resulted in the phosphorylation of Smad1/5/8 in both cell lines. The microarray analysis revealed the induction of interleukin-17 F (IL-17 F), netrin G2 (NTNG2) and hyaluronan synthase 1 (HAS1). Luciferase assay using the 5'-UTR of the IL-17 F gene revealed transcriptional regulation. Induced IL-17 F production was further confirmed at the protein level by ELISA. Smad1/5/8 inhibitor pretreatment decreased IL-17 F expression levels in the cells.

Formulation and in vitro evaluation of 17-allyamino-17-demethoxygeldanamycin (17-AAG) loaded polymeric mixed micelles for glioblastoma multiforme.

Science.gov (United States)

Saxena, Vipin; Hussain, Muhammad Delwar

2013-12-01

Glioblastoma multiforme (GBM) is the most common and aggressive malignant primary brain tumor in human. 17-Allylamino-17-demethoxy geldanamycin (17-AAG) is an inhibitor of heat shock protein 90 (HSP90). The highly lipophilic nature and selective targeting of tumor cells makes 17-AAG a promising candidate for therapy of GBMs but poor water solubility, short biological half-life and hepatotoxicity limited its clinical use. Polymeric mixed micelles composed of Pluronic® P-123 and F-127 (2:1 (w/w)) containing 17-AAG were prepared and characterized. Cellular uptake and in vitro cytotoxicity of the prepared micelles were determined in U87MG human glioblastoma cells. The particle size of 17-AAG loaded Pluronic(®) P-123 and F-127 mixed micelles was 22.2 ± 0.1 nm; drug loading was about 4.0 ± 0.5% (w/w) with 88.2 ± 3.1% (w/w) encapsulation efficiency. About 90% of drug was released from the nanoparticles over 8 days. Cellular uptake studies showed intracellular uptake of mixed micelles. Cytotoxicity study showed 5-fold increase (P AAG-loaded mixed micelles to free 17-AAG. Due to their targeting ability, size, high drug loading and controlled release behavior, 17-AAG loaded Pluronic(®) P-123 and F-127 mixed micelles might be developed as a delivery system for GBM treatment. © 2013 Elsevier B.V. All rights reserved.

{sup 18}F-FDG metabolism in a rat model of chronic infarction. A 17-sector semiquantitative analysis

Energy Technology Data Exchange (ETDEWEB)

Penuelas, I. [Clinica Universitaria de Navarra, Pamplona (Spain). Dept. of Nuclear Medicine; MicroPET Research Unit CIMA-CUN, Pamplona (Spain); Abizanda, G.; Mazo, M.; Prosper, F. [Clinica Universitaria de Navarra, Pamplona (Spain). Hematology and Cell Therapy Service; Navarra Univ., Pamplona (Spain). Foundation for Applied Medical Research; Garcia-Velloso, M.J.; Marti-Climent, J.M.; Richter, J.A. [Clinica Universitaria de Navarra, Pamplona (Spain). Dept. of Nuclear Medicine; Gavira, J.J.; Barba, J. [Clinica Universitaria de Navarra, Pamplona (Spain). Cardiology and Cardiovascular Surgery; Ecay, M.; Collantes, M. [MicroPET Research Unit CIMA-CUN, Pamplona (Spain); Garcia de Jalon, J.A.; Garcia-Rodriguez, A. [Zaragoza Univ. (Spain). Dept. of Animal Pathology

2007-07-01

Strategies to establish the functional benefit of cell therapy in cardiac regeneration and the potential mechanism are needed. Aims: Development of a semi-quantitative method for non invasive assessment of cardiac viability and function in a rat model of myocardial infarction (MI) based on the use of microPET. Animals, methods: Ten rats were subjected to myocardial imaging 2, 7, 14, 30, 60 and 90 days after left coronary artery ligation. Intravenous {sup 18}F-fluoro-2-deoxy-2-D-glucose ({sup 18}F-FDG) was administered and regional {sup 18}F activity concentrations per unit area were measured in 17 regions of interest (ROIs) drawn on cardiac polar maps. By comparing the differences in {sup 18}F uptake between baseline and each of the follow up time points, parametric polar maps of statistical significance (PPMSS) were calculated. Left ventricular ejection fraction (LVEF) was blindly assessed echocardiographically. All animals were sacrificed for histopathological analysis after 90 days. Results: The diagnostic quality of {sup 18}F-FDG microPET images was excellent. PPMSS demonstrated a statistically significant decrease in {sup 18}F concentrations as early as 48 hours after MI in 4 of the 17 ROIs (segments 7, 13, 16 and 17; p <0.05) that persisted throughout the study. Semi-quantitative analysis of {sup 18}F-FDG uptake correlated with echocardiographic decrease in LVEF (p <0.001). Conclusion: The use of PPMSS based on 18F-FDG-microPET provides valuable semi-quantitative information of heart glucose metabolism allowing for non-invasive follow up thus representing a useful strategy for assessment of novel therapies in cardiac regeneration. (orig.)

Quality management system in Nuclear Medicine

International Nuclear Information System (INIS)

Peña Tornet, Adela; Torres Aroche, Leonel A.

2016-01-01

Establishing Management Systems (QMS) in services Nuclear Medicine (NM) is a prerequisite for optimizing the efficacy and safety of diagnostic and therapeutic procedures of this specialty and increase steadily the quality of the services provide patients. Several international organizations such as the IAEA and scientific specialty societies (SNM, EBNM, etc) and national bodies stimulate and enhance their introduction; in our country is also a requirement of the National Nuclear Safety Centre (CNSN). Are presented in this paper, the main experiences of our country related to the implementation of QMS and developed tools for achieving this goal, such as: The QNUMED automated web environment for managing indicators and documentation format digital; b) The development of prototypes and models for the implementation of the documentation system; d) requirements applying QUANUM in conducting audits of quality management in local services including QUANUM T ool tool; and f) human resource development issues in Quality Management. (author)

NNS computing facility manual P-17 Neutron and Nuclear Science

International Nuclear Information System (INIS)

Hoeberling, M.; Nelson, R.O.

1993-11-01

This document describes basic policies and provides information and examples on using the computing resources provided by P-17, the Neutron and Nuclear Science (NNS) group. Information on user accounts, getting help, network access, electronic mail, disk drives, tape drives, printers, batch processing software, XSYS hints, PC networking hints, and Mac networking hints is given

{beta}-Ray angular distribution from purely nuclear spin aligned {sup 20}F

Energy Technology Data Exchange (ETDEWEB)

Nagatomo, T., E-mail: nagatomo@riken.jp [RIKEN Nishina Center (Japan); Matsuta, K. [Osaka University (Japan); Minamisono, K. [NSCL/MSU (United States); Sumikama, T. [Tokyo University of Science (Japan); Mihara, M. [Osaka University (Japan); Ozawa, A.; Tagishi, Y. [University of Tsukuba (Japan); Ogura, M.; Matsumiya, R.; Fukuda, M. [Osaka University (Japan); Yamaguchi, M.; Yasuno, T.; Ohta, H.; Hashizume, Y. [University of Tsukuba (Japan); Fujiwara, H. [Osaka University (Japan); Chiba, A. [University of Tsukuba (Japan); Minamisono, T. [Fukui University of Technology (Japan)

2007-11-15

The alignment correlation term in the {beta}-ray angular distribution from purely nuclear spin aligned {sup 20}F has been measured to test the G-parity conservation law which is one of the fundamental symmetries in the weak nucleon current. We utilized the hyperfine interaction of {sup 20}F in an MgF{sub 2} single crystal and successfully created the pure alignment from the polarization by means of the spin manipulation technique based on the {beta}-NMR method.

SCALE: A modular code system for performing Standardized Computer Analyses for Licensing Evaluation. Volume 2, Part 3: Functional modules F16--F17; Revision 5

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automated the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.3 of the system.

SCALE: A modular code system for performing Standardized Computer Analyses for Licensing Evaluation. Volume 2, Part 3: Functional modules F16--F17; Revision 5

International Nuclear Information System (INIS)

1997-03-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automated the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.3 of the system

Expression and Functional Pathway Analysis of Nuclear Receptor NR2F2 in Ovarian Cancer

Science.gov (United States)

Hawkins, Shannon M.; Loomans, Holli A.; Wan, Ying-Wooi; Ghosh-Choudhury, Triparna; Coffey, Donna; Xiao, Weimin; Liu, Zhandong; Sangi-Haghpeykar, Haleh

2013-01-01

Context: Recent evidence implicates the orphan nuclear receptor, nuclear receptor subfamily 2, group F, member 2 (NR2F2; chicken ovalbumin upstream promoter-transcription factor II) as both a master regulator of angiogenesis and an oncogene in prostate and other human cancers. Objective: The objective of the study was to determine whether NR2F2 plays a role in ovarian cancer and dissect its potential mechanisms of action. Design, Setting, and Patients: We examined NR2F2 expression in healthy ovary and ovarian cancers using quantitative PCR and immunohistochemistry. NR2F2 expression was targeted in established ovarian cancer cell lines to assess the impact of dysregulated NR2F2 expression in the epithelial compartment of ovarian cancers. Results: Our results indicate that NR2F2 is robustly expressed in the stroma of healthy ovary with little or no expression in epithelia lining the ovarian surface, clefts, or crypts. This pattern of NR2F2 expression was markedly disrupted in ovarian cancers, in which decreased levels of stromal expression and ectopic epithelial expression were frequently observed. Ovarian cancers with the most disrupted patterns of NR2F2 were associated with significantly shorter disease-free interval by Kaplan-Meier analysis. Targeting NR2F2 expression in established ovarian cancer cell lines enhanced apoptosis and increased proliferation. In addition, we found that NR2F2 regulates the expression of NEK2, RAI14, and multiple other genes involved in the cell cycle, suggesting potential pathways by which dysregulated expression of NR2F2 impacts ovarian cancer. Conclusions: These results uncover novel roles for NR2F2 in ovarian cancer and point to a unique scenario in which a single nuclear receptor plays potentially distinct roles in the stromal and epithelial compartments of the same tissue. PMID:23690307

The Management System for Nuclear Installations (Russian Edition)

International Nuclear Information System (INIS)

2014-01-01

This Safety Guide is applicable throughout the lifetime of a nuclear installation, including any subsequent period of institutional control, until there is no significant residual radiation hazard. For a nuclear installation, the lifetime includes site evaluation, design, construction, commissioning, operation and decommissioning. These stages in the lifetime of a nuclear installation may overlap. This Safety Guide may be applied to nuclear installations in the following ways: (a)To support the development, implementation, assessment and improvement of the management system of those organizations responsible for research, site evaluation, design, construction, commissioning, operation and decommissioning of a nuclear installation; (b)As an aid in the assessment by the regulatory body of the adequacy of the management system of a nuclear installation; (c)To assist an organization in specifying to a supplier, via contractual documentation, any specific element that should be included within the supplier's management system for the supply of products. This Safety Guide follows the structure of the Safety Requirements publication on The Management System for Facilities and Activities, whereby: (a)Section 2 provides recommendations on implementing the management system, including recommendations relating to safety culture, grading and documentation. (b)Section 3 provides recommendations on the responsibilities of senior management for the development and implementation of an effective management system. (c)Section 4 provides recommendations on resource management, including guidance on human resources, infrastructure and the working environment. (d)Section 5 provides recommendations on how the processes of the installation can be specified and developed, including recommendations on some generic processes of the management system. (e)Section 6 provides recommendations on the measurement, assessment and improvement of the management system of a nuclear installation. (f

The Management System for Nuclear Installations Safety Guide

International Nuclear Information System (INIS)

2009-01-01

This Safety Guide is applicable throughout the lifetime of a nuclear installation, including any subsequent period of institutional control, until there is no significant residual radiation hazard. For a nuclear installation, the lifetime includes site evaluation, design, construction, commissioning, operation and decommissioning. These stages in the lifetime of a nuclear installation may overlap. This Safety Guide may be applied to nuclear installations in the following ways: (a)To support the development, implementation, assessment and improvement of the management system of those organizations responsible for research, site evaluation, design, construction, commissioning, operation and decommissioning of a nuclear installation; (b)As an aid in the assessment by the regulatory body of the adequacy of the management system of a nuclear installation; (c)To assist an organization in specifying to a supplier, via contractual documentation, any specific element that should be included within the supplier's management system for the supply of products. This Safety Guide follows the structure of the Safety Requirements publication on The Management System for Facilities and Activities, whereby: (a)Section 2 provides recommendations on implementing the management system, including recommendations relating to safety culture, grading and documentation. (b)Section 3 provides recommendations on the responsibilities of senior management for the development and implementation of an effective management system. (c)Section 4 provides recommendations on resource management, including guidance on human resources, infrastructure and the working environment. (d)Section 5 provides recommendations on how the processes of the installation can be specified and developed, including recommendations on some generic processes of the management system. (e)Section 6 provides recommendations on the measurement, assessment and improvement of the management system of a nuclear installation. (f

19F-nuclear magnetic resonance spectroscopy as a tool to ...

African Journals Online (AJOL)

19F-nuclear magnetic resonance spectroscopy as a tool to investigate host-guest complexation of some antidepressant drugs with natural and modified cyclodextrins. Leila Shafiee Dastjerdi1* and Mojtaba Shamsipur2. 1Faculty of Science, Roudehen Branch, Islamic Azad University, Tehran, 2Department of Chemistry, ...

Mapping of carbonic anhydrase and estrone sulphatase in rat brain using 16-α-[18F]fluoroestradiol-3,17-β-disulphamate ([18F]FESDS)

International Nuclear Information System (INIS)

Rodig, H.; Brust, P.; Bergmann, R.; Roemer, J.; Fuechtner, F.; Steinbach, J.; Kasch, H.

2002-01-01

16α-[ 18 F]Fluoroestradiol-3,17β-disulphamate ([ 18 F]FESDS) was recently found to display affinities to carbonic anhydrase (CA) and estrone sulphatase (ES), enzymes which are expressed in the CNS and probably play a regulatory role in various brain diseases. In this study the radioligand was used to provide quantitative data on the regional distribution of these enzymes in the rat brain. (orig.)

Quasi-free knockout reactions with the proton-dripline nucleus {sup 17}Ne

Energy Technology Data Exchange (ETDEWEB)

Wamers, Felix; Aumann, Thomas [Institut fuer Kernphysik, TU, Darmstadt (Germany); Heil, Michael [Kernreaktionen und Nukleare Astrophysik, GSI, Darmstadt (Germany); Marganiec, Justyna [ExtreMe Matter Institute EMMI, GSI, Darmstadt (Germany); Plag, Ralf [Kernreaktionen und Nukleare Astrophysik, GSI, Darmstadt (Germany); Goethe Universitaet, Frankfurt a.M. (Germany); Collaboration: R3B-Collaboration

2011-07-01

{sup 17}Ne is a proton-dripline nucleus that has raised special interest in nuclear-structure physics in recent years. As a ({sup 15}O+2p) Borromean 3-body system, it is often considered to be a 2-proton-halo nucleus, yet lacking concluding experimental evidence about its structure. We have studied breakup reactions of 500 AMeV {sup 17}Ne secondary beams using the R{sup 3}B-LAND setup at GSI. One focus was on the quasi-free one-proton knockout in a proton-rich paraffin (CH{sub 2}) target in inverse kinematics, i.e., {sup 17}Ne(p,2p){sup 16}F{yields}{sup 15}O+p, in comparison to the one-proton knockout with a carbon target. Recoil protons have been detected with Si-Strip detectors and the surrounding 4{pi} NaI spectrometer ''Crystal Ball'', thus providing a clean signature for quasi-free knockout. First results on two-proton removal cross sections with CH{sub 2} and C targets will be presented, as well as transverse momentum distributions of the {sup 15}O core in {sup 17}Ne. Projectile-like forward protons after one-proton knockout from {sup 17}Ne have been measured in coincidence with the {sup 15}O residual core, leading to the relative-energy spectrum of the unbound {sup 16}F. Possible interpretations and implications regarding the structure of {sup 17}Ne are discussed.

17 CFR 249.250 - Form F-X, for appointment of agent for service of process by issuers registering securities on...

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Form F-X, for appointment of agent for service of process by issuers registering securities on Form F-8, F-9, F-10 or F-80 (§ 239.38... F-X, for appointment of agent for service of process by issuers registering securities on Form F-8...

Low Power, Room Temperature Systems for the Detection and Identification of Radionuclides from Atmospheric Nuclear Test

Science.gov (United States)

2013-07-01

DTRA-TR-13-48 Low Power, Room Temperature Systems for the Detection and Identification of Radionuclides from Atmospheric Nuclear Test Approved for...01-C-0071 Radionuclides from Atmospheric Nuclear Tests 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR(S) 5d. PROJECT NUMBER Muren Chu...I IIlIl4eI ilf "tt""f;lk~ l).t::l’e.do)- mllin:: in an n-t~’J𔃻f mlllril.: II!’ ,-kll ~".r’I::!, ..... ·hkh j,-, .:auI,,·d br thP . la-ek f.r ·;IIff

Molecular composition of vapor in the NaF-ZrF4 system

International Nuclear Information System (INIS)

Korenev, Yu.M.; Sidorov, L.N.; Rykov, A.N.; Novoselova, A.V.

1980-01-01

The NaF-ZrF 4 system is studied. It is established that Na 2 ZrF 6 , NaZrF 5 , (NaZrF 5 ) 2 , NaZr 2 F 9 complex molecules are present in the saturated vapor alongside with pure components. Partial pressures of all vapor components are determined. The values of partial pressure and evaporation heat have been used to calculate the vapor composition above the system; T-x and P-T projections of the phase diagram of the NaF-ZrF 4 system are plotted

Activity standardisation of 18F and ionisation chamber calibration for nuclear medicine

International Nuclear Information System (INIS)

Schrader, H.; Klein, R.; Kossert, K.

2007-01-01

Primary activity standardisations were performed on solutions of 18 F using 4πβ-γ coincidence counting and liquid scintillation counting (LSC) according to the CIEMAT/NIST method. A β + -emission probability of 96.86% was used for both methods. The various standardised 18 F solutions were measured in ionisation chambers of the Physikalisch-Technische Bundesanstalt (PTB) and compared by determining radionuclide calibration factors. Already in 2001 an 18 F solution had been standardised at the PTB and compared with the results of nine national metrology institutes (NMIs), using the ISOCAL IV secondary radionuclide calibrators of the National Physical Laboratory (NPL) as transfer instruments and a 68 Ge check source solution. These results were linked to the International Reference System (SIR) at the Bureau International des Poids et Mesures (BIPM) by aliquots of solutions sent by the Laboratoire National Henri Becquerel (BNM-LNHB) and the NPL. Further on, in 2005, PTB sent an aliquot of an 18 F solution to the SIR for ionisation chamber measurements. A value of the equivalent activity was determined and included in the key comparison database (KCDB). The recent PTB value of the equivalent activity of the SIR is in good agreement with the key comparison reference value determined from five NMIs. These results confirm that the standardisation of 18 F solutions can be achieved with the accuracy required for use in nuclear medicine and, in particular, for applications in positron emission tomography (PET)

Chilean experience in production of 18F-FDG from 18F in a reactor

International Nuclear Information System (INIS)

Chandia, M.; Godoy, N.; Errazu, X.; Hernandez; Figols, M.; Firnau, G.; Tronsoco, F.

2000-01-01

18 F-FDG (fluorine-deoxy-D-glucose) is an important and useful radiopharmaceutical for imaging and study of myocardial viability. Usually cyclotron-produced 18 F is used to label 18 F-FDG. The availability of a 5 MW Nuclear Reactor in Chile and the absence of a quality cyclotron to produce 18 F required that we developed a method in order to obtain suitable 18 F to label 18 F-FDG using the facilities we have at the Nuclear Center of La Reina, Chilean Nuclear Energy Commission. The nuclear reactions involved are: 6 Li(n,aα) 3 H and 16 O( 3 H,n) 18 F. Enriched Li 2 CO 3 ( 6 Li = 95 %) was irradiated in a 5 MW swimming pool type nuclear reactor with a neutron flux of 5. 7 x 10 13 n cm -2 s -1 for 4 hours. The irradiated Li 2 CO 3 was dissolved in H 2 SO 4 (1:1) and distilled as trimethylsilyl( 18 F)fluoride ( 18 F-TMS). The labelling of the sugar was carried out using the method described by Hamacker. The 18 F-TMS was trapped in a solution of acetonitrile, water, potassium carbonate, and kriptofix and hydrolysed to form 18 F fluoride. The nucleophilic complex reacts with 1,3,4,6, tetra-O-acetyl- 2-O-trifluoromethanesulfonyl-bβ-D-mannopyranose. The acetylated carbohydrate by acid hydrolysis produces 18 F-FDG. The final product was purified using an ion retarding resin (AG11-A8) and a system two Sep Pak Plus: Alumina and C-18 cartridge and sterilised by Millipore 0.22 μm filter. The 18 F-FDG was obtained in an apyrogenic and sterile solution. The 18 F radionuclide purity was higher than 99.9% and the radiochemical purity ofthe 18 F-FDG obtained was over than 99%. Residual 3 H content was as low as 20 (Bq 3 H/MBq 18 F-FDG.). The yield of the process 18 F-FDG was 13.2 %. (authors)

The kin17 Protein in Murine Melanoma Cells

Directory of Open Access Journals (Sweden)

Anelise C. Ramos

2015-11-01

Full Text Available kin17 has been described as a protein involved in the processes of DNA replication initiation, DNA recombination, and DNA repair. kin17 has been studied as a potential molecular marker of breast cancer. This work reports the detection and localization of this protein in the murine melanoma cell line B16F10-Nex2 and in two derived subclones with different metastatic potential, B16-8HR and B16-10CR. Nuclear and chromatin-associated protein fractions were analyzed, and kin17 was detected in all fractions, with an elevated concentration observed in the chromatin-associated fraction of the clone with low metastatic potential, suggesting that the kin17 expression level could be a marker of melanoma.

Anomalous longitudinal relaxation of nuclear spins in CaF{sub 2}

Energy Technology Data Exchange (ETDEWEB)

Kropf, Chahan M. [Institute of Physics, University of Freiburg, Hermann-Herder-Str. 3, D-79104, Freiburg (Germany); Kohlrautz, Jonas; Haase, Juergen [University of Leipzig, Faculty of Physics and Earth Sciences, Linnestr. 5, 04103, Leipzig (Germany); Fine, Boris V. [Skolkovo Institute of Science and Technology, 100 Novaya Str., Skolkovo, Moscow Region, 143025 (Russian Federation); Institute for Theoretical Physics, University of Heidelberg, Philosophenweg 12, 69120, Heidelberg (Germany)

2017-06-15

We consider the effect of non-secular resonances for interacting nuclear spins in solids which were predicted theoretically to exist in the presence of strong static and strong radio-frequency magnetic fields. These resonances imply corrections to the standard secular approximation for the nuclear spin-spin interaction in solids, which, in turn, should lead to an anomalous longitudinal relaxation in nuclear magnetic resonance experiments. In this article, we investigate the feasibility of the experimental observation of this anomalous longitudinal relaxation in calcium fluoride (CaF{sub 2}) and conclude that such an observation is realistic. (copyright 2016 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

Exotic behavior of elastic scattering differential cross-sections of weakly bound nucleus 17F at small angles

International Nuclear Information System (INIS)

Han Jianlong; Hu Zhengguo; Zhang Xueyin; Yuan Xiaohua; Xu Huagen; Qi Huirong; Wang Yue; Jia Fei; Wu Lijie; Ding Xianli; Gao Qi; Gao Hui; Bai Zhen

2006-01-01

The differential cross-sections for elastic scattering of 17 F and 17 O on 208 Pb have been measured at Radioactive Ion Beam Line at Lanzhou (RIBLL). The variation of the logarithms of differential cross-sections with the square of scattering angles shows clearly that there exists a turning point in the range of small scattering angles (6 degree-20 degree) for 17 F having exotic structure, while no turning point was observed in the 17 O elastic scattering. The experimental results have been compared with previous data. Systematical analysis on the available data seems to conclude that there is an exotic behavior of elastic scattering differential cross-sections of weakly bound nuclei with halo or skin structure as compared with that of the ordinary nuclei near stable line. Therefore the fact that the turning point of the logarithms of differential cross-sections appears at small angle for weakly bound nuclei could be used as a new probe to investigate the halo and skin phenomenon. (authors)

The lactoferricin B-derived peptide, LfB17-34, induces melanogenesis in B16F10 cells.

Science.gov (United States)

Huang, Hsiu-Chin; Lin, Hsuan; Huang, Min-Chuan

2017-03-01

Lactoferricin B (LfcinB), a peptide of bovine lactoferrin (LfB), exhibits multiple biological functions, including antimicrobial, antiviral, antioxidant and immunomodulatory activities. However, the role of LfcinB-related peptides in melanogenesis remains unclear. In this study, a set of five LfcinB-related peptides was examined. We found that LfB17‑34, an 18-mer LfcinB-derived peptide, increased melanogenesis in B16F10 melanoma cells without significantly affecting cell viability. LfB17‑34 increased in vitro tyrosinase activity and melanin content in a dose-dependent manner. The results of RT-qPCR and western blot analyses showed that LfB17‑34 increased the mRNA and protein expression of tyrosinase and tyrosinase-related protein 1 (Trp1). Moreover, LfB17‑34 inhibited the phosphorylation of MAPK/Erk, but not p38 and Akt, and constitutively active MEK was able to reverse the LfB17-34-enhanced pigmentation, melanin content, and tyrosinase activity, suggesting a role of Erk signaling in the process of LfB17‑34-mediated pigmentation. Taken together, these results suggest that LfB17‑34 induces melanogenesis in B16F10 cells primarily through increased tyrosinase expression and activity and that LfB17‑34 could be further developed for the treatment of hypopigmentation disorders.

17 CFR 269.5 - Form F-X, for appointment of agent for service of process by issuers registering securities on...

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Form F-X, for appointment of agent for service of process by issuers registering securities on Form F-8, F-9, F-10 or F-80 (§§ 239... INDENTURE ACT OF 1939 § 269.5 Form F-X, for appointment of agent for service of process by issuers...

A novel mechanism of E2F1 regulation via nucleocytoplasmic shuttling: determinants of nuclear import and export.

Science.gov (United States)

Ivanova, Iordanka A; Vespa, Alisa; Dagnino, Lina

2007-09-01

E2F1 is a transcription factor central for cell survival, proliferation, and repair following genomic insult. Depending on the cell type and conditions, E2F1 can induce apoptosis in transformed cells, behaving as a tumour suppressor, or impart growth advantages favouring tumour formation. The pleiotropic functions of E2F1 are a likely consequence of its ability to transcriptionally control a wide variety of target genes, and require tight regulation of its activity at multiple levels. Although sequestration of proteins to particular cellular compartments is a well-established regulatory mechanism, virtually nothing is known about its contribution to modulation of E2F1 target gene expression. We have examined the subcellular trafficking of E2F1 and, contrary to the widely held notion that this factor is constitutively nuclear, we now demonstrate that it is subjected to continuous nucleocytoplasmic shuttling. We have also defined two nuclear localization domains and a nuclear export region, which mediates CRM1-dependent transit out of the nucleus. The predominant subcellular location of E2F1 is likely determined by the balance between the activity of nuclear import and export domains, and can be modulated by differentiation stimuli in epidermal cells. Thus, we have identified a hitherto unrecognized mechanism to control E2F1 function through modulation of its subcellular localization.

IL-17 Genetic and Immunophenotypic Evaluation in Chronic Graft-versus-Host Disease

Directory of Open Access Journals (Sweden)

Renata Gonçalves Resende

2014-01-01

Full Text Available Although interleukin-17 (IL-17 is a recently discovered cytokine associated with several autoimmune diseases, its role in the pathogenesis of chronic graft-versus-host disease (cGVHD was not established yet. The objective of this study was to investigate the association of IL17A and IL17F genes polymorphisms and IL-17A and IL-17F levels with cGVHD. IL-17A expression was also investigated in CD4+ T cells of patients with systemic cGVHD. For Part I of the study, fifty-eight allo-HSCT recipients and donors were prospectively studied. Blood samples were obtained to determine IL17A and IL17F genes polymorphisms. Cytokines levels in blood and saliva were assessed by ELISA at days +35 and +100 after HSCT. In Part II, for the immunophenotypic evaluation, eight patients with systemic cGVHD were selected and the expression of IL-17A was evaluated. We found association between recipient AA genotype with systemic cGVHD. No association was observed between IL-17A levels and cGVHD. Lower IL-17A levels in the blood were associated with AA genotype. In flow cytometry analysis, decreased expression of IL-17A was observed in patients with cGVHD after stimulation. In conclusion, IL-17A may have an important role in the development of systemic cGVHD.

A unique nuclear receptor direct repeat 17 (DR17) is present within the upstream region of Schistosoma mansoni female-specific p14 gene

International Nuclear Information System (INIS)

Fantappie, Marcelo Rosado; Furtado, Daniel Rodrigues; Rumjanek, Franklin David; LoVerde, Philip T.

2008-01-01

The eggs produced by sexually mature female Schistosma mansoni are responsible for the pathogenesis of the disease. The eggshell precursor gene p14 is expressed only in the vitelline cells of sexually mature female worms in response to a yet unidentified male stimulus. Herein, we report the identification of a novel nuclear receptor response element in the upstream region of the p14 gene. This element contains the canonical hexameric DNA core motif, 5'-PuGGTCA, composed of an atypically spaced direct repeat (DR17). Schistosome nuclear receptors SmRXR1 and SmNR1 specifically bound to the p14-DR17 element as a heterodimer. SmRXR1, but not SmNR1, bound to the motif as a monomer. Introduction of mutations in the TCA core sequence completely abolished the binding by SmRXR1/SmNR1 heterodimer. This finding supports our hypothesis that the expression of Schistosoma mansonip14 gene is regulated through the nuclear receptor signaling pathway

Total system for manufacture of nuclear vessels by computer: VECTRON

International Nuclear Information System (INIS)

Inagawa, Jin; Ueno, Osamu; Hanai, Yoshiharu; Ohkawa, Isao; Washizu, Hideyuki

1980-01-01

VECTRON (Vessel Engineering by Computer Tool and Rapid Operating for the N/C System) is a CAM (Computer Aided Manufacturing) system that has been developed to produce high quality and highly accurate vessels for nuclear power plants and other industrial plants. Outputs of this system are design drawings, manufacturing information and magnetic tapes of the N/C marking machine for vessel shell plates including their attachments. And it can also output information at each stage of designing, marking, cutting, forming and assembling by treating the vessels in three dimensions and by using data filing systems and plotting program for general use. The data filing systems consist of functional and manufacturing data of each part of vessels. This system not only realizes a change from manual work to computer work, but also leads us to improve production engineering and production jigs for safety and high quality. At present, VECTRON is being applied to the manufacture of the shell plates of primary containment vessels in the Kashiwazaki-Kariwa Nuclear Power Station Unit 1 (K-1) and the Fukushima Daini Nuclear Power Station Unit 3 (2F-3), to realize increased productivity. (author)

MicroRNA-17-92 Regulates the Transcription Factor E2F3b during Myogenesis In Vitro and In Vivo

Directory of Open Access Journals (Sweden)

Zhixiong Tang

2017-03-01

Full Text Available Myogenic differentiation, which occurs during muscle development, is a highly ordered process that can be regulated by E2F transcription factors. Available data show that E2F3b, but not E2F3a, is upregulated and required for myogenic differentiation. However, the regulation of E2F3b expression in myogenic differentiation is not well understood. To investigate whether E2Fb expression is controlled by miRNAs, we used bioinformatics to combine the database of microRNAs downregulated during myogenesis and those predicted to target E2F3. This identified miR-17 and miR-20a as miRNAs potentially involved in E2F3 regulation. We found that miR-17-92 controls the expression of E2F3b in C2C12 cells during myogenic differentiation. Moreover, we confirmed that miR-20a regulates the expression of E2F3b proteins in vivo using a muscle regeneration model.

Seismic effects on technological equipment and systems of nuclear power plants

International Nuclear Information System (INIS)

Masopust, R.; Pecinka, L.; Podrouzek, J.

1983-01-01

A survey is given of problems related to the construction of nuclear power plants with regard to seismic resistance. Sei--smic resistance of technological equipment is evaluated by experimental trials, calculation or the combination of both. Existing and future standards are given for the given field. The Czechoslovak situation is discussed as related to the construction of the Mochovce nuclear power plant. Procedures for testing seismic resistance, types of tests and methods of simulating seismic excitation are described. Antiseismic measures together with structural elements for limiting the seismic effects on technological equipment and nuclear power plant systems are summed up on the basis of foreign experience. (E.F.)

A Mock UF6 Feed and Withdrawal System for Testing Safeguards Monitoring Systems and Strategies Intended for Nuclear Fuel Enrichment and Processing Plants

International Nuclear Information System (INIS)

Krichinsky, Alan M.; Bates, Bruce E.; Chesser, Joel B.; Koo, Sinsze; Whitaker, J. Michael

2009-01-01

This report describes an engineering-scale, mock UF6 feed and withdrawal (F and W) system, its operation, and its intended uses. This system has been assembled to provide a test bed for evaluating and demonstrating new methodologies that can be used in remote, unattended, continuous monitoring of nuclear material process operations. These measures are being investigated to provide independent inspectors improved assurance that operations are being conducted within declared parameters, and to increase the overall effectiveness of safeguarding nuclear material. Testing applicable technologies on a mock F and W system, which uses water as a surrogate for UF6, enables thorough and cost-effective investigation of hardware, software, and operational strategies before their direct installation in an industrial nuclear material processing environment. Electronic scales used for continuous load-cell monitoring also are described as part of the basic mock F and W system description. Continuous monitoring components on the mock F and W system are linked to a data aggregation computer by a local network, which also is depicted. Data collection and storage systems are described only briefly in this report. The mock UF 6 F and W system is economical to operate. It uses a simple process involving only a surge tank between feed tanks and product and withdrawal (or waste) tanks. The system uses water as the transfer fluid, thereby avoiding the use of hazardous UF 6 . The system is not tethered to an operating industrial process involving nuclear materials, thereby allowing scenarios (e.g., material diversion) that cannot be conducted otherwise. These features facilitate conducting experiments that yield meaningful results with a minimum of expenditure and quick turnaround time. Technologies demonstrated on the engineering-scale system lead to field trials (described briefly in this report) for determining implementation issues and performance of the monitoring technologies under

Cycle for innovative nuclear Gen 4. systems=

International Nuclear Information System (INIS)

2004-01-01

In the framework of the development of nuclear systems of the 4. generation, the preliminary and schematic reprocessing goals are a cleaning of fission products without a priori separation of the different actinides. The objective of the workshop is to exchange information about the potential efficiency of innovative fuel processing treatments in order to evaluate the impact of impurities on the design of the fuel during its re-fabrication and re-introduction inside the reactor, and on the materials and systems. This document gathers the slides of the 18 presentations given at this workshop: 1 - from the PWR fuel to the closed cycle fast spectrum concepts of generation 4 systems (P. Anzieu, F. Carre, Ph. Brossard, M. Delpech); 2 - the double strata scenarios: objectives and characteristics (S. David and F. Varaine); 3 - why a molten salts thorium file (D. Heuer); 4 - the common 'molten salts' research program of the CNRS (D. Heuer, S. Sanchez); 5 - the hydro-metallurgical reprocessing, the knowledge gained and the statuses of the 5. PCRD, synthesis of the OECD works (C. Madic); 6 - pyro-chemistry: Pyropep status (H. Boussier); 7 - technological bolts identified during the Most project of the 5. PCRD (C. Renault, Ch. Le Brun, M. Delpech and C. Garzenne); 8 - the molten salt reactor concept and its reprocessing options, expected efficiencies (L. Mathieu); 9 - methodology of evaluation of pyro-chemical fuel reprocessing schemes (H. Boussier); 10 - molten salt reactor, design-aided tools for the reactor and the reprocessing plant (O. Gastaldi, E. Walle, O. Koberl, D. Lecarpentier); 11 - status of CEA's prospective studies for the front-end of the fuel reprocessing process/dry ways (S. Bourg); 12 - results of activity coefficient measurements in liquid metals (J. Finne, E. Walle, G. Picard, S. Sanchez and O. Conocar); 13 - potentialities of electrolytic separation and liquid-liquid extraction processes (molten salts/molten metal) for the multi-recycling of actinides (J

Emerging nuclear energy systems and nuclear weapon proliferation

International Nuclear Information System (INIS)

Gsponer, A.; Sahin, S.; Jasani, B.

1983-01-01

Generally when considering problems of proliferation of nuclear weapons, discussions are focused on horizontal proliferation. However, the emerging nuclear energy systems currently have an impact mainly on vertical proliferation. The paper indicates that technologies connected with emerging nuclear energy systems, such as fusion reactors and accelerators, enhance the knowledge of thermonuclear weapon physics and will enable production of military useful nuclear materials (including some rare elements). At present such technologies are enhancing the arsenal of the nuclear weapon states. But one should not forget the future implications for horizontal proliferation of nuclear weapons as some of the techniques will in the near future be within the technological and economic capabilities of non-nuclear weapon states. Some of these systems are not under any international control. (orig.) [de

Reuse of nuclear byproducts, NaF and HF in metal glass industries

Energy Technology Data Exchange (ETDEWEB)

Park, J.W.; Lee, H.W. [Korea Power Engineering Co., Inc., Kyunggi-do (Korea, Republic of); Yoo, S.H.; Moon, H.S.; Cho, N.C. [Korea Nuclear Fuel Co., Ltd., Daejon (Korea, Republic of)

1997-02-01

A study has been performed to evaluate the radiological safety and feasibility associated with reuse of NaF(Sodium Fluoride) and HF(Hydrofluoric Acid) which are generated as byproducts from the nuclear fuel fabrication process. The investigation of oversea`s experience reveals that the byproduct materials are most often used in the metal and glass industries. For the radiological safety evaluation, the uranium radioactivities in the byproduct materials were examined and shown to be less than radioactivities in natural materials. The radiation doses to plant personnel and the general public were assessed to be very small and could be ignored. The Korea nuclear regulatory body permits the reuse of NaF in the metal industry on the basis of associated radioactivity being {open_quote}below regulatory concern{close_quote}. HF is now under review for reuse acceptability in the steel and glass industries.

Interaction of Prevotella intermedia strain 17 leucine-rich repeat domain protein AdpF with eukaryotic cells promotes bacterial internalization.

Science.gov (United States)

Sengupta, Dipanwita; Kang, Dae-Joong; Anaya-Bergman, Cecilia; Wyant, Tiana; Ghosh, Arnab K; Miyazaki, Hiroshi; Lewis, Janina P

2014-06-01

Prevotella intermedia is an oral bacterium implicated in a variety of oral diseases. Although internalization of this bacterium by nonphagocytic host cells is well established, the molecular players mediating the process are not well known. Here, the properties of a leucine-rich repeat (LRR) domain protein, designated AdpF, are described. This protein contains a leucine-rich region composed of 663 amino acid residues, and molecular modeling shows that it folds into a classical curved solenoid structure. The cell surface localization of recombinant AdpF (rAdpF) was confirmed by electron and confocal microscopy analyses. The recombinant form of this protein bound fibronectin in a dose-dependent manner. Furthermore, the protein was internalized by host cells, with the majority of the process accomplished within 30 min. The internalization of rAdpF was inhibited by nystatin, cytochalasin, latrunculin, nocodazole, and wortmannin, indicating that microtubules, microfilaments, and signal transduction are required for the invasion. It is noteworthy that preincubation of eukaryotic cells with AdpF increased P. intermedia 17 internalization by 5- and 10-fold for HeLa and NIH 3T3 fibroblast cell lines, respectively. The addition of the rAdpF protein was also very effective in inducing bacterial internalization into the oral epithelial cell line HN4, as well as into primary cells, including human oral keratinocytes (HOKs) and human umbilical vein endothelial cells (HUVECs). Finally, cells exposed to P. intermedia 17 internalized the bacteria more readily upon reinfection. Taken together, our data demonstrate that rAdpF plays a role in the internalization of P. intermedia 17 by a variety of host cells.

EdF in the core of UK's nuclear industry... before expecting more

International Nuclear Information System (INIS)

Moal, C.

2008-01-01

With the announcement at the end of September 2008 of EdF's friendly takeover bid on British Energy, the French group confirms its will of dominating the European nuclear industry before going back to the assault of the US market. Together, EdF and British Energy (owner of 8 NPPs (9.5 GW) and 1 coal-fired power plant (2 GW)) will make a turnover of 11.9 billion euro with 19800 employees and 85.6 TWh of production. Short paper. (J.S.)

Glass formation in RbF-BeF2-ErF3 system

International Nuclear Information System (INIS)

Reshetnikova, L.P.; Topshinoev, A.P.; Zakharova, B.S.; Sipachev, V.A.

1987-01-01

IR spectroscopic method (200-2000 cm -1 ) is used to study the glass structure in RbF-BeF 2 -ErF 3 system. It is shown that with increase of erbium fluoride content in fluoroberyllate glasses the absorption bands characteristic of (BeF 3 ) n n- groupings, appear in spectra. DTA and X-ray diffraction analysis of the glass annealing products are used to study the glass crystallization process. It is stated that erbium fluoride introduction into the glass results in increase of crystallization stability. The glass structure model is suggested

Tritium recovery as waste sub product in the Fluorine 18 production in a nuclear reactor; Recuperacion de tritio como subproducto de desecho en la produccion de F-18 en un reactor nuclear

Energy Technology Data Exchange (ETDEWEB)

Flores R, H; Palma G, F A; Ramirez, F M

1990-09-15

The tritium is a radioisotope that can be used to carry out basic as applied research. The current researches on the labelling of the organic molecules as well as its application in diagnostic, radiotherapy and hydrology among others confirm the before said. Due to their utility, they have been carried out studies to recover it of radioactive or nuclear waste as well as, to concentrate it of the natural water, the one which due to the nuclear tests in the last decades has gotten rich in tritium. In this work previous studies to recover the tritium coming from the process that was used to produce F-18 following the reaction {sup 6} Li (n, {alpha}) {sup 3} H, {sup 16} O (t, n) {sup 18} F in made up of lithium oxygenated, in the TRIGA Mark III Nuclear Reactor of the Nuclear Center of Mexico. The method consists on purifying by ion exchange the waste solutions where F-18 took place, to distill them and to concentrate them for an electrochemical method. It was already adapts a system reported to concentrate big volumes (approximately 250 ml) in such a way that could be used for small volumes. It was recovered 30% of the considered initial quantity of tritium. A modification to the proposed methodology will allow to recover the waste tritium in a percentage greater to 80%. (Author)

The Management System for Nuclear Installations. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2017-01-01

installation. (f) Appendix I provides some examples of activities that could demonstrate the safety culture attributes. Appendix II provides guidance on implementing the management system requirements for research and development activities. Appendices III-VIII provide guidance on the specific processes to be developed for the various stages in the lifetime of a nuclear installation: site evaluation, design, construction, commissioning, operation and decommissioning. Annex I provides an example from a Member State of a methodology for grading the application of management system requirements

Nuclear safety and radiation protection report of EdF's Tricastin operational hot base nuclear facilities (BCOT) - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Synthesis of NCA 11,17β-dihydroxy-6-methyl-17α-(3-[18F]fluoroprop-1-ynyl)androsta-1,4,6-trien-3-one as a potential glucocorticoid receptor ligand for neuro-PET studies

International Nuclear Information System (INIS)

DaSilva, J.N.; Crouzel, C.

1990-01-01

Glucocorticoids appear to exert physiologic, biochemical and behavioral effects on the central nervous system (1). The presence of glucocorticoid binding sites have been demonstrated in human brain by autoradiographic studies (2). In order to visualize the brain glucocorticoid binding sites by PET, the authors have synthesized n.c.a. 11,17β-dihydroxy-6-methyl-17α-(3-[ 18 F]fluoroprop-1-ynyl)androsta-1,4,6-trien-3-one, a fluorine-18 analog of the selective type II glucocorticoid receptor agonist RU 28362 (3). Biodistribution studies in mature male rats and in vivo distribution of 2 by PET on a baboon are in progress

Convention on nuclear safety. Signature, ratification, acceptance, approval or accession. Status as of 17 March 1997

International Nuclear Information System (INIS)

1997-01-01

The document presents the status as of 17 March 1997 of signature, ratification, acceptance, approval or accession by Member States of the Convention on Nuclear Safety adopted on 17 June 1994 by the Diplomatic Conference convened by the IAEA at its Headquarters between 14-17 June 1994. The Convention entered into force on 24 October 1996. There are 65 signatories and 35 parties. Reservations/declarations deposited upon signature are also included

17 CFR 200.80f - Appendix F-Records control schedule.

Science.gov (United States)

2010-04-01

... ORGANIZATION; CONDUCT AND ETHICS; AND INFORMATION AND REQUESTS Information and Requests § 200.80f Appendix F... in purchasing new issues of securities from underwriters 6 years. 821- Reports by registered small... state or federal laws in the purchase and sale of securities Until date of last reported action plus 10...

Nuclear localization of CPI-17, a protein phosphatase-1 inhibitor protein, affects histone H3 phosphorylation and corresponds to proliferation of cancer and smooth muscle cells

Energy Technology Data Exchange (ETDEWEB)

Eto, Masumi, E-mail: masumi.eto@jefferson.edu [Department of Molecular Physiology and Biophysics, and Kimmel Cancer Center, Thomas Jefferson University, 1020 Locust Street, PA 19107 (United States); Kirkbride, Jason A.; Chugh, Rishika; Karikari, Nana Kofi [Department of Molecular Physiology and Biophysics, and Kimmel Cancer Center, Thomas Jefferson University, 1020 Locust Street, PA 19107 (United States); Kim, Jee In [Department of Molecular Physiology and Biophysics, and Kimmel Cancer Center, Thomas Jefferson University, 1020 Locust Street, PA 19107 (United States); Cardiovascular Research Institute, Kyungpook National University School of Medicine, Daegu 700-422 (Korea, Republic of)

2013-04-26

Highlights: •Non-canonical roles of the myosin phosphatase inhibitor (CPI-17) were studied. •CPI-17 is localized in the nucleus of hyperplastic cancer and smooth muscle cells. •CPI-17 Ser12 phosphorylation may regulate the nuclear import. •CPI-17 regulates histone H3 phosphorylation and cell proliferation. •The nuclear CPI-17-PP1 axis plays a proliferative role in cells. -- Abstract: CPI-17 (C-kinase-activated protein phosphatase-1 (PP1) inhibitor, 17 kDa) is a cytoplasmic protein predominantly expressed in mature smooth muscle (SM) that regulates the myosin-associated PP1 holoenzyme (MLCP). Here, we show CPI-17 expression in proliferating cells, such as pancreatic cancer and hyperplastic SM cells. Immunofluorescence showed that CPI-17 was concentrated in nuclei of human pancreatic cancer (Panc1) cells. Nuclear accumulation of CPI-17 was also detected in the proliferating vascular SM cell culture and cells at neointima of rat vascular injury model. The N-terminal 21-residue tail domain of CPI-17 was necessary for the nuclear localization. Phospho-mimetic Asp-substitution of CPI-17 at Ser12 attenuated the nuclear import. CPI-17 phosphorylated at Ser12 was not localized at nuclei, suggesting a suppressive role of Ser12 phosphorylation in the nuclear import. Activated CPI-17 bound to all three isoforms of PP1 catalytic subunit in Panc1 nuclear extracts. CPI-17 knockdown in Panc1 resulted in dephosphorylation of histone H3 at Thr3, Ser10 and Thr11, whereas it had no effects on the phosphorylation of myosin light chain and merlin, the known targets of MLCP. In parallel, CPI-17 knockdown suppressed Panc1 proliferation. We propose that CPI-17 accumulated in the nucleus through the N-terminal tail targets multiple PP1 signaling pathways regulating cell proliferation.

Azeotrope in LiF-HfF4 system

International Nuclear Information System (INIS)

Sorokin, I.D.; Korenev, Yu.M.; Sidorov, L.N.

1975-01-01

The gaseous phase of the system LiF-HfF 4 is investigated by means of isothermal evaporation. Using experimental data, p-X diagrams are constructed for 1125, 1075, 1025, 975 and 925 K. It is shown that the azeotrope with minimum total pressure observed at 1125 K degenerates upon lowering of the temperature and entry into the heterogeneous region. At 975 K the azeotrope corresponds to the point of inflexion from the horizontal tangent on the total pressure curve. At lower temperatures azeotropic distillation is absent from the system. (author)

Identification and fine mapping of nuclear and nucleolar localization signals within the human ribosomal protein S17.

Directory of Open Access Journals (Sweden)

Scott P Kenney

Full Text Available Human ribosomal protein S17 (RPS17 is mutated in Diamond-Blackfan Anemia (DBA, a bone marrow disorder that fails to produce sufficient red blood cells leading to anemia. Recently, an RPS17 protein sequence was also found to be naturally inserted in the genome of hepatitis E virus (HEV from patients chronically-infected by HEV. The role of RPS17 in HEV replication and pathogenesis remains unknown due to the lack of knowledge about how RPS17 functions at a molecular level. Understanding the biological function of RPS17 is critical for elucidating its role in virus infection and DBA disease processes. In this study we probed the subcellular distribution of normal and mutant RPS17 proteins in a human liver cell line (Huh7. RPS17 was primarily detected within the nucleus, and more specifically within the nucleoli. Using a transient expression system in which RPS17 or truncations were expressed as fusions with enhanced yellow fluorescent protein (eYFP, we were able to identify and map, for the first time, two separate nuclear localization signals (NLSs, one to the first 13 amino acids of the amino-terminus of RPS17 and the other within amino acids 30-60. Additionally, we mapped amino acid sequences required for nucleolar accumulation of RPS17 to amino acids 60-70. Amino acids 60-70 possess a di-RG motif that may be necessary for nucleolar retention of RPS17. The results from this study enhance our knowledge of RSP17 and will facilitate future mechanistic studies about the roles of RSP17 in hepatitis E and DBA disease processes.

Nuclear fuel cycle system analysis

International Nuclear Information System (INIS)

Ko, W. I.; Kwon, E. H.; Kim, S. G.; Park, B. H.; Song, K. C.; Song, D. Y.; Lee, H. H.; Chang, H. L.; Jeong, C. J.

2012-04-01

The nuclear fuel cycle system analysis method has been designed and established for an integrated nuclear fuel cycle system assessment by analyzing various methodologies. The economics, PR(Proliferation Resistance) and environmental impact evaluation of the fuel cycle system were performed using improved DB, and finally the best fuel cycle option which is applicable in Korea was derived. In addition, this research is helped to increase the national credibility and transparency for PR with developing and fulfilling PR enhancement program. The detailed contents of the work are as follows: 1)Establish and improve the DB for nuclear fuel cycle system analysis 2)Development of the analysis model for nuclear fuel cycle 3)Preliminary study for nuclear fuel cycle analysis 4)Development of overall evaluation model of nuclear fuel cycle system 5)Overall evaluation of nuclear fuel cycle system 6)Evaluate the PR for nuclear fuel cycle system and derive the enhancement method 7)Derive and fulfill of nuclear transparency enhancement method The optimum fuel cycle option which is economical and applicable to domestic situation was derived in this research. It would be a basis for establishment of the long-term strategy for nuclear fuel cycle. This work contributes for guaranteeing the technical, economical validity of the optimal fuel cycle option. Deriving and fulfillment of the method for enhancing nuclear transparency will also contribute to renewing the ROK-U.S Atomic Energy Agreement in 2014

Nuclear quadrupole interaction measurements of 19F* and 22Na* on Graphite

International Nuclear Information System (INIS)

Djoko-Surono, Th; Martin, Peter W

1996-01-01

Time differential perturbed angular distribution (TDPAD) technique has been used to investigate nuclear quadrupole interactions of 19 F * and 22 Na * in graphite. We concentrated the measurements on pseudo single crystal graphite called Highly Oriented Pyrolytic Graphite for it has an ordered structure in which the c-axes of the microcrystals aligned in a certain direction with the mosaic spread less than 1 o , while the a- and b-axes randomly oriented on a plane perpendicular to the c-axes. Interactions between quadrupole moment of 19 F * and 22 Na * with its surroundings electric field gradient were studied by detecting the γ-rays distribution, W(Θ,t). For 1 9F * we found one static interaction. The corresponding electric field gradient was V zz =3.24(19)x10 22 V/m 2 . In the case of 22 Na * we found no evidence of nuclear quadrupole interaction, however, we were able to conclude that |QV 22 | 19 bV/m 2 . Using theoretical calculation Q=0.06 barn, we find that |V zz | 20 V/m 2 . These results indicate that the value efg depend on two factors, the host crystal and the core electrons. The core electrons contribution to the total efg is considerably large

Thermal analysis and phase diagrams of the LiF BiF{sub 3} e NaF BiF{sub 3} systems; Analise termica e diagramas de fase dos sistemas LiF-BiF{sub 3} e NaF-BiF{sub 3}

Energy Technology Data Exchange (ETDEWEB)

Nakamura, Gerson Hiroshi de Godoy

2013-07-01

Investigations of the binary systems LiF-BiF{sub 3} and NaF-BiF{sub 3} were performed with the objective of clarifying the thermal behavior and phase equilibria of these systems and their intermediary phases, an important requisite for high-quality crystal growth. Several samples in the entire range of compositions (0 to 100 mol% BiF{sub 3}) of both systems were subjected to experiments of differential thermal analysis (DTA) and thermogravimetry (TG), and also of differential scanning calorimetry (DSC). A few specific compositions were selected for X-ray diffraction to supplement the experimental data. Due to the high vulnerability of BiF{sub 3} to oxygen contamination, its volatility and propensity to destroy metal parts upon heating, it was necessary to determine the optimal conditions for thermal analysis before investigating the systems themselves. Phase relations in the system LiF-BiF{sub 3} were completely clarified and a phase diagram was calculated and evaluated via the commercial software Factsage. The diagram itself consists in a simple peritectic system in which the only intermediary compound, LiBiF{sub 4}, decomposes into LiF and a liquid phase. The NaF-BiF{sub 3} system could not be completely elucidated and the phase relations in the NaF poor side (> 50% BiF{sub 3}) are still unknown. In the NaF rich side, however, the possible peritectoid decomposition of the compound NaBiF{sub 4} was identified. In both systems X-ray diffraction yielded crystal structures discrepant with the literature for the intermediary phases, LiBiF{sub 4}, NaBiF{sub 4} and a solid solution of NaF and BiF{sub 3} called {sup I.} The observed structures remain unknown and explanations for the discrepancies were proposed. (author)

Nuclear material control systems for nuclear power plants

International Nuclear Information System (INIS)

1975-06-01

Paragraph 70.51(c) of 10 CFR Part 70 requires each licensee who is authorized to possess at any one time special nuclear material in a quantity exceeding one effective kilogram to establish, maintain, and follow written material control and accounting procedures that are sufficient to enable the licensee to account for the special nuclear material in his possession under license. While other paragraphs and sections of Part 70 provide specific requirements for nuclear material control systems for fuel cycle plants, such detailed requirements are not included for nuclear power reactors. This guide identifies elements acceptable to the NRC staff for a nuclear material control system for nuclear power reactors. (U.S.)

Molecular-nuclear transitions

International Nuclear Information System (INIS)

Belyaev, V.B.; Miller, M.B.

2007-01-01

Full text: The spectra in some light nuclei have one interesting property. For example, in the closed vicinity of some resonance states of such nuclei as 5 He, 8 Be, 18 F, 18 Ne the thresholds exist for two- or three-body decay of those nuclei. Let us consider the lightest of the above nuclei, 5 He. The energy threshold for 5 He > d+t decay is ∼50 keV lower than the energy of 3/2 + state of 5 He nucleus. However, due to a rather large width of this state, ∼70 keV, the nuclear capture of deuterons by tritons in dtm-molecule is highly enhanced in comparison with the process of dd capture in the ddm molecule. The physical reason for the enhancement of the probability of the capture into the resonant state can be associated with a long tail of wave function of the resonant state and, accordingly, with the large value of the overlap integral determining in general the probability of the transition between two systems. Thus, one can expect the enhancement of the molecular-nuclear transitions, and this was indeed observed experimentally for the case of dtm molecule. Now, let us consider some other molecular-nuclear combinations: 18 Ne - H 2 O, 18 F - 17 OH, and 8 Be - 6 LiD molecule. With the high accuracy the energies of the above molecular systems coincide with the energies of the resonant states in the appropriate nuclei. Due to the uncertainty in the experimental nuclear data it is not known at present whether the energies of these thresholds are lower or higher of the corresponding energies of the nuclear resonances. Let us assume that the molecular energy is few keV over the energy of the nuclear resonance. Then, we will deal with a very interesting phenomenon: the molecular-nuclear complex constitutes a two level system, which in some sense is analogous to the two-level atomic system, as in a laser. The crucial difference between this one and the two-level atomic systems consists in a fact that in the molecular-nuclear case no special procedure of pumping up

Nuclear energy: The need for a new framework, 17 April 2008, Berlin, Germany

International Nuclear Information System (INIS)

ElBaradei, M.

2008-01-01

IAEA Director General Dr. Mohamed ElBaradei addresses the critical issue of assurance of supply of nuclear fuel. He indicates that a growing number of countries are looking seriously at introducing or expanding the use of nuclear power as part of their energy mix. This is primarily because of the huge need for additional energy as the world's reserves of fossil fuels are inexorably depleted and concerns about global warming mount. To date, the use of nuclear power has been concentrated mainly in industrialized countries. But of the 35 new reactors currently under construction, 17 are in developing countries. Recent expansion has been primarily in Asia and Eastern Europe. It is vital that the expected increase in the use of nuclear power is managed properly, taking into account all economic, safety, security and non-proliferation requirements. It is possible - and indeed essential - to create a new mechanism that will assure supplies of nuclear fuel and reactors to countries which want them, while strengthening non-proliferation through better controls over the sensitive parts of the nuclear fuel cycle - uranium enrichment and plutonium separation - by way of a multinational approach to the front and back ends of the cycle. So far 12 proposals have been made on different ways of assuring supply of nuclear fuel. The 12 proposals cover a broad spectrum, from establishing an IAEA-controlled last resort reserve of low enriched uranium to providing backup assurance of supply and setting up international uranium enrichment centres. A three-stage process can be envisaged. The first step would be to establish a system for assuring supply of fuel for nuclear power reactors - and, if necessary, supply of the actual reactors. The second step would be to have all new enrichment and reprocessing activities in future put exclusively under multilateral control. And the third step would be to convert all existing enrichment and reprocessing facilities from national to multilateral

Probing nuclear forces beyond the drip-line using the mirror nuclei N-16 and F-16

Czech Academy of Sciences Publication Activity Database

Stefan, I.; de Oliveira Santos, F.; Sorlin, O.; Davinson, T.; Lewitowicz, M.; Dumitru, G.; Angelique, J. C.; Angelique, M.; Berthoumieux, E.; Borcea, C.; Borcea, R.; Buta, A.; Daugas, J. M.; De Grancey, F.; Fadil, M.; Grévy, S.; Kiener, J.; Lefebvre-Schuhl, A.; Lenhardt, M.; Mrázek, Jaromír; Negoita, F.

2014-01-01

Roč. 90, č. 1 (2014), 014307 ISSN 0556-2813 Institutional support: RVO:61389005 Keywords : nuclear reactions * differential cross sections * 15,16F * deduced levels * resonances * spectroscopic factors * R-matrix analysis Subject RIV: BG - Nuclear, Atomic and Molecular Physics , Colliders Impact factor: 3.733, year: 2014

Nuclear facilities of EdF's operational hot base of Tricastin. 2009 annual report

International Nuclear Information System (INIS)

2010-01-01

This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the nuclear facilities of the EdF operational hot base of Tricastin, then, the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities), and finally the procedures of management of radioactive wastes. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

Fission product chemistry in severe nuclear reactor accidents, specialists' meeting at JRC-Ispra, 15-17 January 1990

International Nuclear Information System (INIS)

Nichols, A.L.

1990-05-01

A specialists' meeting was held at JRC-Ispra from 15 to 17 January 1990 to review the current understanding of fission-product chemistry during severe accidents in light water reactors. Discussions focussed on the important chemical phenomena that could occur across the wide range of conditions of a damaged nuclear plant. Recommendations for future chemistry work were made covering the following areas: (a) fuel degradation and fission-product release, (b) transport and attenuation processes in the reactor coolant system, (c) containment chemistry (iodine behaviour and core-concrete interactions). (author)

Measurement of the inelastic branch of the stellar $^{14}$O($\\alpha$, p)$^{17}$F reaction occurring in the explosive burning in Novae and X-ray busters

CERN Document Server

He, J J; Hass, M; Warr, N; Raabe, R; Neyskens, P; Aliotta, M; Robinson, A P; Murphy, A St J; Davinson, T; Buescler, J; Wenander, F; Woods, P J; Jenkins, D G; Clement, E; Kumar, V; van der Walle, J

2010-01-01

The inelastic component of the key astrophysical resonance (1(-), E-x=6.15 MeV) in the O-14(alpha,p)F-17 reaction has been studied by using the resonant scattering of F-17+p. The experiment was done at REX-ISOLDE CERN with the Miniball setup. The thick target method in inverse kinematics was utilized in the present experiment where a 44.2 MeV F-17 beam bombarded a similar to 40 mu m thick (CH2)(n) target. The inelastic scattering protons in coincidence with the de-excited 495 keV gamma rays have been clearly seen and they are from the inelastic branch to the first excited state in F-17 following decay of the 1(-) resonance in Ne-18. Some preliminary results are reported.

Measurement of the inelastic branch of the stellar 14O(α,p)17F reaction occurring in the explosive burning in Novae and X-ray bursters

International Nuclear Information System (INIS)

He, J.J.; Woods, P.J.; Davinson, T.; Aliotta, M.; Buescler, J.; Clement, E.; Delahaye, P.; Hass, M.; Jenkins, D.G.; Kumar, V.; Murphy, A.St.J.; Neyskens, P.; Raabe, R.; Robinson, A.P.; Walle, J. van der; Warr, N.; Wenander, F.

2010-01-01

The inelastic component of the key astrophysical resonance (1 - , E x =6.15 MeV) in the 14 O(α,p) 17 F reaction has been studied by using the resonant scattering of 17 F+p. The experiment was done at REX-ISOLDE CERN with the Miniball setup. The thick target method in inverse kinematics was utilized in the present experiment where a 44.2 MeV 17 F beam bombarded a∼40μm thick (CH 2 ) n target. The inelastic scattering protons in coincidence with the de-excited 495 keV γ rays have been clearly seen and they are from the inelastic branch to the first excited state in 17 F following decay of the 1 - resonance in 18 Ne. Some preliminary results are reported.

Thermal coupling in low fields between the nuclear and electronic spins in Tm2+ doped CaF2

International Nuclear Information System (INIS)

Urbina, Cristian.

1977-01-01

It is shown that in a CaF 2 crystal doped with divalent thulium ions there is in low fields, a thermal coupling between the electron magnetic moments of Tm 2+ and the nuclear moments of 19 F. When these ones have been lowered down to temperature through dynamical high-field polarization and adiabatic demagnetization in succession the resulting polarisation of the formed ones can overstep their original polarization in high field. A trial is given to explain this Zeeman electronic energy cooling through nuclear Zeeman energy with invoking a thermal coupling between both systems through the spin-spin electronic interaction but no theoretical model is developed in view of a quantitative explanation of the dynamics of such a process. The magnetic resonance spectrum of Tm 2 + in low field is also investigated: an important shift and narrowing of the electron resonance line in low field are obtained when 19 F nuclei are very cold. This special spectral characters are explained as due to magnetic interactions between electronic impurities and the neighbouring 19 F nuclei and a theoretical model is developed (based on the local Weiss field approximation) which explains rather well the changes in the spectral shift as a function of the 19 F nucleus temperature. A second theoretical model has also been developed in view of a quantitative explanation of both the narrowing and shift of the spectrum, but its prediction disagree with the experimental results. It is shown that in low fieldsx it is possible to get rid of paramagnetic impurities after they have been reused as reducing agents for 19 F nucleus entropy populating at about 80%, a non magnetic metastable state with these impurities [fr

Lessons Learned and Flight Results from the F15 Intelligent Flight Control System Project

Science.gov (United States)

Bosworth, John

2006-01-01

A viewgraph presentation on the lessons learned and flight results from the F15 Intelligent Flight Control System (IFCS) project is shown. The topics include: 1) F-15 IFCS Project Goals; 2) Motivation; 3) IFCS Approach; 4) NASA F-15 #837 Aircraft Description; 5) Flight Envelope; 6) Limited Authority System; 7) NN Floating Limiter; 8) Flight Experiment; 9) Adaptation Goals; 10) Handling Qualities Performance Metric; 11) Project Phases; 12) Indirect Adaptive Control Architecture; 13) Indirect Adaptive Experience and Lessons Learned; 14) Gen II Direct Adaptive Control Architecture; 15) Current Status; 16) Effect of Canard Multiplier; 17) Simulated Canard Failure Stab Open Loop; 18) Canard Multiplier Effect Closed Loop Freq. Resp.; 19) Simulated Canard Failure Stab Open Loop with Adaptation; 20) Canard Multiplier Effect Closed Loop with Adaptation; 21) Gen 2 NN Wts from Simulation; 22) Direct Adaptive Experience and Lessons Learned; and 23) Conclusions

Measurements of nuclear polarization and nuclear magnetic moment of 170Tm in 170Tm:SrF2 by optical pumping

International Nuclear Information System (INIS)

Shimomura, K.

1988-01-01

Significant nuclear polarization of unstable 170 Tm in Tm 2+ :SrF 2 was for the first time achieved with β-ray radiation detected optical pumping in solids, providing a new powerful method to measure magnetic moments of unstable nuclei. (author)

Alimentary tract absorption (f1 values) for radionuclides in local and regional fallout from nuclear tests.

Science.gov (United States)

Ibrahim, Shawki A; Simon, Steven L; Bouville, André; Melo, Dunstana; Beck, Harold L

2010-08-01

This paper presents gastrointestinal absorption fractions (f1 values) for estimating internal doses from local and regional fallout radionuclides due to nuclear tests. The choice of f1 values are based on specific circumstances of weapons test conditions and a review of reported f1 values for elements in different physical and chemical states. Special attention is given to fallout from nuclear tests conducted at the Marshall Islands. We make a distinction between the f1 values for intakes of radioactive materials immediately after deposition (acute intakes) and intakes that occur in the course of months and years after deposition, following incorporation into terrestrial and aquatic foodstuffs (chronic intakes). Multiple f1 values for different circumstances where persons are exposed to radioactive fallout (e.g., local vs. regional fallout and coral vs. continental tests) are presented when supportive information is available. In some cases, our selected f1 values are similar to those adopted by the International Commission on Radiological Protection (ICRP) (e.g., iodine and most actinides). However, f1 values for cesium and strontium derived from urine bioassay data of the Marshallese population are notably lower than the generic f1 values recommended by ICRP, particularly for acute intakes from local fallout (0.4 and 0.05 for Cs and Sr, respectively). The f1 values presented here form the first complete set of values relevant to realistic dose assessments for exposure to local or regional radioactive fallout.

Implantable nuclear-fueled circulatory support system. V. Acute physiologic analyses

Energy Technology Data Exchange (ETDEWEB)

Huffman, F N; Migliore, J J; Hagen, K G; Daly, B D.T.; Robinson, W J; Ruggles, A E; Norman, J C

1973-01-01

Nuclear-Fueled circulatory assist systems have reached the stage of in vivo evaluation. Physiologic studies of the effects of intracorporeal heat and radiation as well as blood pumps indicate that these factors should not preclude clinical application of nuclear artificial hearts. In the circulatory system under consideration, a fraction of the heat from a 50 watt Plutonium-238 fuel capsule is converted into hydraulic power for driving a left ventricular assist pump via a miniature, electronically controlled steam (tidal regenerator) engine. The engine is pressurized (8-140 PSIA) by the displacement of a single drop of water between the condenser (150/sup 0/F) and the boiler (360/sup 0/F). The electrical power for sensing, logic and displacement is provided by a thermoelectric module interposed between the superheater (900/sup 0/F) and boiler. The pusher plate pump also functions as a blood-cooled heat exchanger and sensor for the control logic. The assist pump is connected between the apex of the left ventricle and the descending thoracic aorta. The power source module is suspended in the left retroperitoneal cavity from the psoas tendon. The blood interface of the pump is flocked with polyester fibers. A stable biologic lining develops in the pump using Dextran as the only anticoagulant. The longest in vivo testing period has been 4/sup 1///sub 2/ days. Plasma hemoglobinshave remained below 10 mg/sup 0///sub 0/. Although rectal temperatures have not increased, elevated respiratory rates have been noted. Reduction of left ventricular pressure and dp/dt have been demonstrated with maintenance of arterial pressure.

Meltability in system of K2TaF7-NaF-NaCl-KCl

International Nuclear Information System (INIS)

Kartsev, V.E.; Kovalev, F.V.; Korshunov, B.G.

1975-01-01

Thermographic and visual-polythermal techniques were used to study the meltability in K 2 TaF 7 -NaF-NaCl-KCl system. The tetrahedron-forming sections NaF-NaCl-K 2 TaF 7 xKCl and NaF-K 2 TaF 7 xKCl-2K 2 TaF 7 xNaCl divide the concentration tetrahedron into three particular tetrahedra: NaF-K 2 TaF 7 xKCl-2K 2 TaF 7 xNaCl-K 2 TaF 7 , NaF-NaCl-K 2 TaF 7 xKCl-2K 2 TaF 7 xaCl, and NaF-NaCl-KCl-K 2 TaF 7 xKCl. Non-variant equilibrium points in all of the particular four-component systems have been determined

Verification and uncertainty evaluation of HELIOS/MASTER nuclear design system

Energy Technology Data Exchange (ETDEWEB)

Song, Jae Seung; Kim, J. C.; Cho, B. O. [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-03-01

A nuclear design system HELIOS/MASTER was established and core follow calculations were performed for Yonggwang Unit 1 cycles 1 through 7 and Yonggwang Unit 3 cycles 1 through 2. The accuracy of HELIOS/MASTER system was evaluated by estimations of uncertainties of reactivity and peaking factors and by comparisons of the maximum differences of isothermal temperature coefficient, inverse boron worth and control rod worth with the CASMO-3/MASTER uncertainties. The reactivity uncertainty was estimated by 362 pcm, and the uncertainties of three-dimensional, axially integrated radial, and planar peaking factors were evaluated by 0.048, 0.034, and 0.044 in relative power unit, respectively. The maximum differences of isothermal temperature coefficient, inverse boron worth and control rod worth were within the CASMO-3/MASTER uncertainties. 17 refs., 17 figs., 10 tabs. (Author)

Annular tidal regenerator engine for nuclear circulatory support systems

International Nuclear Information System (INIS)

Hagen, K.G.; Ruggles, A.E.; Fam, S.S.; Torti, V.A.

1975-01-01

In order to simplify the configuration of the tidal regenerator engine nuclear-powered circulatory support system, thereby drastically reducing its size and improving the intrinsic reliability, the engine has been redesigned. This redesign focuses on allowing power to be extracted at the low temperature end of the engine utilizing a piston-cylinder arrangement wherein all of the necessary heat transfer processes occur in the annular gap between the piston and cylinder. In all other respects the engine retains its basic characteristics as a hybrid between a Stirling engine and a Rankine engine. A significant advantage of the new arrangement is the ability to raise the superheat temperature limit from 650 0 F to over 900 0 F. This has yielded an increase in engine efficiency from 10 percent to 14 percent, and further increases are anticipated by utilizing an expansion and/or a binary version of the engine. The implantable system volume has been reduced by a factor of three and orientation insensitivity with respect to gravity has been demonstrated. Many system components have already demonstrated endurances of several thousand hours

Modification of the Japanese first nuclear ship reactor for a regional energy supply system

International Nuclear Information System (INIS)

Sato, K.; Shimazu, Y.; Narabayashi, T.; Tsuji, M.

2008-01-01

Nuclear Ship Mutsu was developed as the first experimental nuclear ship of Japan. It has several advantages as a prototype for regional energy supply system. Considering the attractive advantages of the Mutsu reactor, we investigated the feasibility of development of a small regional energy system by adopting the Mutsu reactor as a starting model. The system could supply with not only electricity but also heat. Heat could be used for hot-water supply, a heating system of a house, melting snow and so on, especially for those in northern part of Japan. The system should satisfy the requirements for GEN IV systems and the current regulations. From this point of view, the modification of the reactor was initiated by taking into improvements and technology of the state of arts to fulfill the requirements such as (1) Longer core life without refueling, (2) Reactivity adjustment for load change without control rods or soluble boron, (3) Simpler operations for load changes and (4) Ultimate safety with sufficient passive capability. Currently it is assumed to use basic standard 17x17 fuel assembly design for WH type PWRs. Nuclear design calculations are carried out by 'SRAC 2002 ', which has been developed in Japan Atomic Energy Agency. Several problems have not been solved yet, but we confirmed the proposed core has about 10 years life time. So the proposed core has a possibility to be used for a small regional energy system. (authors)

Bone marrow CD11b(+)F4/80(+) dendritic cells ameliorate collagen-induced arthritis through modulating the balance between Treg and Th17.

Science.gov (United States)

Zhang, Lingling; Fu, Jingjing; Sheng, Kangliang; Li, Ying; Song, Shanshan; Li, Peipei; Song, Shasha; Wang, Qingtong; Chen, Jingyu; Yu, Jianhua; Wei, Wei

2015-03-01

Tolerogenic dendritic cells (DCs) are well-known to show an immunosuppressive function. In this study we determine the therapeutic effects and potential mechanisms of transferred bone marrow (BM) CD11b(+)F4/80(+) DCs on collagen-induced arthritis (CIA) in mice. Murine BM CD11b(+)F4/80(+) DCs were generated under the stimulation of GM-CSF and IL-4, and the function of BM CD11b(+) F4/80(+) DCs was identified by measuring the levels of IL-10, TGF-beta and indoleamine 2,3-dioxygenase (IDO). BM CD11b(+)F4/80(+) DCs were transferred to CIA mice by intravenous injections. The histopathology of joint and spleen were evaluated. T lymphocyte proliferation, Treg and Th17 subsets were analyzed. The expressions of Foxp3, Helios and RORγt in T lymphocytes co-cultured with BM CD11b(+)F4/80(+) DCs were measured in vitro. We found that BM CD11b(+)F4/80(+) DCs induced by GM-CSF and IL-4 could express high levels of IL-10, TGF-beta and IDO. BM CD11b(+)F4/80(+) DCs significantly reduced the pathologic scores in joints and spleens, which correlated significantly with the reduced T lymphocyte proliferation and Th17 cell number, and with the increased Tregs number. In vitro, OVA-pulsed BM CD11b(+)F4/80(+) DCs promoted Treg cell expansion, enhanced IL-10 and CTLA-4 protein expression, augmented Foxp3 and Helios mRNA expression, and inhibited RORγt and IL-17 mRNA expression. Taken together, BM CD11b(+)F4/80(+) DCs are able to ameliorate the development and severity of CIA, at least partly by inducing Foxp3(+) Treg cell expansion and suppressing Th17 function. The BM CD11b(+)F4/80(+) DCs might have a promising immunotherapeutic potential for autoimmune arthritis. Copyright © 2015 Elsevier B.V. All rights reserved.

Measurement of the inelastic branch of the $^{14}$O(α,p)$^{17}$F reaction Implications for explosive burning in novae and x-ray bursters

CERN Document Server

He, J J; Davinson, T; Aliotta, M; Büscher, J; Clement, E; Delahaye, P; Hass, M; Jenkins, D G; Kumar, V; Murphy, A St J; Neyskens, P; Raabe, R; Robinson, A P; Voulot, D; van der Walle, J; Warr, N; Wenander, F

2009-01-01

A measurement of the inelastic component of the key astrophysical resonance in the 14O(α,p)17F reaction for burning and breakout from hot carbon-nitrogen-oxygen (CNO) cycles is reported. The inelastic component is found to be comparable to the ground-state branch and will enhance the 14O(α,p)17F reaction rate. The current results for the reaction rate confirm that the 14O(α,p)17F reaction is unlikely to contribute substantially to burning and breakout from the CNO cycles under novae conditions. The reaction can, however, contribute strongly to the breakout from the hot CNO cycles under the more extreme conditions found in x-ray bursters.

Nuclear power life cycle management, managing nuclear knowledge, and nuclear security. Introductory statement to the 5th scientific forum during the 46th session of the IAEA General Conference. Vienna, 17 September 2002

International Nuclear Information System (INIS)

ElBaradei, M.

2002-01-01

The document reproduces the text of the introductory statement made by the Director General of the IAEA at the 5th scientific forum organized during the 46th session of the IAEA General Conference, Vienna, 17 september 2002, on the nuclear power life cycle management, managing nuclear knowledge, and nuclear security. In the area of nuclear power life cycle management two aspects were emphasized: licence extension and facility decommissioning. Nuclear knowledge management includes ensuring the continued availability of the qualified personnel. Nuclear security must be considered for all nuclear applications, in a manner that encompasses all phases of nuclear activity - the use, storage and transport of nuclear and other radioactive material, as well as the design, operation, and decommissioning of nuclear facilities

Determination of tea fluorine concentration with 19F(p, αγ)16O prompt nuclear reaction analysis

International Nuclear Information System (INIS)

Liang Daihua; Shen Guantao; Li Deyi; Wu Junheng

1987-01-01

Experiments of 19 F(p, αγ) 16 O prompt nuclear reaction analyses of tea F contents were performed on a Cockroft-Walton accelerator. The principle and apparatus are described. More than 150 varieties tea samples were examined. Results show that for the same variety of tea samples, the higher the grade of the tea, the higher the F concentration it contains, and for different varieties, the better the tea, the lower the F concentration of the tea

The monomeric orphan nuclear receptor Schistosoma mansoni Ftz-F1 dimerizes specifically and functionally with the schistosome RXR homologue, SmRXR1

International Nuclear Information System (INIS)

Bertin, Benjamin; Caby, Stephanie; Oger, Frederik; Sasorith, Souphatta; Wurtz, Jean-Marie; Pierce, Raymond J.

2005-01-01

In an attempt to understand development and differentiation processes of the parasitic blood fluke Schistosoma mansoni, several members of the nuclear receptor superfamily were cloned, including SmFtz-F1 (S. mansoni Fushi Tarazu-factor 1). The Ftz-F1 nuclear receptor subfamily only contains orphan receptors that bind to their response element as monomers. Whereas SmFtz-F1 displays these basic functional properties, we have identified an original and specific interaction between SmFtz-F1 and the schistosome RXR homologue, SmRXR1. The mammalian two-hybrid assay showed that the D, E, and F domains of SmFtz-F1 were capable of interacting specifically with the E domain of SmRXR1 but not with that of mouse RXRα. Using three-dimensional LBD homology modelling and structure-guided mutagenesis, we were able to demonstrate the essential role of exposed residues located in the dimerization interfaces of both receptors in the maintenance of the interaction. Cotransfection experiments with constructions encoding full-length nuclear receptors show that SmRXR1 potentiates the transcriptional activity of SmFtz-F1 from various promoters. Nevertheless, the lack of identification of a dimeric response element for this SmFtz-F1/SmRXR1 heterodimer seems to indicate a 'tethering' mechanism. Thus, our results suggest for the first time that a member of the Ftz-F1 family could heterodimerize functionally with a homologue of the universal heterodimerization partner of nuclear receptors. This unique property confirms that SmFtz-F1 may be involved in the development and differentiation of schistosome-specific structures

18F in hot atom chemistry and equilibrium chemical kinetics

International Nuclear Information System (INIS)

Root, J.W.; Tomiyoshi, Katsumi; Knickelbein, M.B.

1993-01-01

Superexcited molecules are unusual species that at present can only be investigated using nuclear recoil methods. The thermochemical technique for measuring the excitation energy distributions of superexcited molecules is reviewed and applied to recent studies of CF 3 18 F and C 2 F 5 18 F formed from high energy atomic exchange reactions in CF 4 and C 2 F 6 . The nascent CF 3 18 F and C 2 F 5 18 F range in energy from 1.7 to about 45 eV. The average energies of these products range from 15 to 20 eV. The internal excitation that accompanies these reactions is initially localized near the 18 F bonding site, and the C 2 F 5 18 F decomposition mechanism is non-statistical. Moderated nuclear recoil experiments yield mechanisms and rates for the reactions of thermal 18 F atoms. Under our standard experimental conditions from 3.4 x 10 4 to 3.4 x 10 8 labeled product molecules are available for radioassay. This procedure is free from systematic error and the measurements yield exceptional precision and sensitivity because (1) high energy reactions with the thermally active reagents are suppressed. (2) the host environment is rigorously controlled, and (3) the molecular products from many single atom reactions are directly counted. The limitations of this technique are described and results are presented for the reactions of thermal 18 F atoms with CH 4 and C 2 H 4 . (J.P.N.)

Photoionization study of the F2+ ion via the screening constant by unit nuclear charge method

Science.gov (United States)

Dieng, M.; Tine, M.; Sow, M.; Diop, B.; Guèye, M.; Faye, M.; Sakho, I.; Biaye, M.; Wagué, A.

2014-03-01

In this paper, we have tabulated energy resonances of the 2s22p2 (1D)nd (2L), 2s22p2 (1S)nd (2L) and 2s22p3 (3D)np Rydberg series originating from the 2s22p3(2Po) and from the 2s22p3 (2Do) metastable states of F2+. In addition, energy resonances of the 2s2p3(5So)np (4P) Rydberg series originating from the 2s22p3 (4So) ground-state of F2+are also reported. Calculations are performed using the Screening constant by unit nuclear charge (SCUNC) method. Analysis of the present data is achieved by calculating the quantum defects and the effective nuclear charges for each series. The present results agree very well with the Advanced Light Source experiments on F2+ (Aguilar et al., 2005). Upto n=30, the present quantum defects are almost constant and the effective charge decreases regularly toward the electric charge of the F3+ core ion along each series.

Pelletizing of NaF granules as adsorbent for fluorides of nuclear fuel materials, (1)

International Nuclear Information System (INIS)

Kimura, Syojiro; Tsutsui, Tenson; Kanagawa, Akira.

1976-01-01

The pelletizing of NaF granules on laboratory scale used for recovery and purification of fluorides of nuclear fuel materials are investigated, particularity experimental studies on how to pelletize, fluidity of granules and flow rate of the granules in mortar of tablet machine are carried out. As result, added quantity of H 2 O as binder at granulation process of spherical NaF granule influence to yield of NaF granules. The proper quantity of H 2 O to NaF powder is about 18--19%. Friction coefficient of unfixed shape NaF granule is higher than that of spherical granule, in opposition, density of the former granule is lower. So fluidity of unfixed shape NaF granule is low, flow rate of the granules through feeder of tablet machine is slow, and arching on mortar of the tablet machine occurs. Then, some further operation for getting better fluidity needs for pelletizing of NaF granules using unfixed shape granule. The other hand, using spherical NaF granule, continuous pelletizing by commercial tablet machine can be carried out. (auth.)

Thermodynamic assessment of the LiF-NaF-ThF4-UF4 system

International Nuclear Information System (INIS)

Benes, O.; Beilmann, M.; Konings, R.J.M.

2010-01-01

A thermodynamic assessment of the LiF-NaF-ThF 4 -UF 4 system is presented in this study. The binary phase diagrams are optimized based on the known experimental data and the excess Gibbs energies of liquid and solid solutions are described using a modified quasi chemical model and polynomial formalism respectively. The higher order systems are extrapolated according to asymmetric Toop mathematical formalism. Based on the developed thermodynamic database the fuel composition of the molten salt fast reactor is optimized. In total three different fuel compositions are identified. Properties of these fuel compositions such as melting point, vapour pressure and the boiling temperature are derived from the obtained thermodynamic assessment and are presented in this study.

New 17x17 assembly takes the heat

International Nuclear Information System (INIS)

Reparaz, A.; Brown, C.A. Sr.

1992-01-01

Advanced Nuclear Fuels' (ANF's) new 17 x 17 fuel assembly described in this article offers advanced features which provide increased thermal margins, higher burnup, responsiveness to electrical grid demands, improved seismic performance and superior corrosion resistance. (Author)

P-T and T-x projections of phase diagram of CsF-ZrF4 system

International Nuclear Information System (INIS)

Karasev, N.M.; Korenev, Yu.M.; Sidorov, L.N.

1980-01-01

The CsF-ZrF 4 system has been investigated by the Knudsen effusion method and mass-spectral analysis of vaporization products. A molecular composition of vapour was determined. CsF, Cs 2 F 2 , ZrF 4 , Cs 2 ZrF 6 , CsZrF 5 , CsZr 2 F 9 molecules were found in the saturated vapour of the system. Heats of phase transitions and partial pressures of the molecules detected were determined depending on the melt compositions. Dissociation enthalpies of complex molecules were calculated. P-T and T-x projections of the state diagram of the CsF-ZrF 4 system were constructed

Nuclear power plant diagnostic system

International Nuclear Information System (INIS)

Prokop, K.; Volavy, J.

1982-01-01

Basic information is presented on diagnostic systems used at nuclear power plants with PWR reactors. They include systems used at the Novovoronezh nuclear power plant in the USSR, at the Nord power plant in the GDR, the system developed at the Hungarian VEIKI institute, the system used at the V-1 nuclear power plant at Jaslovske Bohunice in Czechoslovakia and systems of the Rockwell International company used in US nuclear power plants. These diagnostic systems are basically founded on monitoring vibrations and noise, loose parts, pressure pulsations, neutron noise, coolant leaks and acoustic emissions. The Rockwell International system represents a complex unit whose advantage is the on-line evaluation of signals which gives certain instructions for the given situation directly to the operator. The other described systems process signals using similar methods. Digitized signals only serve off-line computer analyses. (Z.M.)

The computerized system of meteorology data process for nuclear power plant

International Nuclear Information System (INIS)

Yan Jun; Dai Zhongde; Huang Haitao; Zhang Yiqing; Gu Zhijie

1994-06-01

Based on some specifications of the second-stage of the Qinshan Nuclear Power Plant and combined with advantages of STD-BUS, the computerized acquisition system with 7 kinds of meteorology data was developed. The system was put into operation in Nov. 1991, and acquisition rate reached 90% in one year. The system consists of two sub-systems, 7 kinds of meteorology sensors and their interface. Rain and sun radiation quantities are transmitted by means of V/F conversion. In order to enhance the system reliability all sensors are calibrated, the industrial control computer with STD-BUS is applied. The system has keyboard, micro-printer and LED display with block construction and has good resistance to interference

17 CFR 270.18f-2 - Fair and equitable treatment for holders of each class or series of stock of series investment...

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Fair and equitable treatment for holders of each class or series of stock of series investment companies. 270.18f-2 Section 270.18f... or series of stock of series investment companies. (a) For purposes of this § 270.18f-2 a series...

Thermodynamic assessment of the LiF–ThF4–PuF3–UF4 system

NARCIS (Netherlands)

Capelli, E.; Benes, O.; Konings, R.J.M.

2015-01-01

The LiF–ThF4–PuF3–UF4 system is the reference salt mixture considered for the Molten Salt Fast Reactor (MSFR) concept started with PuF3. In order to obtain the complete thermodynamic description of this quaternary system, two binary systems (ThF4–PuF3 and UF4–PuF3) and two ternary systems

Assessment and balancing of nuclear fuels

International Nuclear Information System (INIS)

Reinhard, H.

1982-01-01

In 1981 nuclear energy had a share of ca. 17% in the electric power supply of the F.R. of Germany. The amount of nuclear fuels required is equal to ca. 15 million tce. In public technical discussions the economic importance which must be assigned to nuclear energy, e.g. with regard to curbing the energy price development or relieving our balance of payments, is discussed in detail. On the other hand, a number of industrial aspects of nuclear energy utilization - problems of commercial or fiscal law - have been little considered in the technical literature. The following contribution is to present the principles of commercial and fiscal law which have taken shape in connection with the assessment and balancing of the single stages of the nuclear fuel cycle. (orig./UA) [de

A family of splice variants of CstF-64 expressed in vertebrate nervous systems

Science.gov (United States)

Shankarling, Ganesh S; Coates, Penelope W; Dass, Brinda; MacDonald, Clinton C

2009-01-01

Background Alternative splicing and polyadenylation are important mechanisms for creating the proteomic diversity necessary for the nervous system to fulfill its specialized functions. The contribution of alternative splicing to proteomic diversity in the nervous system has been well documented, whereas the role of alternative polyadenylation in this process is less well understood. Since the CstF-64 polyadenylation protein is known to be an important regulator of tissue-specific polyadenylation, we examined its expression in brain and other organs. Results We discovered several closely related splice variants of CstF-64 – collectively called βCstF-64 – that could potentially contribute to proteomic diversity in the nervous system. The βCstF-64 splice variants are found predominantly in the brains of several vertebrate species including mice and humans. The major βCstF-64 variant mRNA is generated by inclusion of two alternate exons (that we call exons 8.1 and 8.2) found between exons 8 and 9 of the CstF-64 gene, and contains an additional 147 nucleotides, encoding 49 additional amino acids. Some variants of βCstF-64 contain only the first alternate exon (exon 8.1) while other variants contain both alternate exons (8.1 and 8.2). In mice, the predominant form of βCstF-64 also contains a deletion of 78 nucleotides from exon 9, although that variant is not seen in any other species examined, including rats. Immunoblot and 2D-PAGE analyses of mouse nuclear extracts indicate that a protein corresponding to βCstF-64 is expressed in brain at approximately equal levels to CstF-64. Since βCstF-64 splice variant family members were found in the brains of all vertebrate species examined (including turtles and fish), this suggests that βCstF-64 has an evolutionarily conserved function in these animals. βCstF-64 was present in both pre- and post-natal mice and in different regions of the nervous system, suggesting an important role for βCstF-64 in neural gene

Ion-molecular equilibria and activity determination in the RbF-ZrF4 system

International Nuclear Information System (INIS)

Skokan, E.V.; Nikitin, M.I.; Sorokin, I.D.; Korenev, Yu.M.; Sidorov, L.N.

1983-01-01

Activity of zirconium tetrofluoride in 100-33.3 mol % ZrF 4 concentration range was determined during isothermal evaporation of samples of different initial composition of RbF-ZrF 4 system, using ion-molecular equilibrium method. It became possible, using the exchange ion-molecular reactions to determine ZrF 4 activity approximately 10 -10 in the region of state diagram of RbF-ZrF 4 system, adjoining to rubidium fluoride. The comparative analysis of results, obtained by the methods of isothermal evaporation, ion-molecular equilibria is given; the advantages and restrictions of ion-molecular equilibrium method are presented

Innovative nuclear energy systems roadmap

International Nuclear Information System (INIS)

2007-12-01

Developing nuclear energy that is sustainable, safe, has little waste by-product, and cannot be proliferated is an extremely vital and pressing issue. To resolve the four issues through free thinking and overall vision, research activities of 'innovative nuclear energy systems' and 'innovative separation and transmutation' started as a unique 21st Century COE Program for nuclear energy called the Innovative Nuclear Energy Systems for Sustainable Development of the World, COE-INES. 'Innovative nuclear energy systems' include research on CANDLE burn-up reactors, lead-cooled fast reactors and using nuclear energy in heat energy. 'Innovative separation and transmutation' include research on using chemical microchips to efficiently separate TRU waste to MA, burning or destroying waste products, or transmuting plutonium and other nuclear materials. Research on 'nuclear technology and society' and 'education' was also added in order for nuclear energy to be accepted into society. COE-INES was a five-year program ending in 2007. But some activities should be continued and this roadmap detailed them as a rough guide focusing inventions and discoveries. This technology roadmap was created for social acceptance and should be flexible to respond to changing times and conditions. (T. Tanaka)

Continuous monitoring system of environmental γ radiation near nuclear facility

International Nuclear Information System (INIS)

Jin Hua; Yue Qingyu; Wang Wenhai

1996-01-01

The continuous monitoring system for the environmental γ radiation and accident emergency near nuclear facility is described. The continuous monitoring system consists of high pressurized ionization chamber, integrated weak current amplifier, V-F converter and intelligent data recorder. PC 486 microcomputer with standard RS-232C interface is used for data handling and graph plotting. This intelligent data recorder has the functions of alarm over threshold and records the output signal of detector and temperature. The measuring range is from 10 nGy h -1 to 10 mGy h -1 because a high insulation switch automatical changing the measuring ranges is used. The monitoring system has been operating continuously for a long time with high stability and reliability

Cycle for innovative nuclear Gen 4. systems=; Cycle des systemes du futur

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

In the framework of the development of nuclear systems of the 4. generation, the preliminary and schematic reprocessing goals are a cleaning of fission products without a priori separation of the different actinides. The objective of the workshop is to exchange information about the potential efficiency of innovative fuel processing treatments in order to evaluate the impact of impurities on the design of the fuel during its re-fabrication and re-introduction inside the reactor, and on the materials and systems. This document gathers the slides of the 18 presentations given at this workshop: 1 - from the PWR fuel to the closed cycle fast spectrum concepts of generation 4 systems (P. Anzieu, F. Carre, Ph. Brossard, M. Delpech); 2 - the double strata scenarios: objectives and characteristics (S. David and F. Varaine); 3 - why a molten salts thorium file (D. Heuer); 4 - the common 'molten salts' research program of the CNRS (D. Heuer, S. Sanchez); 5 - the hydro-metallurgical reprocessing, the knowledge gained and the statuses of the 5. PCRD, synthesis of the OECD works (C. Madic); 6 - pyro-chemistry: Pyropep status (H. Boussier); 7 - technological bolts identified during the Most project of the 5. PCRD (C. Renault, Ch. Le Brun, M. Delpech and C. Garzenne); 8 - the molten salt reactor concept and its reprocessing options, expected efficiencies (L. Mathieu); 9 - methodology of evaluation of pyro-chemical fuel reprocessing schemes (H. Boussier); 10 - molten salt reactor, design-aided tools for the reactor and the reprocessing plant (O. Gastaldi, E. Walle, O. Koberl, D. Lecarpentier); 11 - status of CEA's prospective studies for the front-end of the fuel reprocessing process/dry ways (S. Bourg); 12 - results of activity coefficient measurements in liquid metals (J. Finne, E. Walle, G. Picard, S. Sanchez and O. Conocar); 13 - potentialities of electrolytic separation and liquid-liquid extraction processes (molten salts/molten metal) for the multi

Gamma radiation measurements in F-18 production in the RDS-111 Cyclotron from the Nuclear Engineering Institute

International Nuclear Information System (INIS)

Taam, Ilka H.; Bellido, Luis F.; Vinagre Filho, Ubirajara M.

2005-01-01

With the acquisition of RDS-111 particle accelerator, the Institute of Nuclear Engineering in Rio de Janeiro city (IEN) operates a new cyclotron to produce 1 8F to obtain the fluorodeoxyglucose (FDG), a radiopharmaceutical used in positron emission tomography (PET), a technique well advanced which allows obtaining images with high resolution for diagnoses in medicine. To evaluate and detect the gamma exposure during 1 8F production, in the routine operation, i.e. current of 30 μA and the operating time 120 minutes, it was used a portable detector hyperpure germanium (HPGe) coupled to an electronic system for acquisition of 4096 data channels. To obtain a wide energy spectrum from 0.1 to 20 MeV were performed measurements with different gains of amplification. The energy average of gamma radiation, calculated from the energy spectra of gamma rays obtained, was 1.59 ± 0.05 MeV. Meanwhile, measurements were made with a MIR 7026 monitor and with thermoluminescent detectors (TLD) of LiF: Mg, Cu, P to calculate the dose equivalent rates H * (10) of the installation

Nuclear steam supply system and method of installation

International Nuclear Information System (INIS)

Tower, S.N.; Christenson, J.A.; Braun, H.E.

1989-01-01

This patent describes a method of providing a nuclear reactor power plant at a predetermined use site accessible by predetermined navigable waterways. The method is practiced with apparatus including a nuclear reactor system. The system has a nuclear steam-supply section. The method consists of: constructing a nuclear reactor system at a manufacturing site remote from the predetermined use site but accessible to the predetermined waterways for transportation from the manufacturing site to the predetermined use site, the nuclear reactor system including a barge with the nuclear steam supply section constructed integrally with the barge. Simultaneously with the construction of the nuclear reactor system, constructing facilities at the use site to be integrated with the nuclear reactor system to form the nuclear-reactor power plant; transporting the nuclear reactor system along the waterways to the predetermined use site; at the use site joining the removal parts of the altered nuclear reactor system to the remainder of the altered nuclear reactor system to complete the nuclear reactor system; and installing the nuclear reactor system at the predetermined use site and integrating the nuclear reactor system to interact with the facilities constructed at the predetermined use site to form the nuclear-reactor power plant

Cost estimation of hydrogen and DME produced by nuclear heat utilization system II

International Nuclear Information System (INIS)

Shiina, Yasuaki; Nishihara, Tetsuo

2004-09-01

Utilization and production of hydrogen has been studied in order to spread utilization of the hydrogen energy in 2020 or 2030. It will take, however, many years for the hydrogen energy to be used very easily like gasoline, diesel oil and city gas in the world. During the periods, low CO 2 release liquid fuels would be used together with hydrogen. Recently, di-methyl-ether (DME). has been noticed as one of the substitute liquid fuels of petroleum. Such liquid fuels can be produced from the mixed gas such as hydrogen and carbon oxide which are produced from natural gas by steam reforming. Therefore, the system would become one of the candidates of future system of nuclear heat utilization. Following the study in 2002, we performed economic evaluation of the hydrogen and DME production by nuclear heat utilization plant where heat generated by HTGR is completely consumed for the production. The results show that hydrogen price produced by nuclear was about 17% cheaper than the commercial price by increase in recovery rate of high purity hydrogen with increased in PSA process. Price of DME in indirect method produced by nuclear heat was also about 17% cheaper than the commercial price by producing high purity hydrogen in the DME producing process. As for the DME, since price of DME produced near oil land in petroleum exporting countries is cheaper than production in Japan, production of DME by nuclear heat in Japan has disadvantage economically in this time. Trial study to estimate DME price produced by direct method was performed. From the present estimation, utilization of nuclear heat for the production of hydrogen would be more effective with coupled consideration of reduction effect of CO 2 release. (author)

Nuclear Power Plant Cyber Security Discrete Dynamic Event Tree Analysis (LDRD 17-0958) FY17 Report

Energy Technology Data Exchange (ETDEWEB)

Wheeler, Timothy A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Denman, Matthew R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Williams, R. A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Martin, Nevin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jankovsky, Zachary Kyle [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-09-01

Instrumentation and control of nuclear power is transforming from analog to modern digital assets. These control systems perform key safety and security functions. This transformation is occurring in new plant designs as well as in the existing fleet of plants as the operation of those plants is extended to 60 years. This transformation introduces new and unknown issues involving both digital asset induced safety issues and security issues. Traditional nuclear power risk assessment tools and cyber security assessment methods have not been modified or developed to address the unique nature of cyber failure modes and of cyber security threat vulnerabilities. iii This Lab-Directed Research and Development project has developed a dynamic cyber-risk in- formed tool to facilitate the analysis of unique cyber failure modes and the time sequencing of cyber faults, both malicious and non-malicious, and impose those cyber exploits and cyber faults onto a nuclear power plant accident sequence simulator code to assess how cyber exploits and cyber faults could interact with a plants digital instrumentation and control (DI&C) system and defeat or circumvent a plants cyber security controls. This was achieved by coupling an existing Sandia National Laboratories nuclear accident dynamic simulator code with a cyber emulytics code to demonstrate real-time simulation of cyber exploits and their impact on automatic DI&C responses. Studying such potential time-sequenced cyber-attacks and their risks (i.e., the associated impact and the associated degree of difficulty to achieve the attack vector) on accident management establishes a technical risk informed framework for developing effective cyber security controls for nuclear power.

Characterization of the fusion-fission process in light nuclear systems

International Nuclear Information System (INIS)

Anjos, R.M. dos.

1992-01-01

Fusion cross sections measurements of highly damped processes and elastic scattering were performed for the 16, 17, 18 O + 10, 11 B and 19 F + 9 Be, in the incident energy interval 22 ≤ E LAB ≤ 64 MeV. Evidences are presented that highly damped binary processes observed in these systems are originated from a fusion-fission process rather than a dinuclear ''orbiting'' mechanism. The relative importance of the fusion-fission process in these very light systems is demonstrated both by the experimental results, which indicate a statistically balanced compound nucleus fission process occurrence, and theoretical calculations. (L.C.J.A.)

Nuclear Installations Act 1965

International Nuclear Information System (INIS)

1965-01-01

This Act governs all activities related to nuclear installations in the United Kingdom. It provides for the licensing procedure for nuclear installations, the duties of licensees, the competent authorities and carriers of nuclear material in respect of nuclear occurrences, as well as for the system of third party liability and compensation for nuclear damage. The Act repeals the Nuclear Installations (Licensing and Insurance) Act 1959 and the Nuclear Installations (Amendment Act) 1965 except for its Section 17(2). (NEA) [fr

Endogenous interleukin (IL)-17A promotes pristane-induced systemic autoimmunity and lupus nephritis induced by pristane.

Science.gov (United States)

Summers, S A; Odobasic, D; Khouri, M B; Steinmetz, O M; Yang, Y; Holdsworth, S R; Kitching, A R

2014-06-01

Interleukin (IL)-17A is increased both in serum and in kidney biopsies from patients with lupus nephritis, but direct evidence of pathogenicity is less well established. Administration of pristane to genetically intact mice results in the production of autoantibodies and proliferative glomerulonephritis, resembling human lupus nephritis. These studies sought to define the role of IL-17A in experimental lupus induced by pristane administration. Pristane was administered to wild-type (WT) and IL-17A(-/-) mice. Local and systemic immune responses were assessed after 6 days and 8 weeks, and autoimmunity, glomerular inflammation and renal injury were measured at 7 months. IL-17A production increased significantly 6 days after pristane injection, with innate immune cells, neutrophils (Ly6G(+)) and macrophages (F4/80(+)) being the predominant source of IL-17A. After 8 weeks, while systemic IL-17A was still readily detected in WT mice, the levels of proinflammatory cytokines, interferon (IFN)-γ and tumour necrosis factor (TNF) were diminished in the absence of endogenous IL-17A. Seven months after pristane treatment humoral autoimmunity was diminished in the absence of IL-17A, with decreased levels of immunoglobulin (Ig)G and anti-dsDNA antibodies. Renal inflammation and injury was less in the absence of IL-17A. Compared to WT mice, glomerular IgG, complement deposition, glomerular CD4(+) T cells and intrarenal expression of T helper type 1 (Th1)-associated proinflammatory mediators were decreased in IL-17A(-/-) mice. WT mice developed progressive proteinuria, but functional and histological renal injury was attenuated in the absence of IL-17A. Therefore, IL-17A is required for the full development of autoimmunity and lupus nephritis in experimental SLE, and early in the development of autoimmunity, innate immune cells produce IL-17A. © 2014 British Society for Immunology.

Effects of Interleukin 17 on the cardiovascular system.

Science.gov (United States)

Robert, Marie; Miossec, Pierre

2017-09-01

Cardiovascular diseases remain the leading cause of death worldwide and account for most of the premature mortality observed in chronic inflammatory diseases. Common mechanisms underlie these two types of disorders, where the contribution of Interleukin (IL)-17A, the founding member of the IL-17 family, is highly suspected. While the local effects of IL-17A in inflammatory disorders have been well described, those on the cardiovascular system remain less studied. This review focuses on the effects of IL-17 on the cardiovascular system both on isolated cells and in vivo. IL-17A acts on vessel and cardiac cells, leading to inflammation, coagulation and thrombosis. In vivo and clinical studies have shown its involvement in the pathogenesis of cardiovascular diseases including atherosclerosis and myocardial infarction that occur prematurely in chronic inflammatory disorders. As new therapeutic approaches are targeting the IL-17 pathway, this review should help to better understand their positive and negative outcomes on the cardio-vascular system. Copyright © 2017 Elsevier B.V. All rights reserved.

Military nuclear activities. Strategic prospects

International Nuclear Information System (INIS)

Coldefy, Alain; Wodka-Gallien, Philippe; Tertrais, Bruno; Rouillard, Gwendal; Widemann, Thierry; Guillaume, Louis-Michel; Steininger, Philippe; Guillemette, Alain; Amabile, Jean-Christophe; Granger-Veyron, Nicolas; Carbonnieres, Hubert de; Roche, Nicolas; Guillou, Herve; Bouvier, Antoine; Pastre, Bertrand; Baconnet, Alexis; Monsonis, Guillem; Brisset, Jean-Vincent; Hemez, Remy; Tchernega, Vladimir; Wedin, Lars; Dumoulin, Andre; Razoux, Pierre; Migault, Philippe; Wilson, Ward; Maillard, Benjamin de; Aichi, Leila; Charvoz, Ivan; Rousset, Valery; Lespinois, Jerome de; Kempf, Olivier; Dufourcq, Jean; Gere, Francois; Mauro, Frederic; Delort Laval, Gabriel; Charaix, Patrick; Norlain, Bernard; Collin, Jean-Marie; Jourdier, Francois

2015-01-01

This special dossier aims at providing some key articles about France's deterrence doctrine. It provides a comprehensive overview of the challenges and questions about military nuclear activities and opens up some future prospects about this question. The dossier comprises 37 papers dealing with: 1 - Military nuclear activities: yesterday, today, tomorrow (Coldefy, A.); 2 - Deterrence according to French President Francois Hollande: continuation, precision and inflexions (Tertrais, B.); 3 - French deterrence warrantor of our independence in the 21. century (Rouillard, G.); 4 - The deterrence concept prior to the nuclear weapon era (Widemann, T.); 5 - France: the strategic marine force in operation (Guillaume, L.M.); 6 - Relevance of the airborne component in the nuclear deterrence strategy (Steininger, P.); 7 - Deterrence stakes for the Directorate General of Armaments (Guillemette, A.); 8 - The Charles-de-Gaulle aircraft carrier: the deterrence voice from the sea (Wodka-Gallien, P.); 9 - Deterrence: missions of the army's radiation protection department (Amabile, J.C.; Granger-Veyron, N.; Carbonnieres, H. de); 10 - The French Atomic Energy Commission (CEA) and the French defense strategy (Roche, N.); 11 - DCNS, general contractor in the service of deterrence (Guillou, H.); 12 - The airborne nuclear component for MBDA (Bouvier, A.); 13 - Ballistic missile of the marine nuclear component: industrial stakes (Pastre, B.); 14 - Beyond defense against missiles: a US anti-deterrence strategy (Baconnet, A.); 15 - Deterrence dynamics in South Asia (Monsonis, G.); 16 - Military nuclear activities in East Asia (Brisset, J.V.); 17 - North Korea would own nuclear weapons, so what? (Hemez, R.); 18 - About the risk of nuclear warfare in Europe (Tchernega, V.); 19 - Present day nuclear activities: deterrence and gesticulation (Wedin, L.); 20 - Belgian F-16 replacement: nuclear dimension (Dumoulin, A.); 21 - Israel and nuclear deterrence (Razoux, P.); 22 - Nuclear

Status of operation of radionuclides assay system in Korean nuclear power plant

International Nuclear Information System (INIS)

Hwang, K.H.; Lee, K.J.; Jeong, C.W.; Ahn, S.M.

2003-01-01

In Korea, 17 nuclear power plants composed of 13 pressurized water reactors and 4 CANDU reactors are currently in operation. The cumulative amounts of low and intermediate level radioactive waste in nuclear power plant reached 58,718 drums (unit: 200 liter) in 2001. Efforts to construct LILW disposal facility are continued and its first operation is planned in the year 2008. Its first stage capacity is assumed to be 100,000 drums and total capacity will reach to 800,000 drums. Radwaste disposal site selection is an urgent national project at present time. Regulations and guidelines require detailed information about the radioactive waste package and its contents prior to the transport to the disposal sites. The Enforcement Decree of the Korean Atomic Energy Act (articles 234-17) requires the Minister of Science and Technology (MOST) of Korea to establish regulation for the waste acceptance (MOST notice. 1196-10). It requires detailed information about the radioactive waste package and its contents such as activity of radionuclides, total activities, types and characteristics of waste. For the measurement of the concentrations and activities of radionuclides in radwaste drum, a radionuclides assay system is installed at Korean nuclear power plant (KORI site) in 1996. The waste drum can be measured in the vertical direction with eight vertical segments while in the radial direction also with eight segments. Using this measurement method, homogeneous and non-homogeneous waste drum can be measured. Scaling factor methods have been played a dominant role in the determination of the radionuclides concentration in this system. For corrosion product, generic scaling factors were used due to the similarity and better-characterized properties of Korean analyzed data as compared with the worldwide data base of PWR industry. For fission product and TRU nuclides, it is not easy to determine the generic scaling factors. Thus simple model reflecting the operation history of power

Mobile nuclear power systems

International Nuclear Information System (INIS)

Andersson, B.

1988-11-01

This report is meant to present a general survey of the mobile nuclear power systems and not a detailed review of their technical accomplishments. It is based in published material mainly up to 1987. Mobile nuclear power systems are of two fundamentally different kinds: nuclear reactors and isotopic generators. In the reactors the energy comes from nuclear fission and in the isotopic generators from the radioactive decay of suitable isotopes. The reactors are primarily used as power sourves on board nuclear submarines and other warships but have also been used in the space and in remote places. Their thermal power has ranged from 30 kWth (in a satellite) to 175 MWth (on board an aircraft carrier). Isotopic generators are suitable only for small power demands and have been used on board satellites and spaceprobes, automatic weatherstations, lighthouses and marine installations for navigation and observation. (author)

Nuclear imaging system

International Nuclear Information System (INIS)

Barrett, H.H.; Horrigan, F.A.

1975-01-01

This invention relates to a nuclear imaging system for mapping the source of high energy nuclear particles from a living organ which has selectively absorbed a radioactive compound by spatially coding the energy from the source in a Fresnel pattern on a detector and decoding the detector output to prouce an image of the source. The coding is produced by a Fresnel zone plate interposed between the nuclear energy source and the detector whose position is adjustable with respect to the detector to focus the slices of the nuclear source on the detector. By adjusting the zone plate to a plurality of positions, data from a plurality of cross-sectional slices are produced from which a three-dimensional image of the nuclear source may be obtained. (Patent Office Record)

Future nuclear systems technology

International Nuclear Information System (INIS)

Brooks, H.

1979-01-01

Five directions can be identified for evolution of nuclear systems, possibly a sixth. These are, first, and perhaps most important, toward a means of extending fissile resources through improvement of the efficiency of their use; second, improvements in nuclear safety; third, reduction in the environmental impacts of nuclear electric power generation, particularly water requirements; fourth, improvements in proliferation resistance of the nuclear fuel cycle; and fifth, improvements in economics. And added in a sixth, and somewhat more speculative direction, the use of nuclear power for purposes other than the direct generation of electricity

Nuclear containment systems and in-service inspection status of Korea nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Jihong, Park; Jaekeun, Hong; Banuk, Park [Korea Institute of Machinery and Materials, Dept. of Authorized Test and Evaluation, Kyungnam (Korea, Republic of)

2007-07-01

20 unit nuclear power plants in Korea have been operated and maintained since the first unit started in commercial service in 1978. Most recently 4 units were under construction and several units were planned to be constructed. by industries. 4 types of nuclear containment systems have been constructed until now: first, metal containments, then pre-stressed concrete containments with grouted tendon systems, followed by pre-stressed concrete containments with un-grouted tendon systems, and Korea standard nuclear containments. All the nuclear containments should be inspected periodically. Therefore for periodic in-service inspection, several appropriate technical requirements should be applied differently depending on the specific nuclear containment types. With the changes of times, nuclear containment systems have undergone a remarkable change, and finally nuclear containment system of Korea standard nuclear power plant was settled down, and as a matter of course it dominates the trend of present and future nuclear containment systems. Overall in-service inspection results of most Korea nuclear containments have not showed any serious evidence of degradation.

Measurement system for nuclear safeguards based on bismuth-germanate scintillators

International Nuclear Information System (INIS)

Moss, C.E.; Dowdy, E.J.; Evans, A.E.; Hamm, M.E.; Lucas, M.C.; Shunk, E.R.

1983-01-01

To determine gamma-ray flux spectra, with high efficiency as the foremost objective, we constructed a system that uses bismuth-germanage scintillators as sensors. The system, consisting of eight scintillators and a LeCroy 3500 data acquisition system, has been calibrated and characterized from 0.06 to 8.29 MeV. By fitting the calibration spectra with a function containing 17 parameters, we were able to construct theoretical response functions, which we then used to obtain the gamma-ray flux spectra at multiple space points resulting from a variety of radioactive objects of interest in nuclear safeguards. The results of our procedure agree with calculated values to within less than 10%. 6 figures

A study of the modifications of nuclear instrumentation systems for JRR-2

International Nuclear Information System (INIS)

Azim, Mohammad; Horiki, Ooichiro; Sato, Mitsugu

1978-04-01

In this report a comparative study has been carried out between the original A.M.F. design and the modified design for the nuclear instrumentation systems of the Research Reactor JRR-2, at the Tokai Research Establishment of JAERI. Due to a fire accident in the control room, in July 1968, the originally designed nuclear instrumentation systems, using conventional vacuum tube circuits, were destroyed and were replaced by the modified design, incorporating solid state linear integrated circuits as basic circuit components. The results of the reactor instrumentation systems modification at JRR-2 are very encouraging as the operating efficiency of the Reactor registered an improvement of 43%. Moreover the safety aspects have been fully taken care of in the new design and the reactor is well guarded against all possible instrument failures and human errors. This report presents the basic theory of operation of the two designs alongwith a comparative safety analysis. (auth.)

Federal Administrative Court, judgement of December 17, 1986 (nuclear power station at international border)

International Nuclear Information System (INIS)

Anon.

1987-01-01

In its decision of December 17, 1986, the Federal Administrative Court accepted the right of action of Dutch borderers against an atomic licence for a German nuclear power plant. The necessary involvement according to sec. 42 Paragraph 2 of the Administrative Court Procedure Act results from the violation of the third party protection provision in sec. 7 Atomic Energy Act. (WG) [de

Nuclear Systems Kilopower Overview

Science.gov (United States)

Palac, Don; Gibson, Marc; Mason, Lee; Houts, Michael; McClure, Patrick; Robinson, Ross

2016-01-01

The Nuclear Systems Kilopower Project was initiated by NASAs Space Technology Mission Directorate Game Changing Development Program in fiscal year 2015 to demonstrate subsystem-level technology readiness of small space fission power in a relevant environment (Technology Readiness Level 5) for space science and human exploration power needs. The Nuclear Systems Kilopower Project consists of two elements. The primary element is the Kilopower Prototype Test, also called the Kilopower Reactor Using Stirling Technology(KRUSTY) Test. This element consists of the development and testing of a fission ground technology demonstrator of a 1 kWe fission power system. A 1 kWe system matches requirements for some robotic precursor exploration systems and future potential deep space science missions, and also allows a nuclear ground technology demonstration in existing nuclear test facilities at low cost. The second element, the Mars Kilopower Scalability Study, consists of the analysis and design of a scaled-up version of the 1 kWe reference concept to 10 kWe for Mars surface power projected requirements, and validation of the applicability of the KRUSTY experiment to key technology challenges for a 10 kWe system. If successful, these two elements will lead to initiation of planning for a technology demonstration of a 10 kWe fission power capability for Mars surface outpost power.

Coulomb and nuclear excitations of narrow resonances in 17Ne

Directory of Open Access Journals (Sweden)

J. Marganiec

2016-08-01

Full Text Available New experimental data for dissociation of relativistic 17Ne projectiles incident on targets of lead, carbon, and polyethylene targets at GSI are presented. Special attention is paid to the excitation and decay of narrow resonant states in 17Ne. Distributions of internal energy in the O15+p+p three-body system have been determined together with angular and partial-energy correlations between the decay products in different energy regions. The analysis was done using existing experimental data on 17Ne and its mirror nucleus 17N. The isobaric multiplet mass equation is used for assignment of observed resonances and their spins and parities. A combination of data from the heavy and light targets yielded cross sections and transition probabilities for the Coulomb excitations of the narrow resonant states. The resulting transition probabilities provide information relevant for a better understanding of the 17Ne structure.

21 CFR 892.1310 - Nuclear tomography system.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Nuclear tomography system. 892.1310 Section 892...) MEDICAL DEVICES RADIOLOGY DEVICES Diagnostic Devices § 892.1310 Nuclear tomography system. (a) Identification. A nuclear tomography system is a device intended to detect nuclear radiation in the body and...

Communication of nuclear data progress: No.4(1990)

International Nuclear Information System (INIS)

1990-12-01

Communication of Nuclear Data Progress (CNDP) in English is set up by Chinese Nuclear Committee and Chinese Nuclear Data Center (CNDC). This is the fourth issue. It includes measurements of neutron smaee angle scattering cross sections for Fe, Ni and Cr; n-D scattering phase-shift and 17 O R-matrix analyses; calculations of neutron elastic and inclastic scattering from 7 Li; evaluations of 2 H(n,2n), 23 Na, 59 Co(n, γ), 235,238 U, 239 Pu(n,f) and (n, γ) cross sections; and a fitting code of corrected SLBW with multlievel effect (CBNFIT); R-matrix analysis code (RAC) etc

Nuclear Space Power Systems Materials Requirements

International Nuclear Information System (INIS)

Buckman, R.W. Jr.

2004-01-01

High specific energy is required for space nuclear power systems. This generally means high operating temperatures and the only alloy class of materials available for construction of such systems are the refractory metals niobium, tantalum, molybdenum and tungsten. The refractory metals in the past have been the construction materials selected for nuclear space power systems. The objective of this paper will be to review the past history and requirements for space nuclear power systems from the early 1960's through the SP-100 program. Also presented will be the past and present status of refractory metal alloy technology and what will be needed to support the next advanced nuclear space power system. The next generation of advanced nuclear space power systems can benefit from the review of this past experience. Because of a decline in the refractory metal industry in the United States, ready availability of specific refractory metal alloys is limited

Nuclear data information system for nuclear materials

International Nuclear Information System (INIS)

Fujita, Mitsutane; Noda, Tetsuji; Utsumi, Misako

1996-01-01

The conceptual system for nuclear material design is considered and some trials on WWW server with functions of the easily accessible simulation of nuclear reactions are introduced. Moreover, as an example of the simulation on the system using nuclear data, transmutation calculation was made for candidate first wall materials such as 9Cr-2W steel, V-5Cr-5Ti and SiC in SUS316/Li 2 O/H 2 O(SUS), 9Cr-2W/Li 2 O/H 2 O(RAF), V alloy/Li/Be(V), and SiC/Li 2 ZrO 3 /He(SiC) blanket/shield systems based on ITER design model. Neutron spectrum varies with different blanket/shield compositions. The flux of low energy neutrons decreases in order of V< SiC< RAF< SUS blanket/shield systems. Fair amounts of W depletion in 9Cr-2W steel and the increase of Cr content in V-5Cr-5Ti were predicted in SUS or RAF systems. Concentration change in W and Cr is estimated to be suppressed if Li coolant is used in place of water. Helium and hydrogen production are not strongly affected by the different blanket/shield compositions. (author)

DIMCO. A new system for mechanical and bidimensional of nuclear fuel pins

International Nuclear Information System (INIS)

Moreno, A.

1977-01-01

The system developed in JEN, for: the mechanical analysis uni and bidimensional, of nuclear fuels is presented. The mathematical and numerical foundations used, are here described. And so the models developed for effects such as swelling, cracking, clad growth etc. Numerical results for several cases are presented. a) Numerical test in one and two dimensions. b) Applicability range, c) Interaction effects. d) Influence of the power history. (Author) 17 refs

Percolation and nucleation approaches to nuclear fragmentation: criticality in very small systems

Energy Technology Data Exchange (ETDEWEB)

Santiago, A.J. [Universidade do Estado, Rio de Janeiro, RJ (Brazil). Inst. de Fisica; Chung, K.C.

1994-12-01

Different criteria for criticality in very small systems are discussed in the context of percolation and nucleation approaches to nuclear fragmentation. It is shown that the probability threshold in percolation and interaction radius threshold in nucleation are very strongly dependent upon the adopted criterion. By using Monte Carlo method, similarities and dissimilarities between nucleation and percolation pictures are also pointed out. (author). 17 refs, 5 figs, 2 tabs.

Percolation and nucleation approaches to nuclear fragmentation: criticality in very small systems

International Nuclear Information System (INIS)

Santiago, A.J.; Chung, K.C.

1994-12-01

Different criteria for criticality in very small systems are discussed in the context of percolation and nucleation approaches to nuclear fragmentation. It is shown that the probability threshold in percolation and interaction radius threshold in nucleation are very strongly dependent upon the adopted criterion. By using Monte Carlo method, similarities and dissimilarities between nucleation and percolation pictures are also pointed out. (author). 17 refs, 5 figs, 2 tabs

WESTINGHOUSE 17X17 MOX PWR ASSEMBLY - WASTE PACKAGE CRITICALITY ANALYSIS (SCPB: N/A)

International Nuclear Information System (INIS)

J.W. Davis

1996-01-01

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to compare the criticality potential of Westinghouse 17 x 17 mixed oxide (MOX) PWR fuel with the Design Basis spent nuclear fuel (SNF) analyzed previously (Ref. 5.1, 5.2). The basis of comparison will be the conceptual design Multi-Purpose Canister (MPC) PWR waste package concepts. The objectives of this evaluation are to show that the criticality potential of the MOX fuel is equal to or lower than the DBF or, if necessary, indicate what additional measures are required to make it so

Experience with Nuclear Medicine Information System

Directory of Open Access Journals (Sweden)

Bilge Volkan-Salanci

2012-12-01

Full Text Available Objective: Radiology information system (RIS is basically evolved for the need of radiologists and ignores the vital steps needed for a proper work flow of Nuclear Medicine Department. Moreover, CT/MRI oriented classical PACS systems are far from satisfying Nuclear Physicians like storing dynamic data for reprocessing and quantitative analysis of colored images. Our purpose was to develop a workflow based Nuclear Medicine Information System (NMIS that fulfills the needs of Nuclear Medicine Department and its integration to hospital PACS system. Material and Methods: Workflow in NMIS uses HL7 (health level seven and steps include, patient scheduling and retrieving information from HIS (hospital information system, radiopharmacy, acquisition, digital reporting and approval of the reports using Nuclear Medicine specific diagnostic codes. Images and dynamic data from cameras of are sent to and retrieved from PACS system (Corttex© for reprocessing and quantitative analysis. Results: NMIS has additional functions to the RIS such as radiopharmaceutical management program which includes stock recording of both radioactive and non-radioactive substances, calculation of the radiopharmaceutical dose for individual patient according to body weight and maximum permissible activity, and calculation of radioactivity left per unit volume for each radionuclide according their half lives. Patient scheduling and gamma camera patient work list settings were arranged according to specific Nuclear Medicine procedures. Nuclear Medicine images and reports can be retrieved and viewed from HIS. Conclusion: NMIS provides functionality to standard RIS and PACS system according to the needs of Nuclear Medicine. (MIRT 2012;21:97-102

17 CFR 240.17a-23 - Recordkeeping and reporting requirements relating to broker-dealer trading systems.

Science.gov (United States)

2010-04-01

... requirements relating to broker-dealer trading systems. 240.17a-23 Section 240.17a-23 Commodity and Securities... relating to broker-dealer trading systems. (a) Scope of section. This section shall apply to any registered broker or dealer that acts as the sponsor of a broker-dealer trading system. (b) Definitions. For...

xF 3( x,Q 2) Structure Function and Gross-Llewellyn Smith Sum Rule with Nuclear Effect and Higher Twist Correction

International Nuclear Information System (INIS)

Nath, N.M.; Mukharjee, A.; Das, M.K.; Sarma, J.K.

2016-01-01

We present an analysis of the xF 3 (x,Q 2 ) structure function and Gross-Llewellyn Smith(GLS) sum rule taking into account the nuclear effects and higher twist correction. This analysis is based on the results presented in [N.M. Nath, et al, Indian J. Phys. 90 (2016) 117]. The corrections due to nuclear effects predicted in several earlier analysis are incorporated to our results of xF 3 (x,Q 2 ) structure function and GLS sum rule for free nucleon, corrected upto next-next-to-leading order (NNLO) perturbative order and calculate the nuclear structure function as well as sum rule for nuclei. In addition, by means of a simple model we have extracted the higher twist contributions to the non-singlet structure function xF 3 (x,Q 2 ) and GLS sum rule in NNLO perturbative orders and then incorporated them to our results. Our NNLO results along with nuclear effect and higher twist corrections are observed to be compatible with corresponding experimental data and other phenomenological analysis. (paper)

Nuclear propulsion systems engineering

International Nuclear Information System (INIS)

Madsen, W.W.; Neuman, J.E.: Van Haaften, D.H.

1992-01-01

The Nuclear Energy for Rocket Vehicle Application (NERVA) program of the 1960's and early 1970's was dramatically successful, with no major failures during the entire testing program. This success was due in large part to the successful development of a systems engineering process. Systems engineering, properly implemented, involves all aspects of the system design and operation, and leads to optimization of theentire system: cost, schedule, performance, safety, reliability, function, requirements, etc. The process must be incorporated from the very first and continued to project completion. This paper will discuss major aspects of the NERVA systems engineering effort, and consider the implications for current nuclear propulsion efforts

Nuclear information access system

International Nuclear Information System (INIS)

Ham, C. H.; Yang, M. H.; Yoon, S. W.

1998-01-01

The energy supply in the countries, which have abundant energy resources, may not be affected by accepting the assertion of anti-nuclear and environment groups. Anti-nuclear movements in the countries which have little energy resources may cause serious problem in securing energy supply. Especially, it is distinct in Korea because she heavily depends on nuclear energy in electricity supply(nuclear share in total electricity supply is about 40%).The cause of social trouble surrounding nuclear energy is being involved with various circumstances. However, it is very important that we are not aware of the importance of information access and prepared for such a situation from the early stage of nuclear energy's development. In those matter, this paper analyzes the contents of nuclear information access system in France and Japan which have dynamic nuclear development program and presents the direction of the nuclear access regime through comparing Korean status and referring to progresses of the regime

Summary of breakout Session F2: F2, decision support systems: Knowledge systems

International Nuclear Information System (INIS)

Anon.

1992-01-01

The discussions in breakout session F2 are summarized. The topics discussed include contingency planning, environmental sensitivity, countermeasures planning tools, cleanup operations management, and logistics support systems. General comments, concerns and major research issues are summarized

Advanced nuclear systems. Review study

International Nuclear Information System (INIS)

Liebert, Wolfgang; Glaser, Alexander; Pistner, Christoph; Baehr, Roland; Hahn, Lothar

1999-04-01

The task of this review study is to from provide an overview of the developments in the field of the various advanced nuclear systems, and to create the basis for more comprehensive studies of technology assessment. In an overview the concepts for advanced nuclear systems pursued worldwide are subdivided into eight subgroups. A coarse examination raster (set pattern) is developed to enable a detailed examination of the selected systems. In addition to a focus on enhanced safety features, further aspects are also taken into consideration, like the lowering of the proliferation risk, the enhancement of the economic competitiveness of the facilities and new usage possibilities (for instance concerning the relaxation of the waste disposal problem or the usage of alternative fuels to uranium). The question about the expected time span for realization and the discussion about the obstacles on the way to a commercially usable reactor also play a substantial role as well as disposal requirements as far as they can be presently recognized. In the central chapter of this study, the documentation of the representatively selected concepts is evaluated as well as existing technology assessment studies and expert opinions. In a few cases where this appears to be necessary, according technical literature, further policy advisory reports, expert statements as well as other relevant sources are taken into account. Contradictions, different assessments and dissents in the literature as well as a few unsettled questions are thus indicated. The potential of advanced nuclear systems with respect to economical and societal as well as environmental objectives cannot exclusively be measured by the corresponding intrinsic or in comparison remarkable technical improvements. The acceptability of novel or improved systems in nuclear technology will have to be judged by their convincing solutions for the crucial questions of safety, nuclear waste and risk of proliferation of nuclear weapons

Production and use of {sup 18}F by TRIGA nuclear reactor: a first report

Energy Technology Data Exchange (ETDEWEB)

Burgio, N.; Ciavola, C.; Festinesi, A.; Capannesi, G. [ENEA, Centro Ricerche Casaccia, Rome (Italy). Dipt. Innovazione

1999-02-01

The irradiation and radiochemical facilities at public research centre can contribute to the start up of the regional PET centre. In particular, the TRIGA reactor of Casaccia Research Centre could produce a sufficient amount of {sup 18}F to start up a PET centre and successively integrated the cyclotron production. This report establishes, in the light of the preliminary experimental works, a guideline to the reactor`s production and extraction of {sup 18}F in a convenient form for the synthesis of the most representative PET radiopharmaceutical: {sup 18}F-FDG. [Italiano] Le facilities di irraggiamento e i laboratori Radiochimici dei Centri Statali di Ricerca possono contribuire allo sviluppo di centri regionali PET (Tomografia ed Emissione Positronica). In particolare, il reattore TRIGA del Centro Ricerca Casaccia potrebbe produrre un quantitativo di {sup 18}F sufficiente alle attivita` formative propedeutiche al centro PET che, successivamente sarebbe in grado di avviare una propria produzione da ciclotrone. Questo rapporto stabilisce le linee guida sperimentali per la produzione del {sup 18}F da reattore nucleare e la sua successiva estrazione in una forma conveniente per la sintesi del piu` rappresentativo dei radiofarmaci PET: il {sup 18}F-FDG.

Estrogen and progesterone decrease let-7f microRNA expression and increase IL-23/IL-23 receptor signaling and IL-17A production in patients with severe asthma.

Science.gov (United States)

Newcomb, Dawn C; Cephus, Jacqueline Yvonne; Boswell, Madison G; Fahrenholz, John M; Langley, Emily W; Feldman, Amy S; Zhou, Weisong; Dulek, Daniel E; Goleniewska, Kasia; Woodward, Kimberly B; Sevin, Carla M; Hamilton, Robert G; Kolls, Jay K; Peebles, R Stokes

2015-10-01

Women have an increased prevalence of severe asthma compared with men. IL-17A is associated with severe asthma and requires IL-23 receptor (IL-23R) signaling, which is negatively regulated by let-7f microRNA. We sought to Determine the mechanism by which 17β-estradiol (E2) and progesterone (P4) increase IL-17A production. IL-17A production was determined by using flow cytometry in TH17 cells from women (n = 14) and men (n = 15) with severe asthma. Cytokine levels were measured by using ELISA, and IL-23R and let-7f expression was measured by using quantitative PCR in TH17-differentiated cells from healthy women (n = 13) and men (n = 14). In sham-operated or ovariectomized female mice, 17β-E2, P4, 17β-E2+P4, or vehicle pellets were administered for 3 weeks before ex vivo TH17 cell differentiation. Airway neutrophil infiltration and CXCL1 (KC) expression were also determined in ovalbumin (OVA)-challenged wild-type female recipient mice with an adoptive transfer of OVA-specific TH17 cells from female and male mice. In patients with severe asthma and healthy control subjects, IL-17A production was increased in TH17 cells from women compared with men. IL-23R expression was increased and let-7f expression was decreased in TH17-differentiated cells from women compared with men. In ovariectomized mice IL-17A and IL-23R expression was increased and Let-7f expression was decreased in TH17 cells from mice administered 17β-E2+P4 compared with those administered vehicle. Furthermore, transfer of female OVA-specific TH17 cells increased acute neutrophil infiltration in the lungs of OVA-challenged recipient mice compared with transfer of male OVA-specific TH17 cells. 17β-E2+P4 increased IL-17A production from TH17 cells, providing a potential mechanism for the increased prevalence of severe asthma in women compared with men. Copyright © 2015 American Academy of Allergy, Asthma & Immunology. Published by Elsevier Inc. All rights reserved.

Radiolabeling and in vitro and in vivo characterization of [18F]FB-[R(8,15,21), L17]-VIP as a PET imaging agent for tumor overexpressed VIP receptors.

Science.gov (United States)

Cheng, Dengfeng; Yin, Duanzhi; Li, Gucai; Wang, Mingwei; Li, Shiqiang; Zheng, Mingqiang; Cai, Hancheng; Wang, Yongxian

2006-12-01

In an effort to develop a peptide-based radiopharmaceutical for the detection of tumors overexpressed vasoactive intestinal peptide receptors with positron emission tomography, we have prepared a novel [R(8,15,21), L17]-VIP peptide for 18F-labeling. This peptide inhibited 125I-VIP binding to rats lung membranes with high affinity [half-maximal inhibitory concentrations (IC50) of 0.12 nm]. Additionally, [R(8,15,21), L17]-VIP showed higher stability than native vasoactive intestinal peptide in vivo of mice. With N-succinimidyl 4-[18F] fluorobenzoate as labeling prosthetic group, [18F]FB-[R(8,15,21), L17]-VIP was obtained in >99% radiochemical purity within 100 min in decay-for-corrected radiochemical yield of 33.6 +/- 3% (n = 5) and a specific radioactivity 255 GBq/micromol at the end of synthesis. Stability of [18F]FB-[R(8,15,21), L17]-VIP in vitro and in vivo were investigated. Biodistribution of this trace was carried out in mice with induced C26 colorectal tumor. Fast clearance of [18F]FB-[R(8,15,21), L17]-VIP from non-target tissues and specific uptakes by tumors realized higher tumor-to-muscle ratio (3.55) and tumor-to-blood ratio (2.37) 60 min postinjection. Clear difference was observed between the blocking and unblocking experiments in biodistribution and whole body radioautography. [18F]FB-[R(8,15,21), L17]-VIP has demonstrated its potential for diagnosing tumors overexpressed vasoactive intestinal peptide receptors both in vitro and in vivo.

Scenario-based roadmapping assessing nuclear technology development paths for future nuclear energy system scenarios

International Nuclear Information System (INIS)

Van Den Durpel, Luc; Roelofs, Ferry; Yacout, Abdellatif

2009-01-01

Nuclear energy may play a significant role in a future sustainable energy mix. The transition from today's nuclear energy system towards a future more sustainable nuclear energy system will be dictated by technology availability, energy market competitiveness and capability to achieve sustainability through the nuclear fuel cycle. Various scenarios have been investigated worldwide each with a diverse set of assumptions on the timing and characteristics of new nuclear energy systems. Scenario-based roadmapping combines the dynamic scenario-analysis of nuclear energy systems' futures with the technology roadmap information published and analysed in various technology assessment reports though integrated within the nuclear technology roadmap Nuclear-Roadmap.net. The advantages of this combination is to allow mutual improvement of scenario analysis and nuclear technology roadmapping providing a higher degree of confidence in the assessment of nuclear energy system futures. This paper provides a description of scenario-based roadmapping based on DANESS and Nuclear-Roadmap.net. (author)

For establishment on nuclear disaster prevention system

International Nuclear Information System (INIS)

Anon.

2000-01-01

For increasing requirement of peoples for review of nuclear disaster countermeasure at a chance of the JCO critical accident, the Japanese Government newly established the 'Special Measure Act on Nuclear Disaster Countermeasure', which was enacted on July 16, 2000. The nuclear business relatives such as electric power company and so forth established the Business program on nuclear disaster prevention in nuclear business relatives' after their consultation with local communities at their construction, under their co-operation. Simultaneously, the electric power industry field decided to intend to provide some sufficient countermeasures to incidental formation of nuclear accident such as start of the Co-operative agreement on nuclear disaster prevention among the nuclear business relatives' and so forth. Here were described on nuclear safety and disaster prevention, nuclear disaster prevention systems at the electric power industry field, abstract on 'Business program on nuclear disaster prevention in nuclear business relatives', preparation of technical assistance system for nuclear disaster prevention, executive methods and subjects on nuclear disaster prevention at construction areas, recent business on nuclear disaster prevention at the Nuclear Technical Center, and subjects on establishment of nuclear disaster prevention system. (G.K.)

The future of nuclear energy (group 17)

International Nuclear Information System (INIS)

Moncomble, J.E.

2002-01-01

This article is the work of a group of students from the ''Ecole Nationale d'Administration'', they had to study the perspective of nuclear energy in France. Nuclear energy is an important element to assure the stability of the energy supply of the country. Uranium purchases appear to be safe for being diversified and the price of the nuclear fuel contributes to only 20% of the price of the kWh compared to 40% for natural gas. Today the competitiveness of nuclear energy is assured but technological progress concerning gas turbines might challenge it in the years to come. Sustainable development implies not only abundant energy for all but also a preserved environment for the generations to come. The development of nuclear energy is hampered by the lack of satisfactory answers to the problem of fuel back-end cycle and more generally to the issue of radioactive wastes. On the other hand nuclear energy presents serious assets concerning the preservation of environment: nuclear energy as a whole from the uranium ore mining to the production of electricity emits very few atmospheric pollutants and greenhouse effect gases, and requires little room for its installations. The composition of the future energy mix will depend greatly on opinions and assumptions made about the reserves of fossil fuels, technological perspectives and the perception by the public of industrial risks (environmental damage, nuclear accidents...). (A.C.)

Nuclear Regulatory Commission issuances. Volume 17, No. 3

International Nuclear Information System (INIS)

1983-03-01

This report contains the Issuances received during March 1983 from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors Decisions (DD), and the Denials of Petition for Rulemaking (DPRM). The Issuances concerned the following facilities: Three Mile Island Nuclear Station, Unit No. 1; Comanche Peak Steam Electric Station, Units 1 and 2; Vallecitos Nuclear Center; Floating Nuclear Power Plants; San Onofre Nuclear Generating Station, Units 2 and 3; Point Beach Nuclear Plant, Unit 1; Perry Nuclear Power Plant, Units 1 and 2; Shoreham Nuclear Power Station, Unit 1; Western New York Nuclear Service Center; Limerick Generating Station, Units 1 and 2; Seabrook Station, Units 1 and 2; Black Fox Station, Units 1 and 2; WmH Zimmer Nuclear Power Station, Unit 1; WPPSS Nuclear Project No. 1; Zion Nuclear Plant, Units 1 and 2; and South Texas Project, Units 1 and 2

The national nuclear material tracking system. A Korea's countermeasure against nuclear terrorism

International Nuclear Information System (INIS)

Moon, Joo Hyun

2011-01-01

Since nuclear terrorism has been identified as a real threat, the Korean government has earnestly developed elementary technologies and sub-systems for establishing an integrated defensive system against nuclear terrorism, which is based on the concept of defense-in-depth. This paper introduces the gist and implications of the studies that have been conducted in building the national nuclear material tracking system for preventing and intercepting the illicit trafficking and transporting of nuclear material in Korea. (orig.)

IAEA Team Concludes Peer Review of Sweden's Nuclear Regulatory Framework, 17 February 2012, Stockholm, Sweden

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of senior nuclear safety and radiation protection experts today concluded a 12-day mission to review the regulatory framework for nuclear and radiation safety in Sweden. The Integrated Regulatory Review Service (IRRS) mission, which was conducted at the request of Sweden, noted good practices in the country's nuclear regulatory system and also made recommendations and suggestions for the Swedish Radiation Safety Authority (SSM) and the government. These are aimed at strengthening the effectiveness of the country's regulatory framework and functions in line with IAEA Safety Standards. ''Throughout the mission, the IRRS team received full cooperation from SSM staff in its review of Sweden's regulatory, technical and policy issues,'' said Georg Schwarz, mission leader and Deputy Director General of the Swiss nuclear regulator (ENSI). 'The staff were open and candid in their discussions and provided the fullest practicable assistance', he commented. The main observations of the IRRS Review team included the following: SSM operates as an independent regulator in an open and transparent manner with well-organized regulatory processes; SSM is receptive to feedback and strives to maintain a culture of continuous learning; and Following the TEPCO Fukushima Daiichi accident, SSM responded promptly to public demand for information and communicated effectively with the national government, the public and other interested parties. Good practices identified by the IRRS team included, though they are not limited to, the following: The consolidation of the two previous national regulatory authorities into SSM was successful; Overall, SSM's management system is comprehensive and contributes to staff efficiency and effectiveness; The nuclear power plant refurbishment programme as required by SSM enhanced safety; and Sweden's regulatory framework for high-level waste disposal is comprehensive and technically sound. The IRRS Review team identified

The double nuclear system is a new object of nuclear physics studies

International Nuclear Information System (INIS)

Volkov, V.V.

1980-01-01

Deep inelastic collisions of two complex nuclei result in formation of the specific nuclear complex - a double nuclear system which is a new unit of nuclear microworld. In this paper we consider the conditions under which the double nuclear system is formed, its properties, the statistical regularities of its disintegration, and the nuclear shell structure effect on its evolution. The possibility of using deep inelastic transfer reactions to produce nuclear far from the region of β-stability and nuclei with high angular momentum is discussed. (author)

The system of nuclear material control of Kazakhstan

International Nuclear Information System (INIS)

Yeligbayeva, G.Zh.

2001-01-01

Full text: The State system for nuclear material control consists of three integral components. The efficiency of each is to guarantee the non-proliferation regime in Kazakhstan. The components are the following: accounting, export and import control and physical protection of nuclear materials. First, the implementation of the goals of accounting and control bring into force, by the organization of the system for accounting and measurement of nuclear materials to determine present quantity. Organizing the accounting for nuclear material at facilities will ensure the efficiency of accountancy and reporting information. This defines the effectiveness of the state system for the accounting for the Kazakhstan's nuclear materials. Currently, Kazakhstan's nuclear material is fully safeguarded in designated secure locations. Kazakhstan has a nuclear power plant, 4 research reactors and a fuel fabrication plant. The governmental information system for nuclear materials control consist of two level: Governmental level - KAEA collects reports from facilities and prepares the reports for International Atomic Energy Agency, keeping of supporting documents and other necessary information, a data base of export and import, a data base of nuclear material inventory. Facility level - registration and processing information from key measurement points, formation the facility's nuclear materials accounting database. All facilities have computerized systems. Currently, all facilities are safeguarded under IAEA safeguarding standards, through IAEA inspections. Annually, IAEA verifies all nuclear materials at all Kazakhstan nuclear facilities. The government reporting system discloses the existence of all nuclear material and its transfer intended for interaction through the export control system and the nuclear control accounting system. Nuclear material export is regulated by the regulations of the Nuclear Export Control Law. The standard operating procedure is the primary means for

Study of reactor Brayton power systems for nuclear electric spacecraft

Science.gov (United States)

1979-01-01

The feasibility of using Brayton power systems for nuclear electric spacecraft was investigated. The primary performance parameters of systems mass and radiator area were determined for systems from 100 to 1000 kW sub e. Mathematical models of all system components were used to determine masses and volumes. Two completely independent systems provide propulsion power so that no single-point failure can jeopardize a mission. The waste heat radiators utilize armored heat pipes to limit meteorite puncture. The armor thickness was statistically determined to achieve the required probability of survival. A 400 kW sub e reference system received primary attention as required by the contract. The components of this system were defined and a conceptual layout was developed with encouraging results. An arrangement with redundant Brayton power systems having a 1500 K (2240 F) turbine inlet temperature was shown to be compatible with the dimensions of the space shuttle orbiter payload bay.

TOSHIBA CAE system for nuclear power plant

International Nuclear Information System (INIS)

Machiba, Hiroshi; Sasaki, Norio

1990-01-01

TOSHIBA aims to secure safety, increase reliability and improve efficiency through the engineering for nuclear power plant using Computer Aided Engineering (CAE). TOSHIBA CAE system for nuclear power plant consists of numbers of sub-systems which had been integrated centering around the Nuclear Power Plant Engineering Data Base (PDBMS) and covers all stage of engineering for nuclear power plant from project management, design, manufacturing, construction to operating plant service and preventive maintenance as it were 'Plant Life-Cycle CAE System'. In recent years, TOSHIBA has been devoting to extend the system for integrated intelligent CAE system with state-of-the-art computer technologies such as computer graphics and artificial intelligence. This paper shows the outline of CAE system for nuclear power plant in TOSHIBA. (author)

Continuous monitoring system for environmental {gamma} radiation near nuclear facility

Energy Technology Data Exchange (ETDEWEB)

Hua, Jin; Qingyu, Yue; Wenhai, Wang [Academia Sinica, Beijing, BJ (China). Inst. of Atomic Energy

1996-06-01

The continuous monitoring system which is used for the environmental routine and accident emergency {gamma} radiation monitoring near nuclear facility is described. The continuous monitoring system consists of a high pressurized ionization chamber, integrated weak current amplifier, V/F converter and intelligent data recorder. The data gained by recorder can be transmitted to a PC through a standard RS-232-C interface for the data handling and graph plotting. This continuous monitoring system has the functions of alarm over threshold and recorded output signal of detector and temperature. The measuring range is from 10 nGy{center_dot}h{sup -1} to 10 mGy{center_dot}h{sup -1} because a high insulation switch atomically changed measuring ranges is used. The monitoring system has been operating continuously for a long time with high stability and reliability. (5 figs., 2 tabs.).

Continuous monitoring system for environmental γ radiation near nuclear facility

International Nuclear Information System (INIS)

Jin Hua; Yue Qingyu; Wang Wenhai

1996-06-01

The continuous monitoring system which is used for the environmental routine and accident emergency γ radiation monitoring near nuclear facility is described. The continuous monitoring system consists of a high pressurized ionization chamber, integrated weak current amplifier, V/F converter and intelligent data recorder. The data gained by recorder can be transmitted to a PC through a standard RS-232-C interface for the data handling and graph plotting. This continuous monitoring system has the functions of alarm over threshold and recorded output signal of detector and temperature. The measuring range is from 10 nGy·h -1 to 10 mGy·h -1 because a high insulation switch atomically changed measuring ranges is used. The monitoring system has been operating continuously for a long time with high stability and reliability. (5 figs., 2 tabs.)

Theoretical hyperfine structures of 19F i and 17O i

Science.gov (United States)

Aourir, Nouria; Nemouchi, Messaoud; Godefroid, Michel; Jönsson, Per

2018-03-01

Multiconfiguration Hartree-Fock (MCHF) and multiconfiguration Dirac-Hartree-Fock (MCDHF) calculations are performed for the 2 p5P2o , 2 p4(3P ) 3 s 4P , 2 p4(3P ) 3 s 2P , and 2 p4(3P ) 3 p 4So states of 19F i to determine their hyperfine constants. Several computing strategies are considered to investigate electron correlation and relativistic effects. High-order correlation contributions are included in MCHF calculations based on single and double multireference expansions. The largest components of the single reference MCHF wave functions are selected to define the multireference (MR) sets. In this scheme, relativistic corrections are evaluated in the Breit-Pauli approximation. A similar strategy is used for the calculation of MCDHF relativistic wave functions and hyperfine parameters. While correlation and relativistic corrections are found to be rather small for the ground state, we highlight large relativistic effects on the hyperfine constant A3 /2 of 2 p4(3P ) 3 p 4So and, to a lesser extent, on A1 /2 of 2 p4(3P ) 3 s 4P . As expected for such a light system, electron correlation effects dominate over relativity in the calculation of the hyperfine interaction of all other levels considered. We also revisit the hyperfine constants of 2 p3(4S ) 3 s S5o and 2 p3(4S ) 3 p 5P in 17O using similar strategies. The results are found to be in excellent agreement with experiment.

Nuclear Structure References (NSR) file

International Nuclear Information System (INIS)

Ewbank, W.B.

1978-08-01

The use of the Nuclear Structure References file by the Nuclear Data Project at ORNL is described. Much of the report concerns format information of interest only to those preparing input to the system or otherwise needing detailed knowledge of its internal structure. 17 figures

T-x projections of phase diagrams of the MeF-BeF2 systems

International Nuclear Information System (INIS)

Korenev, Yu.M.; Rykov, A.N.; Novoselova, A.V.

1976-01-01

The T-x projections of the state diagrams of the systems MeF-BeF 2 (Me=Li-Rb) have been plotted. Transformation of P-x cross sections of the system state diagrams with decreasing temperature have been considered with the aid, of the general view of T-x projections. The nature of sublimation of the compounds formed in these systems is discussed

Automated synthesis of the estrogen receptors imaging agent 18F-FES

International Nuclear Information System (INIS)

Guo Shen; Chen Guobao; Dai Hongfeng; Lin Meifu; Chen Wenxin

2011-01-01

Objective: 18 F-16α-17β-fluoroestradiol ( 18 F-FES), an estrogen receptors imaging agent, is synthesized with Tracerlab FX FN system. Methods: 18 F-FES is obtained by two steps reactions, including the nucleophilic displacement reaction of no-carrier-added 18 F-fluoride with 3-O-methoxymethyl-16, 17-O-sulfuryl-16-epiesteriol, then the intermediate is evaporated and hydrolyzed with HCI and finally gives 18 F-FES. Results: The synthesis of 18 F-FES can be completed in about 80 min.The radiochemical yield and radio-chemical purity are about 10% and 95% respectively. Conclusion: The procedure of synthesis is simple and automatical. 18 F-FES has an extremely low toxicity, which suggests that 18 F-FES may be a safe, a nd effective estrogen receptors imaging agent. (authors)

Safe and peaceful use of nuclear energy - an IAEA perspective. Address. Deutsche Gesellschaft fuer Auswaertige Politik, Bonn, 17 April 1998

International Nuclear Information System (INIS)

ElBaradei, M.

1998-01-01

The document reproduces the text of the conference given by the Director General of the IAEA at the Deutsche Gesellschaft fuer Auswaertige Politik in Bonn on 17 April 1998. After a presentation of the Agency's role in the safe and peaceful use of nuclear energy, the conference gives an overview of the main issues facing nuclear energy in the following three major areas: the contribution of nuclear energy to economic and social development, nuclear safety, and verification. In the last part, the Director General makes some comments about the future

Preinspection of nuclear power plant systems

International Nuclear Information System (INIS)

1975-01-01

The general plans of the systems affecting the safety of the nuclear power plants are accepted by the Institute of Radiation Protection (IRP) on the basis of the preinspection of the systems. This is the prerequisite of the preinspection of the structures and components belonging to these systems. Exceptionally, when separately agreed, the IRP may perform the preinspection of a separate structure or component, although the preinspection documentation of the whole system, e.g. the nuclear heat generating system, has not been accepted. This guide applies to the nuclear power plant systems that have been defined to be preinspected in the classification document accepted by the IRP

International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings

International Nuclear Information System (INIS)

1984-06-01

This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held October 17 through November 4, 1983, at Santa Fe and Los Alamos, New Mexico and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a State system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1983 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, the Battelle Pacific Northwest Laboratory, Westinghouse Fast Flux Test Facility Visitor Center, and Washington Public Power System nuclear reactor facilities in Richland, Washington. Individual presentations were indexed for inclusion in the Energy Data Base

Pluto/Charon exploration utilizing a bi-modal PBR nuclear propulsion/power system

Science.gov (United States)

Venetoklis, Peter S.

1995-01-01

The paper describes a Pluto/Charon orbiter utilizing a bi-modal nuclear propulsion and power system based on the Particle Bed Reactor. The orbiter is sized for launch to Nuclear-Safe orbit atop a Titan IV or equivalent launch veicle. The bi-modal system provides thermal propulsion for Earth orbital departure and Pluto orbital capture, and 10 kWe of electric power for payload functions and for in-system maneuvering with ion thrusters. Ion thrusters are used to perform inclination changes about Pluto, a transfer from low Pluto orbit to low Charon orbit, and inclination changes about charon. A nominal payload can be deliverd in as little as 15 years, 1000 kg in 17 years, and close to 2000 kg in 20 years. Scientific return is enormously aided by the availability of up to 10 kWe, due to greater data transfer rates and more/better instruments. The bi-modal system can provide power at Pluto/Charon for 10 or more years, enabling an extremely robust, scientifically rewarding, and cost-effective exploration mission.

17 CFR 239.34 - Form F-4, for registration of securities of foreign private issuers issued in certain business...

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 2 2010-04-01 2010-04-01 false Form F-4, for registration of securities of foreign private issuers issued in certain business combination transactions. 239.34 Section 239.34 Commodity and Securities Exchanges SECURITIES AND EXCHANGE COMMISSION FORMS PRESCRIBED UNDER THE...

Basic Research Needs for Advanced Nuclear Systems. Report of the Basic Energy Sciences Workshop on Basic Research Needs for Advanced Nuclear Energy Systems, July 31-August 3, 2006

Energy Technology Data Exchange (ETDEWEB)

Roberto, J.; Diaz de la Rubia, T.; Gibala, R.; Zinkle, S.; Miller, J.R.; Pimblott, S.; Burns, C.; Raymond, K.; Grimes, R.; Pasamehmetoglu, K.; Clark, S.; Ewing, R.; Wagner, A.; Yip, S.; Buchanan, M.; Crabtree, G.; Hemminger, J.; Poate, J.; Miller, J.C.; Edelstein, N.; Fitzsimmons, T.; Gruzalski, G.; Michaels, G.; Morss, L.; Peters, M.; Talamini, K.

2006-10-01

-ray sources, neutron sources, nanoscale science research centers, and supercomputers, offer the opportunity to transform and accelerate the fundamental materials and chemical sciences that underpin technology development for advanced nuclear energy systems. The fundamental challenge is to understand and control chemical and physical phenomena in multi-component systems from femto-seconds to millennia, at temperatures to 1000?C, and for radiation doses to hundreds of displacements per atom (dpa). This is a scientific challenge of enormous proportions, with broad implications in the materials science and chemistry of complex systems. New understanding is required for microstructural evolution and phase stability under relevant chemical and physical conditions, chemistry and structural evolution at interfaces, chemical behavior of actinide and fission-product solutions, and nuclear and thermomechanical phenomena in fuels and waste forms. First-principles approaches are needed to describe f-electron systems, design molecules for separations, and explain materials failure mechanisms. Nanoscale synthesis and characterization methods are needed to understand and design materials and interfaces with radiation, temperature, and corrosion resistance. Dynamical measurements are required to understand fundamental physical and chemical phenomena. New multiscale approaches are needed to integrate this knowledge into accurate models of relevant phenomena and complex systems across multiple length and time scales.

Basic Research Needs for Advanced Nuclear Systems. Report of the Basic Energy Sciences Workshop on Basic Research Needs for Advanced Nuclear Energy Systems, July 31-August 3, 2006

International Nuclear Information System (INIS)

Roberto, J.; Diaz de la Rubia, T.; Gibala, R.; Zinkle, S.; Miller, J.R.; Pimblott, S.; Burns, C.; Raymond, K.; Grimes, R.; Pasamehmetoglu, K.; Clark, S.; Ewing, R.; Wagner, A.; Yip, S.; Buchanan, M.; Crabtree, G.; Hemminger, J.; Poate, J.; Miller, J.C.; Edelstein, N.; Fitzsimmons, T.; Gruzalski, G.; Michaels, G.; Morss, L.; Peters, M.; Talamini, K.

2006-01-01

-ray sources, neutron sources, nanoscale science research centers, and supercomputers, offer the opportunity to transform and accelerate the fundamental materials and chemical sciences that underpin technology development for advanced nuclear energy systems. The fundamental challenge is to understand and control chemical and physical phenomena in multi-component systems from femto-seconds to millennia, at temperatures to 1000?C, and for radiation doses to hundreds of displacements per atom (dpa). This is a scientific challenge of enormous proportions, with broad implications in the materials science and chemistry of complex systems. New understanding is required for microstructural evolution and phase stability under relevant chemical and physical conditions, chemistry and structural evolution at interfaces, chemical behavior of actinide and fission-product solutions, and nuclear and thermomechanical phenomena in fuels and waste forms. First-principles approaches are needed to describe f-electron systems, design molecules for separations, and explain materials failure mechanisms. Nanoscale synthesis and characterization methods are needed to understand and design materials and interfaces with radiation, temperature, and corrosion resistance. Dynamical measurements are required to understand fundamental physical and chemical phenomena. New multiscale approaches are needed to integrate this knowledge into accurate models of relevant phenomena and complex systems across multiple length and time scales

78 FR 38739 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

Science.gov (United States)

2013-06-27

... Systems for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance... Guide (RG) 5.29, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants... material control and accounting. This guide applies to all nuclear power plants. ADDRESSES: Please refer to...

Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol. 11, No. 1--Vol. 17, No. 6

International Nuclear Information System (INIS)

Cottrell, W.B.; Klein, A.

1977-01-01

This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970), through Vol. 17, No. 6 (Nov.-Dec. 1976). The index includes a chronological list of articles (including abstract) followed by KWIC and Author Indexes. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 350 technical articles in the last six years of publication

Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol. 11, No. 1--Vol. 17, No. 6

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W.B.; Klein, A.

1977-02-23

This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970), through Vol. 17, No. 6 (Nov.-Dec. 1976). The index includes a chronological list of articles (including abstract) followed by KWIC and Author Indexes. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 350 technical articles in the last six years of publication.

DIMCO. A new system for mechanical and bidimensional, of nuclear fuel pins; DIMCO un nuevo sistema de calculo mecanico de combustibles nucleares

Energy Technology Data Exchange (ETDEWEB)

Moreno, A

1977-07-01

The system developed in JEN, for: the mechanical analysis uni and bidimensional, of nuclear fuels is presented. The mathematical and numerical foundations used, are here described. And so the models developed for effects such as swelling, cracking, clad growth etc. Numerical results for several cases are presented. a) Numerical test in one and two dimensions. b) Applicability range, c) Interaction effects. d) Influence of the power history. (Author) 17 refs.

2006 annual nuclear technology conference Aachen

International Nuclear Information System (INIS)

Anon.

2006-01-01

This year's ANNUAL NUCLEAR TECHNOLOGY CONFERENCE (JK) was organized in Aachen by the Deutsches Atomforum e.V. (DAtF) and the Kerntechnische Gesellschaft e.V. (KTG). The attendance by more than 1,200 participants from 17 nations underlines the role of this specialized congress as one of the leading events in the field of nuclear power use. For several years in a row, the number of participants has been increasing steadily. The first conference day offered plenary presentations traditionally dealing mainly with political and economic issues of the use of nuclear power, including a presentation by the President of the DAtF. The lead countries of JK 2006 were Belgium and Finland with contributions to the plenary day and special meetings on selected topics. The traditional proven scheme of the three-day meeting offered plenary sessions on the first day, and technical sessions, topical sessions, poster sessions, and special events on the following days. The 'Nuclear Power Campus' was run most successfully for the fourth time, presenting to high school students and university freshmen the world of nuclear power in a transparent way. The special commitment to the young generation was stressed at JK 2006 also by the 'Competence Preservation in Nuclear Technology' workshop. Nearly 2 dozen young scientists used the forum to present results of their work. The meeting was accompanied by a technical exhibition with meeting points established by vendors, suppliers, and service providers. (orig.)

Deformation mechanism in LiF single crystals at 1.7 to 330 K

International Nuclear Information System (INIS)

Niaz, S.; Butt, M.Z.

1999-01-01

The experimental data appertaining to the influence of temperature on the critical resolved shear stress (CRSS) of LiF ionic single crystals containing 10/sup -3/ wt% of divalent metal impurities in the range 1.7 to 330 K have been analyzed within the framework of the kink-pair nucleation (KPN) model of plastic flow in crystalline materials. The CRSS-T data when plotted in log-linear coordinates exhibit three distinct regions represented by straight lines of different slopes. In the temperature range 1.7 to 90 K, the CRSS 6 determined primarily by the stress-assisted thermally-activated escape of screw dislocations trapped in the Peierls troughs. At temperatures between 90 and 260 K, the rate process of plastic deformation is unpinning of edge-dislocation segments from short was rows of randomly dispersed point defects, e.g. residual metal impurities atoms, divalent metal ion-vacancy dipoles, induced defects formed during the pre-yield stage etc. 4. However, at higher temperatures up to 330 K, the CRSS decreases rapidly with rise in temperature, probably due to the mobility of the point defects referred to, and the KPN model becomes inapplicable. (author)

Nuclear energy an introduction to the concepts, systems, and applications of nuclear processes

CERN Document Server

Murray, Raymond L; Murphy, Arthur T; Rosenthal, Daniel I

1987-01-01

Nuclear Energy: An Introduction to the Concepts, Systems, and Applications of Nuclear Processes introduces the reader to the concepts, systems, and applications of nuclear processes. It provides a factual description of basic nuclear phenomena, as well as devices and processes that involve nuclear reactions. The problems and opportunities that are inherent in a nuclear age are also highlighted.Comprised of 27 chapters, this book begins with an overview of fundamental facts and principles, with emphasis on energy and states of matter, atoms and nuclei, and nuclear reactions. Radioactivi

Development of a generic, computerized nuclear material accountability system: NucMAS

International Nuclear Information System (INIS)

Cornell, M.D.; O'Leary, J.M.

1987-01-01

The application NucMAS provides basic computerized accountability functions for the Savannah River Plant (SRP) Separations Department Material Balance Areas (MBA's). These functions include data entry, data management, calculations, and report generation. NucMAS can be used both for routine reporting to the SRP central Material Control and Accounting (MC and A) system and for rapid ad hoc queries in emergency situations. The system is designed to work with any process handling one or more of the 17 accountable nuclear materials specified by the Department of Energy (DOE). It relies on user-supplied configuration data to drive data prompts, report headings, data validations, and calculations

Establishment of nuclear data evaluation system (I)

International Nuclear Information System (INIS)

Chang, Jong Hwa; Lee, Chang Kun; Kim, Jeong Do; Kim, Young Sik; Kim, Young Jin; Kim, Hyung Guk; Kil, Chung Sup; Kim, Kang Suk

1994-08-01

Nuclear data is fundamental data for development of new type of nuclear, upgrade of nuclear fuel, treatment of radwaste, research on fusion reactor, radioisotope usage, and nuclear medical therapy. Nuclear data is produced with experiments. However rack of experimental data for thousands of nuclides and various reaction types makes it essential to do statistical evaluation and theoretical interpolation. This study is intended to join international cooperation after establishing domestic basis for nuclear data evaluation work. This project is the first year of five year plan to do followings: 1) Establishment of database system to collect experimental data, 2) Setup of computer assistance system for evaluation work, 3) Verification of established system by test evaluation of selected nuclide reaction. The system has a collection of mass data of nuclides, computer codes for test evaluation of total cross section of 0-16 and collection of EXFOR format data for 0-16. This system will be improved continuously on next years. (Author)

A nuclear insect appears

International Nuclear Information System (INIS)

Shin, Gi Hwal

1989-06-01

This book is dairy of a nuclear insect in A. F. era. It consists of 6 parts, which have fun pictures and titles. The contents are the letter that is sent the Homo sapiens by insect, exodus of nuclear insect F 100 years latter. The time that a nuclear insect is attacked in F 101, the time that a nuclear dinosaur is beat in AF 102, the time that a nuclear insect struggles in AF 104 and the time that a nuclear insect drifts in AF 104.

Integrated nuclear and radiation protection systems

International Nuclear Information System (INIS)

Oprea, I.; Oprea, M.; Stoica, V.; Cerga, V.; Pirvu, V.; Badea, E.

1993-01-01

A multifunctional radiation monitoring equipment, flexible and capable to meet virtually environmental radiation monitoring, activity measurement and computational requirements, for nuclear laboratories has been designed. It can be used as a radiation protection system, for radionuclide measurement in isotope laboratories, nuclear technology, health physics and nuclear medicine, nuclear power stations and nuclear industry. The equipment is able to measure, transmit and record gamma dose rate and isotope activities. Other parameters and functions are optionally available, such as: self-contained alarm level, system self-test, dose integrator, syringe volume calculation for a given dose corrected for decay, calibration factor, 99 Mo assays performing and background subtraction

EPA assessment of fallout in the United States from atmospheric nuclear testing on September 26 and November 17, 1976 by the People's Republic of China

International Nuclear Information System (INIS)

Strong, A.B.; Smith, J.M.; Johnson, R.H. Jr.

1977-08-01

Following the atmospheric nuclear weapons tests by the People's Republic of China on September 26 and November 17, 1976, the Environmental Radiation Ambient Monitoring System (ERAMS) network was fully activated and frequent samples of air particulates, precipitation, and pasteurized milk were collected for several weeks after each event. Population doses for the United States were calculated using the levels of radioactivity measured in these samples. Based on the calculated doses, health effects to the population of the United States were estimated. This report is a summary of EPA's assessment regarding the radiation doses and potential health effects which may be attributed to radioactive fallout from these nuclear weapons tests

Study on interface between nuclear material accounting system and national nuclear forensic library

International Nuclear Information System (INIS)

Jeong, Yonhong; Han, Jae-Jun; Chang, Sunyoung; Shim, Hye-Won; Ahn, Seungho

2016-01-01

The implementation of nuclear forensics requires physical, chemical and radiological characteristics with transport history to unravel properties of seized nuclear materials. For timely assessment provided in the ITWG guideline, development of national response system (e.g., national nuclear forensic library) is strongly recommended. Nuclear material accounting is essential to obtain basic data in the nuclear forensic implementation phase from the perspective of nuclear non-proliferation related to the IAEA Safeguards and nuclear security. In this study, the nuclear material accounting reports were chosen due to its well-established procedure, and reviewed how to efficiently utilize the existing material accounting system to the nuclear forensic implementation phase In conclusion, limits and improvements in implementing the nuclear forensics were discussed. This study reviewed how to utilize the existing material accounting system for implementing nuclear forensics. Concerning item counting facility, nuclear material properties can be obtained based on nuclear material accounting information. Nuclear fuel assembly data being reported for the IAEA Safeguards can be utilized as unique identifier within the back-end fuel cycle. Depending upon the compulsory accountability report period, there exist time gaps. If national capabilities ensure that history information within the front-end nuclear fuel cycle is traceable particularly for the bulk handling facility, the entire cycle of national nuclear fuel would be managed in the framework of developing a national nuclear forensic library

Study on interface between nuclear material accounting system and national nuclear forensic library

Energy Technology Data Exchange (ETDEWEB)

Jeong, Yonhong; Han, Jae-Jun; Chang, Sunyoung; Shim, Hye-Won; Ahn, Seungho [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

2016-10-15

The implementation of nuclear forensics requires physical, chemical and radiological characteristics with transport history to unravel properties of seized nuclear materials. For timely assessment provided in the ITWG guideline, development of national response system (e.g., national nuclear forensic library) is strongly recommended. Nuclear material accounting is essential to obtain basic data in the nuclear forensic implementation phase from the perspective of nuclear non-proliferation related to the IAEA Safeguards and nuclear security. In this study, the nuclear material accounting reports were chosen due to its well-established procedure, and reviewed how to efficiently utilize the existing material accounting system to the nuclear forensic implementation phase In conclusion, limits and improvements in implementing the nuclear forensics were discussed. This study reviewed how to utilize the existing material accounting system for implementing nuclear forensics. Concerning item counting facility, nuclear material properties can be obtained based on nuclear material accounting information. Nuclear fuel assembly data being reported for the IAEA Safeguards can be utilized as unique identifier within the back-end fuel cycle. Depending upon the compulsory accountability report period, there exist time gaps. If national capabilities ensure that history information within the front-end nuclear fuel cycle is traceable particularly for the bulk handling facility, the entire cycle of national nuclear fuel would be managed in the framework of developing a national nuclear forensic library.

Nuclear fuel element leak detection system

International Nuclear Information System (INIS)

John, C.D. Jr.

1978-01-01

Disclosed is a leak detection system integral with a wall of a building used to fabricate nuclear fuel elements for detecting radiation leakage from the nuclear fuel elements as the fuel elements exit the building. The leak detecting system comprises a shielded compartment constructed to withstand environmental hazards extending into a similarly constructed building and having sealed doors on both ends along with leak detecting apparatus connected to the compartment. The leak detecting system provides a system for removing a nuclear fuel element from its fabrication building while testing for radiation leaks in the fuel element

Mecánica cuántica y física nuclear

OpenAIRE

Von Meyenn, Karl

1999-01-01

El descubrimiento del electrón y de la radiactividad a principios de nuestro siglo proporcionó los elementos esenciales de dos nuevas disciplinas, la física atómica y la nuclear, que en el curso del tiempo cambiaron esencialmente nuestra concepción del mundo y nuestra forma de vida. A partir del estudio del átomo y de su estructura surgió la teoría cuántica, que junto con generalizaciones apropiadas, configuró el marco en el que se inscribían los dos componentes básicos de la materia, el núcl...

Fuel cycle of nuclear power plants and safeguards system of nuclear weapon nonproliferation

International Nuclear Information System (INIS)

Malek, Z.

1980-10-01

The international safeguard system of nuclear weapon nonproliferation and the IAEA safeguard system are briefly described. In Czechoslovakia, a decree was issued in 1977 governing the accounting for and control of nuclear materials. The contents of the decree are presented. Described are computer processing of accounting data, technical criteria for the safeguard system application, containment and inspection in the IAEA safeguard system. The method is shown of the control of and accounting for nuclear materials in nuclear power plants and in fuel manufacturing, reprocessing and enrichment plants. Nondestructive and destructive methods of nuclear materials analysis are discussed. Nondestructive methods used include gamma spectrometry, neutron techniques, X-ray fluores--cence techniques. (J.P.)

Primary central nervous system lymphoma with lymphomatosis cerebri in an immunocompetent child: MRI and 18F-FDG PET-CT findings.

Science.gov (United States)

Jain, Tarun K; Sharma, Punit; Suman, Sudhir K C; Faizi, Nauroze A; Bal, Chandrasekhar; Kumar, Rakesh

2013-01-01

Primary central nervous system lymphoma (PCNSL) is extremely rare in immunocompetent children. We present the magnetic resonance imaging (MRI) and (18)F-fluorodeoxyglucose ((18)F-FDG) positron emission tomography-computed tomography (PET-CT) findings of such a case in a 14-year old immunocompetent boy. In this patient, PCNSL was associated with lymphomatosis cerebri. Familiarity with the findings of this rare condition will improve the diagnostic confidence of the nuclear radiologist and avoid misdiagnosis. Copyright © 2013 Elsevier España, S.L. and SEMNIM. All rights reserved.

Influence of the composition to the physical properties of NaF-LiF-LaF3 melt liquid systems

Directory of Open Access Journals (Sweden)

L. A. Bulavin

2013-06-01

Full Text Available Influence of the chemical composition of NaF-LiF-LaF3 system on temperature dependence of electrical con-ductivity, viscosity and thermoelectric power has been studied in a wide temperature range between 600 and 1500 К. The obtained results could help in design of the molten salt reactor blanket.

Development of nuclear material accountancy control system

International Nuclear Information System (INIS)

Hirosawa, Naonori; Kashima, Sadamitsu; Akiba, Mitsunori

1992-01-01

PNC is developing a wide area of nuclear fuel cycle. Therefore, much nuclear material with a various form exists at each facility in the Works, and the controls of the inventory changes and the physical inventories of nuclear material are important. Nuclear material accountancy is a basic measure in safeguards system based on Non-Proliferation Treaty (NPT). In the light of such importance of material accountancy, the data base of nuclear material control and the material accountancy report system for all facilities has been developed by using the computer. By this system, accountancy report to STA is being presented certainly and timely. Property management and rapid corresponding to various inquiries can be carried out by the data base system which has free item searching procedure. (author)

Nuclear data evaluation method and evaluation system

International Nuclear Information System (INIS)

Liu Tingjin

1995-01-01

The evaluation methods and Nuclear Data Evaluation System have been developed in China. A new version of the system has been established on Micro-VAX2 computer, which is supported by IAEA under the technology assistance program. The flow chart of Chinese Nuclear Data Evaluation System is shown out. For last ten years, the main efforts have been put on the double differential cross section, covariance data and evaluated data library validation. The developed evaluation method and Chinese Nuclear Data Evaluation System have been widely used at CNDC and in Chinese Nuclear Data Network for CENDL. (1 tab., 15 figs.)

Mercury: The Los Alamos ICF KrF laser system

International Nuclear Information System (INIS)

Czuchlewski, S.J.; York, G.W.; Bigio, I.J.; Brucker, J.; Hanson, D.; Honig, E.M.; Kurnit, N.; Leland, W.; McCown, A.W.; McLeod, J.; Rose, E.; Thomas, S.; Thompson, D.

1993-01-01

The Mercury KrF laser facility at Los Alamos is being built with the benefit of lessons learned from the Aurora system. An increased understanding of KrF laser engineering, and the designed implementation of system flexibility, will permit Mercury to serve as a tested for a variety of advanced KrF technology concepts

The protection system to Brazilian Nuclear Program

International Nuclear Information System (INIS)

Andreuzza, Mario Giussepp Santezzi Bertottelli

1997-01-01

The Sistema de Protecao ao Programa Nuclear Brasileiro-SIPRON (Protection System to Brazilian Nuclear Program) was established in 1980. It is intended to accomplish in only one system, all the actions related to security and protection for Nuclear Facilities in Brazil. The author presents in detail the protection system SIPRON, describing the system structure and organization, the functions and obligations of the system involved main organizations, as well as, the system operation and behaviour during an postulated occurrence of a nuclear emergency. It is also described an Exercise that happened in June of 1997 at the Nuclear Power Plant (NPP) Angra I, after two simulated tests in December of 1996 and April of 1997. The NPP Angra I Emergency Plan Exercise was a good opportunity to test the SIPRON structure and preparedness program. It was verified, included by International Atomic Energy Agency observers, the system involved organizations effectiveness and the procedures efficacy to protect the public and the environmental. Finally, it is shown the SIPRON activities of routine, the system obstacles and the expected future performances. (author)

Ventilation-air conditioner system in nuclear power plant

International Nuclear Information System (INIS)

Kubota, Ryuji; Sugisaki, Toshihiko.

1989-01-01

This invention concerns a ventilation-air conditioner system which enables, upon occurrence of accidents in a nuclear power plant, continuous operation for other adjacent nuclear power plants with no effect of accidents. Air supply system and exhaust system are operated during usual operaiton. If loss of coolants accidents should occur in an adjacent nuclear power plants, operation is switched from ventilation operaiton to the operation of re-cycling system based on an AND logic of three signals, that is, a pressure HIGH signal for the reactor container, a water level LOW signal for the reactor and a radioactivity signal of the ventilation-air conditioner sytem on the side of air supply in the nuclear power plant. Thus, nuclear reactor buildings of the nuclear power plant are from the external atmosphere. Therefore, the radioactivity HIGH signal for switching to the emergency air conditioner system of the nuclear power plant is not actuated due to the loss of coolant accidents in the adjacent nuclear power plant. In addition, since the atmospheric temperature in the nuclear reactor building can be maintained by a cooling device disposed to the recycling system, reactor shutdown can be prevented. (I.S.)

Study on HVAC system in nuclear facility

International Nuclear Information System (INIS)

Baeg, S. Y.; Song, W. S.; Oh, Y. O.; Ju, Y. S.; Hong, K. P.

2003-01-01

Heating, Ventilation and Air Conditioning (HVAC) system in nuclear facility should be equipped and constructed more stable and allowable than that in common facility. The purpose of HVAC system is the maintenance of optimum working environment, the protection of worker against a contaminated air and the prevention of atmospheric contamination due to an outward ventilation, etc.. The basic scheme of a safety operation of nuclear facility is to prevent the atmospheric contamination even in low level. The adaptability of HVAC system which is in operation. In this study, the design requirements of HVAC system in nuclear facility and the HVAC systems in foreign countries are reviewed, and the results can be utilized in the design of HVAC system in nuclear facility

Nuclear security and challenges at nuclear power plants. Part 1. Basis of nuclear security

International Nuclear Information System (INIS)

Demachi, Kazuyuki

2017-01-01

The tsunami that occurred in March 2011 associated with the 2011 off the Pacific coast of Tohoku Earthquake hit TEPCO Fukushima Daiichi Nuclear Power Station (1F). The 1F got into station blackout situation, and fell into reactor core meltdown due to inability of cooling down the reactor, eventually leading to the emission accident of radioactive substances over a wide range into the atmosphere, soil, seawater and the like. Through various media such as newspapers, TVs, and the Internet after the accident, important facilities for safety were explained with illustrations. Some of them included the contents that can suggest the causes that trigger the same accident as the 1F accident. It is an urgent task to strengthen security against the terrorism aimed at nuclear power facilities including nuclear power plants, and its realization is a serious problem in each country. This paper summarized nuclear security issues and solutions including explanation on the circumstances of the threat increase of nuclear terrorism that had begun before the 1F accident. The recent nuclear security summit reaffirmed that nuclear security is the basic responsibility of each country, and also reaffirmed the responsibility and importance of IAEA for international cooperation. This paper explains the definition of nuclear security, threat of terrorism, and the contents of the IAEA Nuclear Security Series (NSS), and points out that NSS is considered as the basis among basis that all the countries should share. (A.O.)

Critical enrichment and critical density of infinite systems for nuclear criticality safety evaluation

International Nuclear Information System (INIS)

Naito, Yoshitaka; Koyama, Takashi; Komuro, Yuichi

1986-03-01

Critical enrichment and critical density of homogenous infinite systems, such as U-H 2 O, UO 2 -H 2 O, UO 2 F 2 aqueous solution, UO 2 (NO 3 ) 2 aqueous solution, Pu-H 2 O, PuO 2 -H 2 O, Pu(NO 3 ) 4 aqueous solution and PuO 2 ·UO 2 -H 2 O, were calculated with the criticality safety evaluation computer code system JACS for nuclear criticality safety evaluation on fuel facilities. The computed results were compared with the data described in European and American criticality handbooks and showed good agreement with each other. (author)

International Nuclear Information System in Malaysia

International Nuclear Information System (INIS)

Samsurdin Ahamad

1984-01-01

Practice of the International Nuclear Information System (INIS) in Malaysia is reviewed. The Nuclear Energy Unit, a participating representative of Malaysia, holds the responsibilities of disseminating information through this system. Its available services relevant to the aims of INIS are discussed

17 CFR 240.17i-4 - Internal risk management control system requirements for supervised investment bank holding...

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Internal risk management... Supervised Investment Bank Holding Company Rules § 240.17i-4 Internal risk management control system...) As part of its internal risk management control system, a supervised investment bank holding company...

Modernizing computerized nuclear material accounting systems

International Nuclear Information System (INIS)

Erkkila, B.H.; Claborn, J.

1995-01-01

DOE Orders and draft orders for nuclear material control and accountability address a complete material control and accountability (MC and A) program for all DOE contractors processing, using, or storing nuclear materials. A critical element of an MC and A program is the accounting system used to track and record all inventories of nuclear material and movements of materials in those inventories. Most DOE facilities use computerized accounting systems to facilitate the task of accounting for all their inventory of nuclear materials. Many facilities still use a mixture of a manual paper system with a computerized system. Also, facilities may use multiple systems to support information needed for MC and A. For real-time accounting it is desirable to implement a single integrated data base management system for a variety of users. In addition to accountability needs, waste management, material management, and production operations must be supported. Information in these systems can also support criticality safety and other safety issues. Modern networked microcomputers provide extensive processing and reporting capabilities that single mainframe computer systems struggle with. This paper describes an approach being developed at Los Alamos to address these problems

Law no. 6.453 of 17th October, 1977 on civil liability for nuclear damage and criminal responsibility for acts relating to nuclear activities, and other provisions

International Nuclear Information System (INIS)

1977-01-01

This Act was published on 17 october 1977. Under the Act the operator of a nuclear installation is exclusively liable regardless of fault for compensation of nuclear damage due to a nuclear incident. This exclusive liability is limited to an amount equal to 1,500,000 Treasury Bonds and the operator must take out the maintain insurance or other financial security to cover his liability. The Federative Government will guarantee, up to the prescribed limit, payment of compensation for nuclear damage where it is acknowledged that the operator's liability is involved. As regards apportionment of compensation, persons are granted priority over property. This Act is original in that it contains provisions on criminal liability with penalties ranging from two to ten years imprisonment

Virtual-Reality training system for nuclear security

International Nuclear Information System (INIS)

Nonaka, Nobuyuki

2012-01-01

At the Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency, the virtual reality (VR) training system is under development for providing a practical training environment to implement experience-oriented and interactive lessons on nuclear security for wide range of participants in human resource development assistance program mainly to Asian emerging nuclear-power countries. This system electrically recreates and visualizes nuclear facilities and training conditions in stereoscopic (3D) view on a large-scale display (CAVE system) as virtual reality training facility (VR facility) and it provides training participants with effective environments to learn installation and layout of security equipment in the facility testing and verifying visually the protection performances under various situations such as changes in day-night lighting and weather conditions, which may lead to practical exercise in the design and evaluation of the physical protection system. This paper introduces basic concept of the system and outline of training programs as well as featured aspects in using the VR technology for the nuclear security. (author)

Nuclear power project management information system

International Nuclear Information System (INIS)

Zou Lailong; Zhang Peng; Xiao Ziyan; Chun Zengjun; Huang Futong

2001-01-01

Project Management Information System is an important infrastructure facility for the construction and operation of Nuclear Power Station. Based on the practice of Lingao nuclear power project management information system (NPMIS), the author describes the NPMIS design goals, system architecture and software functionality, points out the outline issues during the development and deployment of NPMIS

Constraining f(R) gravity in solar system, cosmology and binary pulsar systems

Science.gov (United States)

Liu, Tan; Zhang, Xing; Zhao, Wen

2018-02-01

The f (R) gravity can be cast into the form of a scalar-tensor theory, and scalar degree of freedom can be suppressed in high-density regions by the chameleon mechanism. In this article, for the general f (R) gravity, using a scalar-tensor representation with the chameleon mechanism, we calculate the parametrized post-Newtonian parameters γ and β, the effective gravitational constant Geff, and the effective cosmological constant Λeff. In addition, for the general f (R) gravity, we also calculate the rate of orbital period decay of the binary system due to gravitational radiation. Then we apply these results to specific f (R) models (Hu-Sawicki model, Tsujikawa model and Starobinsky model) and derive the constraints on the model parameters by combining the observations in solar system, cosmological scales and the binary systems.

Analysis of task-evoked systemic interference in fNIRS measurements: insights from fMRI.

Science.gov (United States)

Erdoğan, Sinem B; Yücel, Meryem A; Akın, Ata

2014-02-15

Functional near infrared spectroscopy (fNIRS) is a promising method for monitoring cerebral hemodynamics with a wide range of clinical applications. fNIRS signals are contaminated with systemic physiological interferences from both the brain and superficial tissues, resulting in a poor estimation of the task related neuronal activation. In this study, we use the anatomical resolution of functional magnetic resonance imaging (fMRI) to extract scalp and brain vascular signals separately and construct an optically weighted spatial average of the fMRI blood oxygen level-dependent (BOLD) signal for characterizing the scalp signal contribution to fNIRS measurements. We introduce an extended superficial signal regression (ESSR) method for canceling physiology-based systemic interference where the effects of cerebral and superficial systemic interference are treated separately. We apply and validate our method on the optically weighted BOLD signals, which are obtained by projecting the fMRI image onto optical measurement space by use of the optical forward problem. The performance of ESSR method in removing physiological artifacts is compared to i) a global signal regression (GSR) method and ii) a superficial signal regression (SSR) method. The retrieved signals from each method are compared with the neural signals that represent the 'ground truth' brain activation cleaned from cerebral systemic fluctuations. We report significant improvements in the recovery of task induced neural activation with the ESSR method when compared to the other two methods as reflected in the Pearson R(2) coefficient and mean square error (MSE) metrics (two tailed paired t-tests, pnoise (CNR) improvement (60%). Our findings suggest that, during a cognitive task i) superficial scalp signal contribution to fNIRS signals varies significantly among different regions on the forehead and ii) using an average scalp measurement together with a local measure of superficial hemodynamics better accounts

Nuclear-fueled circulatory support systems

Energy Technology Data Exchange (ETDEWEB)

Norman, J C [Texas Heart Inst. (USA)

1975-08-01

Experiments on calves using two types of systems for nuclear left ventricular assist pumps are described. These two systems use a nuclear heat source containing 120 g, 1600 Ci Pu-238 in the form of plutonium oxide. The heat source for the first system is the tidal regenerator engine with no valve or seal and is controlled using a hall effect displacement sensor. The second left ventricular assist system uses heat generated by nuclear decay for producing high gas pressure which is converted into a high hydraulic pressure for pumping. The engine efficiency amounts to 7 to 16%, and the measurement value of the pump efficiency obtained is 85%. How these two systems are synchronized with the left ventricle of vital body is described. IN a transplant experiment for a short period (175 hours) in the initial stage, the possibility of the present method was demonstrated. A long-term performance experiment and improvement of the systems are anticipated. However, there still remain many problems, such as improvement of efficiency, reliability, and performance and diminution of the size.

Understanding Nuclear Safety Culture: A Systemic Approach

International Nuclear Information System (INIS)

Afghan, A.N.

2016-01-01

The Fukushima accident was a systemic failure (Report by Director General IAEA on the Fukushima Daiichi Accident). Systemic failure is a failure at system level unlike the currently understood notion which regards it as the failure of component and equipment. Systemic failures are due to the interdependence, complexity and unpredictability within systems and that is why these systems are called complex adaptive systems (CAS), in which “attractors” play an important role. If we want to understand the systemic failures we need to understand CAS and the role of these attractors. The intent of this paper is to identify some typical attractors (including stakeholders) and their role within complex adaptive system. Attractors can be stakeholders, individuals, processes, rules and regulations, SOPs etc., towards which other agents and individuals are attracted. This paper will try to identify attractors in nuclear safety culture and influence of their assumptions on safety culture behavior by taking examples from nuclear industry in Pakistan. For example, if the nuclear regulator is an attractor within nuclear safety culture CAS then how basic assumptions of nuclear plant operators and shift in-charges about “regulator” affect their own safety behavior?

Systems integration processes for space nuclear electric propulsion systems

International Nuclear Information System (INIS)

Olsen, C.S.; Rice, J.W.; Stanley, M.L.

1991-01-01

The various components and subsystems that comprise a nuclear electric propulsion system should be developed and integrated so that each functions ideally and so that each is properly integrated with the other components and subsystems in the optimum way. This paper discusses how processes similar to those used in the development and intergration of the subsystems that comprise the Multimegawatt Space Nuclear Power System concepts can be and are being efficiently and effectively utilized for these purposes. The processes discussed include the development of functional and operational requirements at the system and subsystem level; the assessment of individual nuclear power supply and thruster concepts and their associated technologies; the conduct of systems integration efforts including the evaluation of the mission benefits for each system; the identification and resolution of concepts development, technology development, and systems integration feasibility issues; subsystem, system, and technology development and integration; and ground and flight subsystem and integrated system testing

Integrated engineering system for nuclear facilities building

International Nuclear Information System (INIS)

Tomura, H.; Miyamoto, A.; Futami, F.; Yasuda, S.; Ohtomo, T.

1995-01-01

In the construction of buildings for nuclear facilities in Japan, construction companies are generally in charge of the building engineering work, coordinating with plant engineering. An integrated system for buildings (PROMOTE: PROductive MOdeling system for Total nuclear Engineering) described here is a building engineering system including the entire life cycle of buildings for nuclear facilities. A Three-dimensional (3D) building model (PRO-model) is to be in the core of the system (PROMOTE). Data sharing in the PROMOTE is also done with plant engineering systems. By providing these basic technical foundations, PROMOTE is oriented toward offering rational, highquality engineering for the projects. The aim of the system is to provide a technical foundation in building engineering. This paper discusses the characteristics of buildings for nuclear facilities and the outline of the PROMOTE. (author)

Why nuclear geostorage systems for petroleum?

Energy Technology Data Exchange (ETDEWEB)

Harst, L van der; Knutson, C F [CER Geonuclear Corporation, Las Vegas, Nevada (United States)

1970-05-15

The objective of any kind of storage system in general is to act as a buffer between cyclical changes in supply and demand of the stored commodities. Since the advent of nuclear explosives engineering the possibility of constructing large-scale underground storage systems by means of contained nuclear explosions, for which the name nuclear geostorage has been coined, should be regarded as a valid alternative to the conventional storage systems currently in existence. Limiting this discussion to systems for storing crude oil, various options are available. The choice of any particular storage method depends, of course, on the circumstances surrounding each particular storage requirement; however, in many cases and for a variety of reasons, nuclear geostorage can be preferable to conventional solutions. Economic considerations are clearly among the most important ones. In this respect an increase in storage capacity will tend to favor the nuclear approach. Besides the economics, however, other considerations are important and may in some cases swing the balance in favor of nuclear geostorage plants, for instance: safety and strategic values, aesthetics, ease of access, lack of suitable tank farm space or lack of suitable geologic conditions for natural reservoirs. It should be borne in mind that the decision to use the nuclear approach to solve a storage problem can only be taken after satisfactory evaluation of the geological and geographical characteristics of the site, and when the technical, safety, political, and public relations factors can be handled adequately. (author)

Why nuclear geostorage systems for petroleum?

International Nuclear Information System (INIS)

Harst, L. van der; Knutson, C.F.

1970-01-01

The objective of any kind of storage system in general is to act as a buffer between cyclical changes in supply and demand of the stored commodities. Since the advent of nuclear explosives engineering the possibility of constructing large-scale underground storage systems by means of contained nuclear explosions, for which the name nuclear geostorage has been coined, should be regarded as a valid alternative to the conventional storage systems currently in existence. Limiting this discussion to systems for storing crude oil, various options are available. The choice of any particular storage method depends, of course, on the circumstances surrounding each particular storage requirement; however, in many cases and for a variety of reasons, nuclear geostorage can be preferable to conventional solutions. Economic considerations are clearly among the most important ones. In this respect an increase in storage capacity will tend to favor the nuclear approach. Besides the economics, however, other considerations are important and may in some cases swing the balance in favor of nuclear geostorage plants, for instance: safety and strategic values, aesthetics, ease of access, lack of suitable tank farm space or lack of suitable geologic conditions for natural reservoirs. It should be borne in mind that the decision to use the nuclear approach to solve a storage problem can only be taken after satisfactory evaluation of the geological and geographical characteristics of the site, and when the technical, safety, political, and public relations factors can be handled adequately. (author)

The system K2NbF7-K2TiF6-KCl

International Nuclear Information System (INIS)

Kamenskaya, L.A.; Matveev, A.M.

1984-01-01

Using visual-polythermal and thermographical methods the ternary system K 2 NbF 7 -K 2 TiE 6 -KCl has been studied. Crystallization fields of initial components and the field of solid solutions of double compounds K 3 NbClF 7 and K 3 TiClF 6 are outlined. Ternary eutectics at 654 deg C, having the composition K 2 NbF 6 -41, K 2 TiP 6 -41, KCl-18 mol.%, is determined. Potassium fluoroniobate and fluorotitanate form continuous solid solutions unstable in the presence of the third component, potassium chloride

International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings

Energy Technology Data Exchange (ETDEWEB)

1984-06-01

This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held October 17 through November 4, 1983, at Santa Fe and Los Alamos, New Mexico and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a State system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1983 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, the Battelle Pacific Northwest Laboratory, Westinghouse Fast Flux Test Facility Visitor Center, and Washington Public Power System nuclear reactor facilities in Richland, Washington. Individual presentations were indexed for inclusion in the Energy Data Base.

International Nuclear Information System. 1988-2002. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2002-08-01

This catalogue lists all sales publications and products of the International Atomic Energy Agency dealing with the International Nuclear Information System (INIS), and issued during the period 1 January 1990 - 31 July 2002. Most publications are issued in English, though some are also available in other languages. This is noted as E for English, F for French, G for German, R for Russian and S for Spanish before the relevant ISBN number. Some INIS Reference Series publications are available in electronic form from the INIS Clearinghouse. For more details on the INIS publications programme, please visit the INIS web site mentioned above

Economic principles of optimizing mixed nuclear and non-nuclear electricity systems

International Nuclear Information System (INIS)

Gouni, L.

1984-01-01

In this chapter, an attempt will be made to show how and why, viewed from the economic angle, nuclear energy and electricity systems supplement each other, since the former requires large size facilities, and the latter provide already existing networks for the supply of all users. Consequently, it is primarily through the electric vector that the rational development of the nuclear industry may be ensured. Section 2.1 sets forth the essential rules for economic calculation. In Section 2.2 we discuss the competitive factors among final-use forms of energy in regard to utilization, and we attempt to show how nuclear energy transmitted through electricity systems may meet such terms. Finally, Section 2.3 deals with, and specifies the characteristics of, electricity systems based on nuclear energy and, in particular, the rates to which they lead. (author)

Constraining f(R gravity in solar system, cosmology and binary pulsar systems

Directory of Open Access Journals (Sweden)

Tan Liu

2018-02-01

Full Text Available The f(R gravity can be cast into the form of a scalar–tensor theory, and scalar degree of freedom can be suppressed in high-density regions by the chameleon mechanism. In this article, for the general f(R gravity, using a scalar–tensor representation with the chameleon mechanism, we calculate the parametrized post-Newtonian parameters γ and β, the effective gravitational constant Geff, and the effective cosmological constant Λeff. In addition, for the general f(R gravity, we also calculate the rate of orbital period decay of the binary system due to gravitational radiation. Then we apply these results to specific f(R models (Hu–Sawicki model, Tsujikawa model and Starobinsky model and derive the constraints on the model parameters by combining the observations in solar system, cosmological scales and the binary systems.

Nuclear technologies for local energy systems

International Nuclear Information System (INIS)

McDonnell, F.N.; Lynch, G.F.

1990-03-01

If nuclear energy is to realize its full potential as a safe and cost-effective alternative to fossil fuels, applications beyond those that are currently being serviced by large, central nuclear power stations must be identified and appropriate reactors developed. The Canadian program on reactor systems for local energy supply is at the forefront of these developments. This program emphasizes design simplicity, low power density and fuel rating, reliance on natural processes, passive systems, and reduced reliance on operator action. The first product, the SLOWPOKE Energy System, is a 10 MW heat source specifically designed to provide hot water to satisfy the needs of local heating systems for building complexes, institutions and municipal district heating systems. A demonstration heating reactor has been constructed at the Whiteshell Nuclear Research Establishment in Manitoba and has been undergoing an extensive test program since first operation in 1987 July. Based on the knowledge learned from the design, construction, licensing and operational testing of this facility, the design of the 10 MW commercial-size unit is well advanced, and Atomic Energy of Canada Limited is prepared to commit the construction of the first commercial unit. Although the technical demonstration of the concept is important, it is recognized that another crucial element is the public and regulatory acceptance of small nuclear systems in urban areas. The decision by a community to commit the construction of a SLOWPOKE Energy System brings to a sharp focus the current public apprehension about nuclear technologies

A state-of-the-art report on international nuclear information system

International Nuclear Information System (INIS)

Lee, Sung Ho; Keum, Jong Yong

1997-02-01

INIS (International Nuclear Information System) established in 1969 by IAEA, is the world's leading information system for the peaceful uses of nuclear energy in collaboration with its 98 member states and 17 international organizations. As a member state, Korea has participated in the INIS activities from the beginning of INIS establishment. The technical information department of KAERI plays the role of the National Center of the Republic of Korea. The purpose of this study is to prepare the method for the activation of domestic INIS operation. To accomplish the purpose, we investigated and analyzed the status of INIS, domestic INIS activities, and the recent INIS projects. Especially some projects are expected to influence domestic INIS activities deeply in the near future. The analyzed results show that for better INIS activities in Korea, we need to review politically and technically on the methods to amplify the rate of the INIS input, to construct and manage the INIS local host, and to use the source documents on CD-ROMs. (author). 24 refs., 6 tabs., 6 figs

NCIS: a nuclear criticality information system

International Nuclear Information System (INIS)

Koponen, B.L.; Hampel, V.E.

1984-01-01

The NCIS is one of the developments carried out to meet the requirements in the field of criticality safety information. Its primary goal is to enhance nuclear criticality safety by dissemination of data, standards, and training material. This paper presents the ''NCIS'' progess since 1950: computer-searching, database management, nuclear critical experiments bibliography. American Nuclear Society transactions criticality safety publications compilation, edition of a personnel directory representing over 140 organizations located in 16 countries and showing a wide range of specialists involved in the field of nuclear criticality safety. The NCIS uses the information management and communication resources of TIS (Technology Information System): automated access procedures; creation of program-dependent information systems; communications. The NCIS is still in a growing, formative stage; it has concentrated first on collecting and organizing the nuclear criticality literature; nuclear critical data, calculational tools, standards, and training materials will follow. Finally the planned and contemplated resources are dealt with: expansion of bibliographic compilations; news database; fundamental criticality safety reference; criticality benchmarck database; user community; training resources; related resources; criticality accident database; dynamic databook; dynamic textbook; expert knowledge system; and, extraction of intelligence

Development of a common nuclear group constants library system: JSSTDL-295n-104γ based on JENDL-3 nuclear data library

International Nuclear Information System (INIS)

Hasegawa, A.

1992-01-01

JSSTDL 295n-104γ: A common group cross-section library system has been developed in JAERI to be used in fairly wide range of applications in nuclear industry. This system is composed of a common 295n-104γ group cross-section library based on JENDL-3 nuclear data file and its utility codes. Target of this system is focused to the criticality or shielding calculations in fast and fusion reactors using ANISN, DOT, or MORSE code. Specifications of the common group constants were decided responding to the request from various nuclear data users, particularly from nuclear design group in Japan. Group structure is decided so as to cover almost all group structures currently used in our country. This library includes self-shielding factor tables for primary reactions. A routine for generating macro-scopic cross-section using the self-shielding factor table is also provided. Neutron cross-sections and photon production cross-sections are processed by Prof. GROUCH-G/B code system and γ ray transport cross-sections are generated by GAMLEG-JR. In this paper, outline and present status of the JSSTDL library system is described along with two examples adopted in JENDL-3 benchmark test. One is for shielding calculation, where effects of self-shielding factor (f-table) is shown in conjunction with the analysis of the ASPIS natural iron deep penetration experiment. Without considering resonance self-shielding effect in resonance energy region for resonant nuclides like iron, the results is completely missled in the attenuation profile calculation in the shields. The other example is fast rector criticality calculations of very small critical assemblies with very high enrichment fuel materials where some basic characteristics of this library is presented. (orig.)

Software Quality Assurance for Nuclear Safety Systems

International Nuclear Information System (INIS)

Sparkman, D R; Lagdon, R

2004-01-01

The US Department of Energy has undertaken an initiative to improve the quality of software used to design and operate their nuclear facilities across the United States. One aspect of this initiative is to revise or create new directives and guides associated with quality practices for the safety software in its nuclear facilities. Safety software includes the safety structures, systems, and components software and firmware, support software and design and analysis software used to ensure the safety of the facility. DOE nuclear facilities are unique when compared to commercial nuclear or other industrial activities in terms of the types and quantities of hazards that must be controlled to protect workers, public and the environment. Because of these differences, DOE must develop an approach to software quality assurance that ensures appropriate risk mitigation by developing a framework of requirements that accomplishes the following goals: (sm b ullet) Ensures the software processes developed to address nuclear safety in design, operation, construction and maintenance of its facilities are safe (sm b ullet) Considers the larger system that uses the software and its impacts (sm b ullet) Ensures that the software failures do not create unsafe conditions Software designers for nuclear systems and processes must reduce risks in software applications by incorporating processes that recognize, detect, and mitigate software failure in safety related systems. It must also ensure that fail safe modes and component testing are incorporated into software design. For nuclear facilities, the consideration of risk is not necessarily sufficient to ensure safety. Systematic evaluation, independent verification and system safety analysis must be considered for software design, implementation, and operation. The software industry primarily uses risk analysis to determine the appropriate level of rigor applied to software practices. This risk-based approach distinguishes safety

A study on optimization of the nuclear safety system

International Nuclear Information System (INIS)

Lee, Sang Hoon; Koh, Byung Joon; Kim, Jin Soo; Kim, Byoung Do; Cho, Seong Won; Kwon, Seog Kwon; Choi, Kwang Sik

1986-12-01

The number of nuclear facilities (nuclear power plants, research reactors, nuclear fuel facilities) under construction or in operation in Korea continues to increase and this has brought about increased importance and concerns toward nuclear safety in Korea. Also, domestic nuclear related organizations are increasingly carrying out the design/construction of nuclear power plants and the development /supply of nuclear fuels. In order to flexibly respond to these changes and to suggest direction to take, it is necessary to re-examine the current nuclear safety regulation system. This study is carried out in two stages and this report describes the results of the analysis and the assessment of the nuclear licencing system of such foreign countries as sweden and German, as the first of the two. In this regard, this study includes the analysis on the backgrounds on the choice of nuclear licensing system, the analysis on the licensing procedures, the analysis on the safety inspection system and the enforcement laws, the analysis on the structure and function of the regulatory, business and research organizations as well as the analysis on the relationship between the safety research and the regulatory duties. In this study, the German safety inspection system and the enforcement procedures and the Swedish nuclear licensing system are analyzed in detail. By comparing and assessing the finding with the current Korea Nuclear Licensing System, this study points out some reform measures of the Korean system that needs to improved. With the changing situations in mind, this study aims to develop the nuclear safety regulation system optimized for Korean situation by re-examining the current regulation system. (Author)

Recent space nuclear power systems

International Nuclear Information System (INIS)

Takizuka, Takakazu; Yasuda, Hideshi; Hishida, Makoto

1991-01-01

For the advance of mankind into the space, the power sources of large output are indispensable, and it has been considered that atomic energy is promising as compared with solar energy and others. Accordingly in USA and USSR, the development of the nuclear power generation systems for space use has been carried out since considerable years ago. In this report, the general features of space nuclear reactors are shown, and by taking the system for the SP-100 project being carried out in USA as the example, the contents of the recent design regarding the safety as an important factor are discussed. Moreover, as the examples of utilizing space nuclear reactors, the concepts of the power source for the base on the moon, the sources of propulsive power for the rockets used for Mars exploration and others, the remote power transmission system by laser in the space and so on are explained. In September, 1988, the launching of a space shuttle of USA was resumed, and the Jupiter explorer 'Galileo' and the space telescope 'Hubble' were successfully launched. The space station 'Mir' of USSR has been used since February, 1986. The history of the development of the nuclear power generation systems for space use is described. (K.I.)

Scottish Nuclear's information systems strategy

International Nuclear Information System (INIS)

Inglis, P.

1991-01-01

Scottish Nuclear, the company which has owned and operated Scotland's nuclear power generating capacity since privatization, inherited a substantial amount of computer hardware and software from its predecessor, the South of Scotland Electricity Board. Each of the two power stations, Torness and Hunterston, were using Digital Vax clusters as the Scottish Nuclear company was formed. This had a major influence on the information systems strategy which has subsequently been adopted. (UK)

The F-SCAN system of foot pressure analysis.

Science.gov (United States)

Young, C R

1993-07-01

The age of computerized gait analysis is here. There are several systems available to meet the needs of the podiatric practitioner. This author believes that the F-SCAN technology system makes a significant contribution to the practice of podiatric medicine. The system is user friendly, accurate, reproducible, and affordable. Its graphic display capabilities are colorfully attractive and easily understood. The primary focus of the F-SCAN system is that of peak pressure distribution over time. Vertical plantar pressure dispersion across the plantar surface of the foot is recorded, processed, and graphically displayed in terms of sequential gait changes. The system further allows for the manipulation of the accumulated data to present it in a more comprehensive manner. Future updates on the F-SCAN software are already close at hand and are expected to enhance the diagnostic capabilities of the system further. The four primary areas of clinical application for F-SCAN have been identified and briefly discussed. The recognition of certain biomechanical abnormalities, monitoring preorthotic and postorthotic use, evaluation of the diabetic or neuropathic foot, and presurgical and postsurgical functional examinations constitute this group. The F-SCAN system largely helps to remove some of the unavoidable guess work from essential diagnostic and therapeutic procedures. As we increase our understanding of the pathomechanics of these clinical problems, so too will we improve our management of the associated complications. Years ago, at the time when computerized gait analysis was being introduced to the podiatric profession, a frequently asked question was: What does it tell me that I don't already know or can't see by watching the patient walk?(ABSTRACT TRUNCATED AT 250 WORDS)

Expert system for nuclear power plant feedwater system diagnosis

International Nuclear Information System (INIS)

Meguro, R.; Kinoshita, Y.; Sato, T.; Yokota, Y.; Yokota, M.

1987-01-01

The Expert System for Nuclear Power Plant Feedwater System Diagnosis has been developed to assist maintenance engineers in nuclear power plants. This system adopts the latest process computer TOSBAC G8050 and the expert system developing tool TDES2, and has a large scale knowledge base which consists of the expert knowledge and experience of engineers in many fields. The man-machine system, which has been developed exclusively for diagnosis, improves the man-machine interface and realizes the graphic displays of diagnostic process and path, stores diagnostic results and searches past reference

An approach to a self-consistent nuclear energy system

International Nuclear Information System (INIS)

Fujii-e, Yoichi; Arie, Kazuo; Endo, Hiroshi

1992-01-01

A nuclear energy system should provide a stable supply of energy without endangering the environment or humans. If there is fear about exhausting world energy resources, accumulating radionuclides, and nuclear reactor safety, tension is created in human society. Nuclear energy systems of the future should be able to eliminate fear from people's minds. In other words, the whole system, including the nuclear fuel cycle, should be self-consistent. This is the ultimate goal of nuclear energy. If it can be realized, public acceptance of nuclear energy will increase significantly. In a self-consistent nuclear energy system, misunderstandings between experts on nuclear energy and the public should be minimized. The way to achieve this goal is to explain using simple logic. This paper proposes specific targets for self-consistent nuclear energy systems and shows that the fast breeder reactor (FBR) lies on the route to attaining the final goal

The national nuclear material tracking system. A Korea's countermeasure against nuclear terrorism

Energy Technology Data Exchange (ETDEWEB)

Moon, Joo Hyun [Dongguk Univ., Gyeongbuk (Korea, Republic of)

2011-07-15

Since nuclear terrorism has been identified as a real threat, the Korean government has earnestly developed elementary technologies and sub-systems for establishing an integrated defensive system against nuclear terrorism, which is based on the concept of defense-in-depth. This paper introduces the gist and implications of the studies that have been conducted in building the national nuclear material tracking system for preventing and intercepting the illicit trafficking and transporting of nuclear material in Korea. (orig.)

Quatenary Na//F, Cl, CO3, MoO4 system

International Nuclear Information System (INIS)

Kochkarov, Zh.A.; Lok''yaeva, S.M.; Shurdumov, G.K.; Gasanaliev, A.M.; Trunin, A.S.

1999-01-01

Perspective in applied respect quatenary system (NaF) 2 -(NaCl)-Na 2 CO 3 -Na 2 MoO 4 being element of narrowing of more complex six-membered mutual Na//F, Cl, CO 3 , MoO 4 (WO 4 ) system is investigated by differential thermal analysis with the use of projection-thermographic method for the first time. Crystallization tree of Na//F, Cl, CO 3 , MoO 4 system is established. It is shown that this system by tetrahedrating (NaF) 2 -Na 2 CO 3 -Na 3 ClMoO 4 section is triangulated on two stable system: (NaF) 2 -Na 3 ClMoO 4 -Na 2 CO 3 -(NaCl) 2 and (NaF) 2 -Na 3 ClMoO 4 -Na 2 CO 3 -Na 2 MoO 4 . Phase single units are determined too. Coordinates of desired quatenary nonvariant points are calculated on analytical models of surfaces by mutual crystallization of two phases and are refined by differential thermal analysis [ru

Role of IL-17 Variants in Preeclampsia in Chinese Han Women.

Directory of Open Access Journals (Sweden)

Haiyan Wang

Full Text Available Previous studies have suggested an important role for IL-17, mainly secreted by Th17 cells, in the development of systemic inflammation in preeclampsia (PE. This study therefore investigated the association between genetic variants in IL-17A, IL-17F, and IL-17RA and susceptibility to PE in Chinese Han women. We recruited 1,031 PE patients and 1,298 controls of later pregnant women, and used TaqMan allelic discrimination real-time PCR to genotype the polymorphisms of IL17A rs2275913, IL-17F rs763780, and IL-17RA rs4819554. No significant differences in genotypic or allelic frequencies were found at all three polymorphic sites between PE patients and controls (rs2275913: genotype χ2 = 0.218, p = 0.897 and allele χ2 = 0.157, p = 0.692, OR = 1.024, 95%CI 0.911-1.152; rs763780: genotype χ2 = 1.948, p = 0.377 and allele χ2 = 1.242, p = 0.265, OR = 0.897, 95%CI 0.741-1.086; rs4819554: genotype χ2 = 0.633, p = 0.729 and allele χ2 = 0.115, p = 0.735, OR = 1.020, 95%CI 0.908-1.146. There were also no significant differences in genetic distributions between mild/severe PE or early/late-onset PE and control subgroups. Our data indicate that the genetic variants of rs2275913 in IL-17A, rs763780 in IL-17F, and rs4819554 in IL-17RA may not play a role in the pathogenesis of PE in Chinese Han women. However, these findings should be confirmed in other ethnic populations.

Thermodynamic assessment of the LiF–ThF{sub 4}–PuF{sub 3}–UF{sub 4} system

Energy Technology Data Exchange (ETDEWEB)

Capelli, E. [European Commission, Joint Research Centre, Institute for Transuranium Elements, P.O. Box 2340, 76125 Karlsruhe (Germany); Department of Radiation Science and Technology, Faculty of Applied Physics, Delft University of Technology, Delft 2629JB (Netherlands); Beneš, O., E-mail: ondrej.benes@ec.europa.eu [European Commission, Joint Research Centre, Institute for Transuranium Elements, P.O. Box 2340, 76125 Karlsruhe (Germany); Konings, R.J.M. [European Commission, Joint Research Centre, Institute for Transuranium Elements, P.O. Box 2340, 76125 Karlsruhe (Germany); Department of Radiation Science and Technology, Faculty of Applied Physics, Delft University of Technology, Delft 2629JB (Netherlands)

2015-07-15

The LiF–ThF{sub 4}–PuF{sub 3}–UF{sub 4} system is the reference salt mixture considered for the Molten Salt Fast Reactor (MSFR) concept started with PuF{sub 3}. In order to obtain the complete thermodynamic description of this quaternary system, two binary systems (ThF{sub 4}–PuF{sub 3} and UF{sub 4}–PuF{sub 3}) and two ternary systems (LiF–ThF{sub 4}–PuF{sub 3} and LiF–UF{sub 4}–PuF{sub 3}) have been assessed for the first time. The similarities between CeF{sub 3}/PuF{sub 3} and ThF{sub 4}/UF{sub 4} compounds have been taken into account for the presented optimization as well as in the experimental measurements performed, which have confirmed the temperatures predicted by the model. Moreover, the experimental results and the thermodynamic database developed have been used to identify potential compositions for the MSFR fuel and to evaluate the influence of partial substitution of ThF{sub 4} by UF{sub 4} in the salt.

Performance of the Aurora KrF ICF laser system

International Nuclear Information System (INIS)

Jones, J.E.; Czuchlewski, S.J.; Turner, T.P.; Watt, R.G.; Thomas, S.J.; Netz, D.A.; Tallman, C.R.; Mack, J.M.; Figueira, J.F.

1990-01-01

Because short wavelength lasers are attractive for inertial confinement fusion (ICF), the Department of Energy is sponsoring work at Los Alamos National Laboratory in krypton-fluoride (KrF) laser technology. Aurora is a short-pulse, high-power, KrF laser system. It serves as an end-to-end technology demonstration prototype for large-scale ultraviolet laser systems for short wavelength ICF research. The system employs optical angular multiplexing and serial amplification by electron-beam-driven KrF laser amplifiers. The 1 to 5 ns pulse of the Aurora front end is split into 96 beams which are angularly and temporally multiplexed to produce a 480 ns pulse train for amplification by four KrF laser amplifiers. In the present system configuration half (48) of the amplified pulses are demultiplexed using different optical path lengths and delivered simultaneously to target. This paper discusses how the Aurora laser system has entered the initial operational phase by delivering pulse energies of greater than one kilojoule to target

Future development of nuclear energy systems

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-03-01

Nuclear energy development in Japan has passed about 30 years, and reaches to a step to supply about 35 % of total electric power demand. However, together with globalization of economic and technical development, its future progressing method is required for its new efforts. Among such conditions, when considering a state of future type nuclear energy application, its contribution to further environmental conservation and international cooperation is essential, and it is required for adoption to such requirement how it is made an energy source with excellent economics.The Research Committee on 'Engineering Design on Nuclear Energy Systems' established under recognition in 1998 has been carried out some discussions on present and future status of nuclear energy development. And so forth under participation of outer specialists. Here were summarized on two year's committee actions containing them and viewpoints of nuclear industries, popularization of nuclear system technology, and so forth. (G.K.)

Defense nuclear energy systems selection methodology for civil nuclear power applications

International Nuclear Information System (INIS)

Scarborough, J.C.

1986-01-01

A methodology developed to select a preferred nuclear power system for a US Department of Defense (DOD) application has been used to evaluate preferred nuclear power systems for a remote island community in Southeast Asia. The plant would provide ∼10 MW of electric power, possibly low-temperature process heat for the local community, and would supplement existing island diesel electric capacity. The nuclear power system evaluation procedure was evolved from a disciplined methodology for ranking ten nuclear power designs under joint development by the US Department of Energy (DOE) and DOD. These included six designs proposed by industry for the Secure Military Power Plant Program (now termed Multimegawatt Terrestrial Reactor Program), the SP-100 Program, the North Warning System Program, and the Modular Advanced High-Temperature Gas-Cooled Reactor (HTGR) and Liquid-Metal Reactor (LMR) programs. The 15 evaluation criteria established for the civil application were generally similar to those developed and used for the defense energy systems evaluation, except that the weighting factor applied to each individual criterion differed. The criteria and their weighting (importance) functions for the civil application are described

Certification of U.S. instrumentation in Russian nuclear processing facilities

International Nuclear Information System (INIS)

Powell, D.H.; Sumner, J.N.

2000-01-01

Agreements between the United States (U.S.) and the Russian Federation (R.F.) require the down-blending of highly enriched uranium (HEU) from dismantled Russian Federation nuclear weapons. The Blend Down Monitoring System (BDMS) was jointly developed by the Los Alamos National Laboratory (LANL) and the Oak Ridge National Laboratory (ORNL) to continuously monitor the enrichments and flow rates in the HEU blending operations at the R.F. facilities. A significant requirement of the implementation of the BDMS equipment in R.F. facilities concerned the certification of the BDMS equipment for use in a Russian nuclear facility. This paper discusses the certification of the BDMS for installation in R.F. facilities, and summarizes the lessons learned from the process that can be applied to the installation of other U.S. equipment in Russian nuclear facilities

Remote system for counting of nuclear pulses

International Nuclear Information System (INIS)

Nieves V, J.A.; Garcia H, J.M.; Aguilar B, M.A.

1999-01-01

In this work, it is describe technically the remote system for counting of nuclear pulses, an integral system of the project radiological monitoring in a petroleum distillation tower. The system acquires the counting of incident nuclear particles in a nuclear detector which process this information and send it in serial form, using the RS-485 toward a remote receiver, which can be a Personal computer or any other device capable to interpret the communication protocol. (Author)

17 CFR 239.43 - Form F-N, appointment of agent for service of process by foreign banks and foreign insurance...

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 2 2010-04-01 2010-04-01 false Form F-N, appointment of agent for service of process by foreign banks and foreign insurance companies and certain of their holding... agent for service of process by foreign banks and foreign insurance companies and certain of their...

17 CFR 239.40 - Form F-10, for registration under the Securities Act of 1933 of securities of certain Canadian...

Science.gov (United States)

2010-04-01

...) This Form may not be used for registration of derivative securities except: (1) Warrants, options and... 17 Commodity and Securities Exchanges 2 2010-04-01 2010-04-01 false Form F-10, for registration under the Securities Act of 1933 of securities of certain Canadian issuers. 239.40 Section 239.40...

A contribution to thermoluminescence dosemeter system optimisation applied to environmental monitoring around nuclear power plants

International Nuclear Information System (INIS)

Dies, X.; Ortega, X.; Rosell, J.

1990-01-01

The factors that constitute a thermoluminescence dosimetric system have been studied and optimised, with the intention of defining strategies for improving precision and accuracy of TL dosimetry systems for environmental monitoring. An optimisation technique based on fractional factorial designs permitted a reduction in the number of necessary experiments and clarified interactions between various factors. The model for fading over time showed that TL response in LiF:Mg,Ti dosemeters was independent of time between irradiation and readout, and this was applied to fading corrections in nuclear power plant environmental monitoring. (author)

The regulatory system of nuclear safety in Russia

International Nuclear Information System (INIS)

Mizoguchi, Shuhei

2013-01-01

This article explains what type of mechanism the nuclear system has and how nuclear safety is regulated in Russia. There are two main organizations in this system : ROSATOM and ROSTEKHADZOR. ROSATOM, which was founded in 2007, incorporates all the nuclear industries in Russia, including civil nuclear companies as well as nuclear weapons complex facilities. ROSTEKHNADZOR is the federal body that secures and supervises the safety in using atomic energy. This article also reviews three laws on regulating nuclear safety. (author)

Westinghouse support for Spanish nuclear industry

International Nuclear Information System (INIS)

Rebollo, R.

1999-01-01

One of the major commitments Westinghouse has with the nuclear industry is to provide to the utilities the support necessary to have their nuclear units operating at optimum levels of availability and safety. This article outlines the organization the Energy Systems Business Unit of Westinghouse has in place to fulfill this commitment and describes the evolution of the support Westinghouse is providing to the operation o f the Spanish Nuclear Power plants. (Author)

Westinghouse Small Modular Reactor nuclear steam supply system design

Energy Technology Data Exchange (ETDEWEB)

Memmott, M. J.; Harkness, A. W.; Van Wyk, J. [Westinghouse Electric Company LLC, 600 Cranberry Woods Drive, Cranberry Twp. PA 16066 (United States)

2012-07-01

The Westinghouse Small Modular Reactor (SMR) is an 800 MWt (>225 MWe) integral pressurized water reactor (iPWR), in which all of the components typically associated with the nuclear steam supply system (NSSS) of a nuclear power plant are incorporated within a single reactor pressure vessel. This paper is the first in a series of four papers which describe the design and functionality of the Westinghouse SMR. Also described in this series are the key drivers influencing the design of the Westinghouse SMR and the unique passive safety features of the Westinghouse SMR. Several critical motivators contributed to the development and integration of the Westinghouse SMR design. These design driving motivators dictated the final configuration of the Westinghouse SMR to varying degrees, depending on the specific features under consideration. These design drivers include safety, economics, AP1000{sup R} reactor expertise and experience, research and development requirements, functionality of systems and components, size of the systems and vessels, simplicity of design, and licensing requirements. The Westinghouse SMR NSSS consists of an integral reactor vessel within a compact containment vessel. The core is located in the bottom of the reactor vessel and is composed of 89 modified Westinghouse 17x17 Robust Fuel Assemblies (RFA). These modified fuel assemblies have an active core length of only 2.4 m (8 ft) long, and the entirety of the core is encompassed by a radial reflector. The Westinghouse SMR core operates on a 24 month fuel cycle. The reactor vessel is approximately 24.4 m (80 ft) long and 3.7 m (12 ft) in diameter in order to facilitate standard rail shipping to the site. The reactor vessel houses hot and cold leg channels to facilitate coolant flow, control rod drive mechanisms (CRDM), instrumentation and cabling, an intermediate flange to separate flow and instrumentation and facilitate simpler refueling, a pressurizer, a straight tube, recirculating steam

Containments for consolidated nuclear steam systems

International Nuclear Information System (INIS)

Jabsen, F.S.

1978-01-01

A containment system for a consolidated nuclear steam system incorporating a nuclear core, steam generator and reactor coolant pumps within a single pressure vessel is described which is designed to provide radiation shielding and pressure suppression. Design details, including those for the dry well and wet well of the containment, are given. (UK)

Act No 6453 of 17th October, 1977 on civil liability for nuclear damage and criminal responsibility for acts relating to nuclear activities, and other provisions

International Nuclear Information System (INIS)

1978-01-01

This Act was published on 17 October 1977. It is based to a great extent on the provisions of the Vienna Convention on Civil Liability for Nucler Damage of 21 May 1963. Under the Act the operator of a nuclear installation is exclusively liable regardless of fault for compensation of nuclear damage due to a nuclear incident. This exclusive liability is limited to an amount equal to 1,500,000 Treasury Bonds and the operator must take out and maintain insurance or other financial security to cover his liability. The Federative Government will guarantee, up to the prescribed limit, payment of compensation for nuclear damage where it is acknowledged that the operator's liability is involved. As regards apportionment of compensation, persons are granted priority over property. This Act is original in that it contains provisions on criminal liability with penalties ranging from two to ten years imprisonment. (NEA) [fr

Monte Carlo simulation and theory in Gaussian approximation of a phase transition in the nuclear spin system of a solid

Energy Technology Data Exchange (ETDEWEB)

Merkulov, I A; Papava, Y I; Ponomarenko, V V [Leningradskij Gosudarstvennyj Univ., Leningrad (Russian Federation); Vasiliev, S I [Carleton Univ., Ottawa, ON (Canada). Dept. of Physics

1988-02-01

A phase transition of the nuclear spin system of a solid with dipolar and indirect scalar interactions is considered. Monte Carlo simulations of the spin-system isothermic states and of the adiabatic demagnetization process have been made. The structures and energies of the ground states and the values of the critical temperatures, T[sub C], and minimal polarizations, [rho][sub C], at which adiabatic demagnetization leads to spontaneous spin ordering, calculated for the GaAs and CaF[sub 2] nuclear spin systems, are presented. The results of numerical simulations are compared with the experimental data for CaF[sub 2]. The Weiss-field model is extended to the case of adiabatic demagnetization. The fluctuations of the local field are taken into account in the Gaussian approximation. It is shown that the proposed approach allows one to obtain asymptotically correct results both for T >> T[sub C] and T << T[sub C]. The results of the calculations in the Gaussian approximation are compared with the numerical simulations. (10 refs., 9 figs., tab.).

Development of the Advanced Nuclear Safety Information Management (ANSIM) System

Energy Technology Data Exchange (ETDEWEB)

Sohn, Jae Min; Ko, Young Cheol; Song, Tai Gil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

Korea has become a technically independent nuclear country and has grown into an exporter of nuclear technologies. Thus, nuclear facilities are increasing in significance at KAERI (Korea Atomic Energy Research Institute), and it is time to address the nuclear safety. The importance of nuclear safety cannot be overemphasized. Therefore, a management system is needed urgently to manage the safety of nuclear facilities and to enhance the efficiency of nuclear information. We have established ISP (Information Strategy Planning) for the Integrated Information System of nuclear facility and safety management. The purpose of this paper is to develop a management system for nuclear safety. Therefore, we developed the Advanced Nuclear Safety Information Management system (hereinafter referred to as the 'ANSIM system'). The ANSIM system has been designed and implemented to computerize nuclear safety information for standardization, integration, and sharing in real-time. Figure 1 shows the main home page of the ANSIM system. In this paper, we describe the design requirements, contents, configurations, and utilizations of the ANSIM system

Risk and safety analysis of nuclear systems

National Research Council Canada - National Science Library

Lee, John C; McCormick, Norman J

2011-01-01

...), and failure modes of systems. All of this material is general enough that it could be used in non-nuclear applications, although there is an emphasis placed on the analysis of nuclear systems...

Enhanced nuclear magnetism: some novel features and prospective experiments

International Nuclear Information System (INIS)

Abragam, A.; Bleaney, B.

1983-01-01

It is shown that methods used for studying nuclear magnetism and nuclear magnetic ordering can be extended to 'enhanced nuclear magnetism'. These methods include the use of r.f. fields for adiabatic demagnetization in the rotating frame (a.d.r.f) and beams of neutrons whose spins interact with the nuclear spins. The 'enhancement' of the nuclear moment arises from the electronic magnetization M 1 induced through the hyperfine interaction. It is shown that the spatial distribution of M 1 is the same as that of The Van Vleck magnetization induced by an external field, provided that J is a good quantum number. The spatial distributions are not in general the same in Russell-Saunders coupling, eg. in the 3d group. The Bloch equations are extended to include anisotropic nuclear moments. The 'truncated' spin Hamiltonian is derived for spin-spin interaction between enhanced moments. A general cancellation theorem for second-order processes in spin-lattice relaxation is derived. The interactions of neutrons with the true nuclear moment, the Van Vleck moment, the 'pseudonuclear' moment and the 'pseudomagnetic' nuclear moment are discussed. Ordered states of enhanced nuclear moment systems are considered, together with the conditions under which they might be produced by a.d.r.f. following dynamic nuclear polarization. (U.K.)

Basic study for development of nuclear heat application systems

Energy Technology Data Exchange (ETDEWEB)

Inaba, Yoshitomo; Fumizawa, Motoo; Hishida, Makoto [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

1996-05-01

We need to intensely investigate real possibilities of nuclear heat application systems which exploit high potential of nuclear energy as a promising candidate of the future energy resource in the world. In this report, special interest was placed on coal reforming systems because we thought a compact heat source of nuclear power with a very high energy density might compensate the environmental problem caused by burning a great amount of coal. First, we reviewed state-of-the-art technologies for coal reforming technology with a special attention on coal gasification technologies. Based on these basic data, we proposed several nuclear coal reforming systems and discussed advantages and disadvantages of the systems. We also explored a model with which we could analyze nuclear heat application systems all together. In addition, we investigated possibility and effects of nuclear heat utilization systems producing chemical materials from carbon dioxide in flue gas of fossil fuel power plant. As a result, we showed nuclear heat application systems were useful. (author).

Remote nuclear green pellet processing system

International Nuclear Information System (INIS)

Cellier, Francis.

1980-01-01

An automated system for manufacturing nuclear fuel pellets for use in nuclear fuel elements of nuclear power reactors is described. The system comprises process components arranged vertically but not directly under each other within a single enclosure. The vertical-lateral arrangement provides for gravity flow of the product from one component to the next and for removal of each component without interference with the other components. The single enclosure eliminates time consuming transfer between separate enclosures of each component while providing three-sided access to the component through glove ports. (auth)

Soft systems methodology as a systemic approach to nuclear safety management

International Nuclear Information System (INIS)

Vieira Neto, Antonio S.; Guilhen, Sabine N.; Rubin, Gerson A.; Caldeira Filho, Jose S.; Camargo, Iara M.C.

2017-01-01

Safety approach currently adopted by nuclear installations is built almost exclusively upon analytical methodologies based, mainly, on the belief that the properties of a system, such as its safety, are given by its constituent parts. This approach, however, does not properly address the complex dynamic interactions between technical, human and organizational factors occurring within and outside the organization. After the accident at Fukushima Daiichi nuclear power plant in March 2011, experts of the International Atomic Energy Agency (IAEA) recommended a systemic approach as a complementary perspective to nuclear safety. The aim of this paper is to present an overview of the systems thinking approach and its potential use for structuring socio technical problems involved in the safety of nuclear installations, highlighting the methodologies related to the soft systems thinking, in particular the Soft Systems Methodology (SSM). The implementation of a systemic approach may thus result in a more holistic picture of the system by the complex dynamic interactions between technical, human and organizational factors. (author)

Soft systems methodology as a systemic approach to nuclear safety management

Energy Technology Data Exchange (ETDEWEB)

Vieira Neto, Antonio S.; Guilhen, Sabine N.; Rubin, Gerson A.; Caldeira Filho, Jose S.; Camargo, Iara M.C., E-mail: asvneto@ipen.br, E-mail: snguilhen@ipen.br, E-mail: garubin@ipen.br, E-mail: jscaldeira@ipen.br, E-mail: icamargo@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNE-SP), Sao Paulo, SP (Brazil)

2017-07-01

Safety approach currently adopted by nuclear installations is built almost exclusively upon analytical methodologies based, mainly, on the belief that the properties of a system, such as its safety, are given by its constituent parts. This approach, however, does not properly address the complex dynamic interactions between technical, human and organizational factors occurring within and outside the organization. After the accident at Fukushima Daiichi nuclear power plant in March 2011, experts of the International Atomic Energy Agency (IAEA) recommended a systemic approach as a complementary perspective to nuclear safety. The aim of this paper is to present an overview of the systems thinking approach and its potential use for structuring socio technical problems involved in the safety of nuclear installations, highlighting the methodologies related to the soft systems thinking, in particular the Soft Systems Methodology (SSM). The implementation of a systemic approach may thus result in a more holistic picture of the system by the complex dynamic interactions between technical, human and organizational factors. (author)

[Experimental nuclear physics

International Nuclear Information System (INIS)

1992-01-01

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

Research on nuclear reactor instrumentation system using optical technology. JAERI's nuclear research promotion program, H10-041. Contract research

Energy Technology Data Exchange (ETDEWEB)

Nakazawa, Masaharu; Takahashi, Hiroyuki; Fukuda, Daiji [University of Tokyo, Graduate School of Engineering, Tokyo (Japan)

2002-03-01

To apply optical fiber sensing technique to nuclear measurements, we have irradiated the F-doped optical fiber and experimented with two optical fiber sensors: Raman Distributed Temperature Sensor (RDTS) and Fiber Bragg Grating (FBG). We have irradiated F-doped optical fiber, which has high radiation resistivity, with a 60Co gamma source and fast neutron source reactor YAYOI. Although the radiation induced loss with gamma source showed saturation tendency, the loss with YAYOI showed linear loss increase. RDTS has been installed at YAYOI with the correction techniques. During the continuous measurements more than 1 year, the feasibility of RDTS for remote inspection and surveillance was demonstrated. From the result of irradiation experiments on FBG, FBG has high radiation resistivity for a temperature or strain monitor in nuclear plants. For these results, optical fiber sensing can be expected as nuclear measurements. (author)

Simulation of a Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant

International Nuclear Information System (INIS)

Reis Martins Junior, L.L. dos.

1980-01-01

The following work intends to perform the digital simulation, of the Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant for control systems design and analysis purposes. There are mathematical models for the reactor, the steam generator, the pressurizer and for transport lags of the coolant in the primary circuit. Nevertheless no one control system has been considered to permit any user the inclusion in the more convenient way of the desired control systems' models. The characteristics of the system in consideration are fundamentally equal to the ones of Almirante Alvaro Alberto Nuclear Power Plant, Unit I (Angra I) obtained in the Final Safety Analysis Report at Comissao Nacional de Energia Nuclear. (author)

Process information systems in nuclear reprocessing

International Nuclear Information System (INIS)

Jaeschke, A.; Keller, H.; Orth, H.

1987-01-01

On a production management level, a process information system in a nuclear reprocessing plant (NRP) has to fulfill conventional operating functions and functions for nuclear material surveillance (safeguards). Based on today's state of the art of on-line process control technology, the progress in hardware and software technology allows to introduce more process-specific intelligence into process information systems. Exemplified by an expert-system-aided laboratory management system as component of a NRP process information system, the paper demonstrates that these technologies can be applied already. (DG) [de

European nuclear data studies for fast systems

International Nuclear Information System (INIS)

Rullhusen, P.; Hambsch, F.-J.; Mondelaers, W.; Plompen, A.J.M.; Schillebeeckx, P.

2010-01-01

Nuclear data needs for fast systems are highlighted and the following projects are described: Joint European research projects: MUSE Experiments for Sub-critical Neutronics Validation; High- and Intermediate Energy Nuclear Data for ADS (HINDAS); and the Time-Of-Flight facility for Nuclear Data Measurements for ADS (n T OF N D A DS); European Research Programme for the Transmutation of High Level Nuclear Waste in an Accelerator Driven System (EUROTRANS-NUDATRA); and CANDIDE; Programmes for transnational access to experimental facilities in Europe: European Facilities for Nuclear Data Measurements (EFNUDAT); Neutron Data Measurements at IRMM (NUDAME); European facility for innovative reactor and transmutation neutron data (EUFRAT) (P.A.)

Sensitivity analysis of parameters important to nuclear criticality safety of Castor X/28F spent nuclear fuel cask

Energy Technology Data Exchange (ETDEWEB)

Leotlela, Mosebetsi J. [Witwatersrand Univ., Johannesburg (South Africa). School of Physics; Koeberg Operating Unit, Johannesburg (South Africa). Regulations and Licensing; Malgas, Isaac [Koeberg Nuclear Power Station, Duinefontein (South Africa). Nuclear Engineering Analysis; Taviv, Eugene [ASARA consultants (PTY) LTD, Johannesburg (South Africa)

2015-11-15

In nuclear criticality safety analysis it is essential to ascertain how various components of the nuclear system will perform under certain conditions they may be subjected to, particularly if the components of the system are likely to be affected by environmental factors such as temperature, radiation or material composition. It is therefore prudent that a sensitivity analysis is performed to determine and quantify the response of the output to variation in any of the input parameters. In a fissile system, the output parameter of importance is the k{sub eff}. Therefore, in attempting to prevent reactivity-induced accidents, it is important for the criticality safety analyst to have a quantified degree of response for the neutron multiplication factor to perturbation in a given input parameter. This article will present the results of the perturbation of the parameters that are important to nuclear criticality safety analysis and their respective correlation equations for deriving the sensitivity coefficients.

{sup 18}F-FDG-PET/CT for systemic staging of newly diagnosed triple-negative breast cancer

Energy Technology Data Exchange (ETDEWEB)

Ulaner, Gary A.; Castillo, Raychel; Riedl, Christopher C.; Jochelson, Maxine S. [Memorial Sloan Kettering Cancer Center, Department of Radiology, New York, NY (United States); Weill Cornell Medical College, Department of Radiology, New York, NY (United States); Goldman, Debra A.; Goenen, Mithat [Memorial Sloan Kettering Cancer Center, Department of Epidemiology and Biostatistics, New York, NY (United States); Wills, Jonathan [Memorial Sloan Kettering Cancer Center, Department of Information Systems, New York, NY (United States); Pinker-Domenig, Katja [Memorial Sloan Kettering Cancer Center, Department of Radiology, New York, NY (United States)

2016-10-15

National Comprehensive Cancer Network guidelines recommend {sup 18}F-FDG-PET/CT, in addition to standard staging procedures, for systemic staging of newly diagnosed stage III breast cancer patients. However, factors in addition to stage may influence PET/CT utility. As breast cancers that are negative for estrogen receptor, progesterone receptor, and human epidermal growth factor receptor (triple-negative breast cancer, or TNBC) are more aggressive and metastasize earlier than other breast cancers, we hypothesized that receptor expression may be one such factor. This study assesses {sup 18}F-FDG-PET/CT for systemic staging of newly diagnosed TNBC. In this Institutional Review Board-approved retrospective study, our Healthcare Information System was screened for patients with TNBC who underwent {sup 18}F-FDG-PET/CT in 2007-2013 prior to systemic or radiation therapy. Initial stage was determined from mammography, ultrasound, magnetic resonance imaging, and/or surgery, if performed prior to {sup 18}F-FDG-PET/CT. {sup 18}F-FDG-PET/CT was evaluated to identify unsuspected extra-axillary regional nodal and distant metastases, as well as unsuspected synchronous malignancies. Kaplan Meier survival estimates were calculated for initial stage IIB patients stratified by whether or not stage 4 disease was detected by {sup 18}F-FDG-PET/CT. A total of 232 patients with TNBC met inclusion criteria. {sup 18}F-FDG-PET/CT revealed unsuspected distant metastases in 30 (13 %): 0/23 initial stage I, 4/82 (5 %) stage IIA, 13/87 (15 %) stage IIB, 4/23 (17 %) stage IIIA, 8/14 (57 %) stage IIIB, and 1/3 (33 %) stage IIIC. Twenty-six of 30 patients upstaged to IV by {sup 18}F-FDG-PET/CT were confirmed by pathology, with the remaining four patients confirmed by follow-up imaging. In addition, seven unsuspected synchronous malignancies were identified in six patients. Initial stage 2B patients who were upstaged to 4 by {sup 18}F-FDG-PET/CT had significantly shorter survival compared to

US Army Nuclear Burst Detection System (NBDS)

International Nuclear Information System (INIS)

Glaser, R.F.

1980-07-01

The Nuclear Burst Detection System (NBDS) was developed to meet the Army requirements of an unattended, automatic nuclear burst reporting system. It provides pertinent data for battlefield commanders on a timely basis with high reliability

Electrochemical behaviours of lanthanide fluorides in the electrolysis system with LiF-NaF-Kf salt

International Nuclear Information System (INIS)

Joon-Bo, Shim; Sung-Chan, Hwang; Eung-Ho, Kim; Young-Ho, Kang; Byung-Jik, Lee; Jae-Hyung, Yoo

2003-01-01

As a part of partitioning studies, the experiments of cyclic voltammetry and electrolytic reduction with the liquid bismuth cathode were conducted to investigate electrochemical behaviours of lanthanide elements in the electrorefining system employing LiF-NaF-KF eutectic salt as the electrolyte. The cyclic voltammograms for NdF 3 and GdF 3 were obtained at various potential scan rates, respectively. The cathodic and anodic peak currents of the elements increased in proportion to the square root of the potential scan rate. According to changes of the potential difference between the coupled cathodic and anodic peaks, reversibilities of the reduction-oxidation reactions in this system were evaluated. In addition, further behaviours of electrochemical reaction of the elements were examined through electrolytic tests of the system using liquid bismuth as the cathode at fixed current densities. (author)

Security Engineering FY17 Systems Aware Cybersecurity

Science.gov (United States)

2017-12-07

Security Engineering – FY17 Systems Aware Cybersecurity Technical Report SERC-2017-TR-114 December 7 2017 Principal Investigator: Dr...December 7, 2017 Copyright © 2017 Stevens Institute of Technology, Systems Engineering Research Center The Systems Engineering Research Center (SERC...supported, in whole or in part, by the U.S. Department of Defense through the Office of the Assistant Secretary of Defense for Research and Engineering (ASD

Differential effects of interleukin-17 receptor signaling on innate and adaptive immunity during central nervous system bacterial infection

Directory of Open Access Journals (Sweden)

Vidlak Debbie

2012-06-01

Full Text Available Abstract Although IL-17A (commonly referred to as IL-17 has been implicated in the pathogenesis of central nervous system (CNS autoimmune disease, its role during CNS bacterial infections remains unclear. To evaluate the broader impact of IL-17 family members in the context of CNS infection, we utilized IL-17 receptor (IL-17R knockout (KO mice that lack the ability to respond to IL-17, IL-17F and IL-17E (IL-25. In this article, we demonstrate that IL-17R signaling regulates bacterial clearance as well as natural killer T (NKT cell and gamma-delta (γδ T cell infiltrates during Staphylococcus aureus-induced brain abscess formation. Specifically, when compared with wild-type (WT animals, IL-17R KO mice exhibited elevated bacterial burdens at days 7 and 14 following S. aureus infection. Additionally, IL-17R KO animals displayed elevated neutrophil chemokine production, revealing the ability to compensate for the lack of IL-17R activity. Despite these differences, innate immune cell recruitment into brain abscesses was similar in IL-17R KO and WT mice, whereas IL-17R signaling exerted a greater influence on adaptive immune cell recruitment. In particular, γδ T cell influx was increased in IL-17R KO mice at day 7 post-infection. In addition, NK1.1high infiltrates were absent in brain abscesses of IL-17R KO animals and, surprisingly, were rarely detected in the livers of uninfected IL-17R KO mice. Although IL-17 is a key regulator of neutrophils in other infection models, our data implicate an important role for IL-17R signaling in regulating adaptive immunity during CNS bacterial infection.

Nuclear power experience

International Nuclear Information System (INIS)

1983-01-01

The International Conference on Nuclear Power Experience, organized by the International Atomic Energy Agency, was held at the Hofburg Conference Center, Vienna, Austria, from 13 to 17 September 1982. Almost 1200 participants and observers from 63 countries and 20 organizations attended the conference. The 239 papers presented were grouped under the following seven main topics: planning and development of nuclear power programmes; technical and economic experience of nuclear power production; the nuclear fuel cycle; nuclear safety experience; advanced systems; international safeguards; international co-operation. The proceedings are published in six volumes. The sixth volume contains a complete Contents of Volume 1 to 5, a List of Participants, Authors and Transliteration Indexes, a Subject Index and an Index of Papers by Number

Quality assurance system in nuclear engineering

International Nuclear Information System (INIS)

Adams, H.W.; Hoensch, V.

1985-01-01

Due to the close connection between the German Atomic Energy Law and the nuclear control regulations, quality systems in nuclear engineering have taken on a special form. Quality assurance systems as a stipulated organisation of structure and procedure to assure quality have implications for the organisation of the electric supply company at the planning, erection and commissioning stage and for the organisation of the nuclear power station facility. To supervise the application and effectiveness of the stipulated organisation of structure and procedure internally and externally among contractors, special organisation units have been set up at the plant suppliers, manufactures, electric supply companies and nuclear power station facilities, which in the electric supply field go by the name of Quality Assurance Supervision. (orig.) [de

Approach for Establishing a National Nuclear Forensics System

International Nuclear Information System (INIS)

Kim, Jaekwang; Hyung, Sangcheol

2014-01-01

The increasing number could give rise to posing a potential threat to national infrastructure which is very vulnerable to radiological sabotage with the materials. International community has been emphasizing the importance of nuclear forensics through the Nuclear Security Summit process as a countermeasure against nuclear terrorism. Global Initiative to Combat Nuclear Terrorism(GICNT) and nuclear forensics International Technology Working Group(ITWG) suggest the establishment of national nuclear forensics system which has a law enforcement for forensic management and maintenance of nuclear forensics database including nuclear material and other radioactive materials. We suggest the legal and institutional system through this paper in an effort to set up a multi expert group and the nuclear forensics DB which can contribute to effective Core capabilities

Approach for Establishing a National Nuclear Forensics System

Energy Technology Data Exchange (ETDEWEB)

Kim, Jaekwang; Hyung, Sangcheol [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2014-05-15

The increasing number could give rise to posing a potential threat to national infrastructure which is very vulnerable to radiological sabotage with the materials. International community has been emphasizing the importance of nuclear forensics through the Nuclear Security Summit process as a countermeasure against nuclear terrorism. Global Initiative to Combat Nuclear Terrorism(GICNT) and nuclear forensics International Technology Working Group(ITWG) suggest the establishment of national nuclear forensics system which has a law enforcement for forensic management and maintenance of nuclear forensics database including nuclear material and other radioactive materials. We suggest the legal and institutional system through this paper in an effort to set up a multi expert group and the nuclear forensics DB which can contribute to effective Core capabilities.

Nuclear technology databases and information network systems

International Nuclear Information System (INIS)

Iwata, Shuichi; Kikuchi, Yasuyuki; Minakuchi, Satoshi

1993-01-01

This paper describes the databases related to nuclear (science) technology, and information network. Following contents are collected in this paper: the database developed by JAERI, ENERGY NET, ATOM NET, NUCLEN nuclear information database, INIS, NUclear Code Information Service (NUCLIS), Social Application of Nuclear Technology Accumulation project (SANTA), Nuclear Information Database/Communication System (NICS), reactor materials database, radiation effects database, NucNet European nuclear information database, reactor dismantling database. (J.P.N.)

Nuclear power systems: Their safety

International Nuclear Information System (INIS)

Myers, L.C.

1993-01-01

Mankind utilizes energy in many forms and from a variety of sources. Canada is one of a growing number of countries which have chosen to embrace nuclear-electric generation as a component of their energy systems. As of August 1992 there were 433 power reactors operating in 35 countries and accounting for more than 15% of the world's production of electricity. In 1992, thirteen countries derived at least 25% of their electricity from nuclear units, with France leading at nearly 70%. In the same year, Canada produced about 16% of its electricity from nuclear units. Some 68 power reactors are under construction in 16 countries, enough to expand present generating capacity by close to 20%. No human endeavour carries the guarantee of perfect safety and the question of whether or not nuclear-electric generation represents an 'acceptable' risk to society has long been vigorously debated. Until the events of late April 1986, nuclear safety had indeed been an issue for discussion, for some concern, but not for alarm. The accident at the Chernobyl reactor in the USSR has irrevocably changed all that. This disaster brought the matter of nuclear safety back into the public mind in a dramatic fashion. This paper discusses the issue of safety in complex energy systems and provides brief accounts of some of the most serious reactor accidents which have occurred to date. (author). 7 refs

U.S. national nuclear material control and accounting system

International Nuclear Information System (INIS)

Taylor, S; Terentiev, V G

1998-01-01

Issues related to nuclear material control and accounting and illegal dealing in these materials were discussed at the April 19--20, 1996 Moscow summit meeting (G7 + Russia). The declaration from this meeting reaffirmed that governments are responsible for the safety of all nuclear materials in their possession and for the effectiveness of the national control and accounting system for these materials. The Russian delegation at this meeting stated that ''the creation of a nuclear materials accounting, control, and physical protection system has become a government priority''. Therefore, in order to create a government nuclear material control and accounting system for the Russian Federation, it is critical to study the structure, operating principles, and regulations supporting the control and accounting of nuclear materials in the national systems of nuclear powers. In particular, Russian specialists have a definite interest in learning about the National Nuclear Material Control and Accounting System of the US, which has been operating successfully as an automated system since 1968

Photoemission study of 5f localization in UPd/sub 3-x/(Pt,Rh)/sub x/

International Nuclear Information System (INIS)

Arko, A.J.; Koelling, D.D.; Dunlap, B.D.; Mitchell, A.W.

1987-10-01

Photoemission measurements in the two systems UPd/sub 3-x/(Pt,Rh)/sub x/ show that the 5f spectra are consistent with localized 5f electrons (peak in spectral weight is below E/sub F/ for all x within the double hexagonal DO 24 phase) while at both phase transitions the 5f peaks lock in at E/sub F/ consistent with intinerancy. A satellite 5f peak representative of d-screening is observed in both localized and itinerant systems. 17 refs., 3 figs

Heat transfer and fluid flow in nuclear systems

CERN Document Server

Fenech, Henri

1982-01-01

Heat Transfer and Fluid in Flow Nuclear Systems discusses topics that bridge the gap between the fundamental principles and the designed practices. The book is comprised of six chapters that cover analysis of the predicting thermal-hydraulics performance of large nuclear reactors and associated heat-exchangers or steam generators of various nuclear systems. Chapter 1 tackles the general considerations on thermal design and performance requirements of nuclear reactor cores. The second chapter deals with pressurized subcooled light water systems, and the third chapter covers boiling water reacto

Nuclear criticality information system

International Nuclear Information System (INIS)

Koponen, B.L.; Hampel, V.E.

1981-01-01

The nuclear criticality safety program at LLNL began in the 1950's with a critical measurements program which produced benchmark data until the late 1960's. This same time period saw the rapid development of computer technology useful for both computer modeling of fissile systems and for computer-aided management and display of the computational benchmark data. Database management grew in importance as the amount of information increased and as experimental programs were terminated. Within the criticality safety program at LLNL we began at that time to develop a computer library of benchmark data for validation of computer codes and cross sections. As part of this effort, we prepared a computer-based bibliography of criticality measurements on relatively simple systems. However, it is only now that some of these computer-based resources can be made available to the nuclear criticality safety community at large. This technology transfer is being accomplished by the DOE Technology Information System (TIS), a dedicated, advanced information system. The NCIS database is described

α and p emission before, during, and after fission of the fusion nucleus 169Ta: Nuclear deformation, field emission, and nuclear shadow

International Nuclear Information System (INIS)

Brucker, A.

1986-01-01

In the asymmetric system 318 MeV 28 Si + 141 Pr the angular and energy distributions of α particles and protons were measured in coincidence with fission fragments. Identification and separation of the sources of sequential emission before (CN) and after (F) fission of the compound-nucleus 169 Ta yields following multiplicities: M CN α =0.38±0.04, M CN p =0.6±0.15; M F α =0.16±0.03, M F p =0.54±0.15. Measurement of the cross sections δ ER =(608±81) mb and δ F =(679±159) mb for residual nucleus formation respectively fission fixes the mean angular momentum for fission l F =(94±7)ℎ and the maximal angular momentum l F,max =(110±10)ℎ (sharp cut-off model). From the angular correlation relative to the spin direction of the compound-nucleus an anisotropy parameter of A α =6.7±0.8 and A p =1.3±0.2 for α respectively proton emission from the compound-nucleus is measured, and by means of the semiclassical model of Dossing a quadrupole deformation parameter of the compound-nucleus of vertical strokeδvertical stroke=0.43±0.05 consistent within the uncertainties of the analysis determined. Apart from pre-equilibrium emission under small angles to the beam significant deviations from sequential emission are observed only in the α emission and detailedly studied by means of angular correlation and energy spectra: (I) an strong nuclear shadowing of the fragment emission of 1/7 of its sequential value in a narrow angular range (≅40 0 (FWHM)) in the direction of the detected fission fragment. From this a mean lifetime of the compound nucleus τ CN =(140-240).10 -22 s is obtained. (II) A perpendicularly to the scission axis strongly pronounced surplus M SC α =(1.7±0.4).10 -2 and an observed deficit of equal magnitude in direction of the scission axis. (orig./HSI) [de

Design and evaluation of a pressure sensor for high temperature nuclear application

International Nuclear Information System (INIS)

Yancey, M.E.

1981-11-01

The goal of this technical development task was the development of a small eddy-current pressure sensor for use within a high temperature nuclear environment. The sensor is designed for use at pressures and temperatures of up to 17.23 MPa and 650 0 F. The design of the sensor incorporated features to minimize possible errors due to temperature transients present in nuclear applications. This report describes a prototype pressure sensor that was designed, the associated 100 kHz signal conditioning electronics, and the evaluation tests which were conducted

Nuclear power reactors and hydrogen storage systems

International Nuclear Information System (INIS)

Ibrahim Aly Mahmoud El Osery.

1980-01-01

Among conclusions and results come by, a nuclear-electric-hydrogen integrated power system was suggested as a way to prevent the energy crisis. It was shown that the hydrogen power system using nuclear power as a leading energy resource would hold an advantage in the current international situation as well as for the long-term future. Results reported provide designers of integrated nuclear-electric-hydrogen systems with computation models and routines which will allow them to explore the optimal solution in coupling power reactors to hydrogen producing systems, taking into account the specific characters of hydrogen storage systems. The models were meant for average computers of a type easily available in developing countries. (author)

Advanced physical protection systems for nuclear materials

International Nuclear Information System (INIS)

Jones, O.E.

1976-01-01

Because of the increasing incidence of terrorism, there is growing concern that nuclear materials and facilities need improved physical protection against theft, diversion, or sabotage. Physical protection systems for facilities or transportation which have balanced effectiveness include information systems, access denial systems, adequate and timely response, recovery capability, and use denial methods for despoiling special nuclear materials (SNM). The role of these elements in reducing societal risk is described; however, it is noted that, similar to nuclear war, the absolute risks of nuclear theft and sabotage are basically unquantifiable. Sandia Laboratories has a major US Energy Research and Development Administration (ERDA) role in developing advanced physical protection systems for improving the security of both SNM and facilities. These activities are surveyed in this paper. A computer simulation model is being developed to assess the cost-effectiveness of alternative physical protection systems under various levels of threat. Improved physical protection equipment such as perimeter and interior alarms, secure portals, and fixed and remotely activated barriers is being developed and tested. In addition, complete prototype protection systems are being developed for representative nuclear facilities. An example is shown for a plutonium storage vault. The ERDA safe-secure transportation system for highway shipments of all significant quantities of government-owned SNM is described. Adversary simulation as a tool for testing and evaluating physical protection systems is discussed. Finally, a list of measures is given for assessing overall physical protection system performance. (author)

Advanced physical protection systems for nuclear materials

International Nuclear Information System (INIS)

Jones, O.E.

1975-10-01

Because of the increasing incidence of terrorism, there is growing concern that nuclear materials and facilities need improved physical protection against theft, diversion, or sabotage. Physical protection systems for facilities or transportation which have balanced effectiveness include information systems, access denial systems, adequate and timely response, recovery capability, and use denial methods for despoiling special nuclear materials (SNM). The role of these elements in reducing societal risk is described; however, it is noted that, similar to nuclear war, the absolute risks of nuclear theft and sabotage are basically unquantifiable. Sandia Laboratories has a major Energy Research and Development Administration (ERDA) role in developing advanced physical protection systems for improving the security of both SNM and facilities. These activities are surveyed. A computer simulation model is being developed to assess the cost-effectiveness of alternative physical protection systems under various levels of threat. Improved physical protection equipment such as perimeter and interior alarms, secure portals, and fixed and remotely-activated barriers is being developed and tested. In addition, complete prototype protection systems are being developed for representative nuclear facilities. An example is shown for a plutonium storage vault. The ERDA safe-secure transportation system for highway shipments of all significant quantities of government-owned SNM is described. Adversary simulation as a tool for testing and evaluating physical protection systems is discussed. A list of measures is given for assessing overall physical protection system performance. (auth)

Synthesis of plutonium trifluoride by hydro-fluorination and novel thermodynamic data for the PuF3-LiF system

Science.gov (United States)

Tosolin, A.; Souček, P.; Beneš, O.; Vigier, J.-F.; Luzzi, L.; Konings, R. J. M.

2018-05-01

PuF3 was synthetized by hydro-fluorination of PuO2 and subsequent reduction of the product by hydrogenation. The obtained PuF3 was analysed by X-Ray Diffraction (XRD) and found phase-pure. High purity was also confirmed by the melting point analysis using Differential Scanning Calorimetry (DSC). PuF3 was then used for thermodynamic assessment of the PuF3-LiF system. Phase equilibrium points and enthalpy of fusion of the eutectic composition were measured by DSC. XRD analyses of selected samples after DSC measurement confirm that after solidification from the liquid, the system returns to a mixture of LiF and PuF3.

Extracardiac 18F-florbetapir imaging in patients with systemic amyloidosis: more than hearts and minds.

Science.gov (United States)

Wagner, T; Page, J; Burniston, M; Skillen, A; Ross, J C; Manwani, R; McCool, D; Hawkins, P N; Wechalekar, Ashutosh D

2018-07-01

18 F-Florbetapir has been reported to show cardiac uptake in patients with systemic light-chain amyloidosis (AL). This study systematically assessed uptake of 18 F-florbetapir in patients with proven systemic amyloidosis at sites outside the heart. Seventeen patients with proven cardiac amyloidosis underwent 18 F-florbetapir PET/CT imaging, 15 with AL and 2 with transthyretin amyloidosis (ATTR). Three patients had repeat scans. All patients had protocolized assessment at the UK National Amyloidosis Centre including imaging with 123 I-serum amyloid P component (SAP). 18 F-Florbetapir images were assessed for areas of increased tracer accumulation and time-uptake curves in terms of standardized uptake values (SUV mean ) were produced. All 17 patients showed 18 F-florbetapir uptake at one or more extracardiac sites. Uptake was seen in the spleen in 6 patients (35%; 6 of 9, 67%, with splenic involvement on 123 I-SAP scintigraphy), in the fat in 11 (65%), in the tongue in 8 (47%), in the parotids in 8 (47%), in the masticatory muscles in 7 (41%), in the lungs in 3 (18%), and in the kidney in 2 (12%) on the late half-body images. The 18 F-florbetapir spleen retention index (SRI) was calculated. SRI >0.045 had 100% sensitivity/sensitivity (in relation to 123 I-SAP splenic uptake, the current standard) in detecting splenic amyloid on dynamic imaging and a sensitivity of 66.7% and a specificity of 100% on the late half-body images. Intense lung uptake was seen in three patients, one of whom had lung interstitial infiltration suggestive of amyloid deposition on previous high-resolution CT. Repeat imaging showed a stable appearance in all three patients suggesting no early impact of treatment response. 18 F-Florbetapir PET/CT is a promising tool for the detection of extracardiac sites of amyloid deposition. The combination of uptake in the heart and uptake in the spleen on 18 F-florbetapir PET/CT, a hallmark of AL, suggests that this tracer holds promise as a screening tool

Environmental dosimetry system based on LiF : Mg, Ti (TLD-100)

International Nuclear Information System (INIS)

Saez Vergara, J.C.

1990-01-01

The report presents the various tests carried out to the characterize a thermoluminescence environmental dosimetry systems, using the phosphor LiF:mg,Ti (TLD-100) in chip form. The holder has been specifically designed in order to obtain simplicity in the operation and to assure correct measurements in terms of the new operational quantities in radiation protection (ICRU-1985). Some topics in TLD Environmental Monitoring are discussed (Dark Current, Reference Light, Zero Reading, Free-in-Air or Phantom Calibration, Fading Correction, Transit Dose, etc.), and the proposed solutions are exposed. The tests performed have been designed to conform with the different existing international Standards and Recommendations (ANSI : N545-1975; IEC: Draft 45B-1987, ISO : DP 8034-19849. The data from an European Interlaboratory Programm (EUR-8932) have been used to evaluate the performance : the TLD System presented is among the best systems using TLD-100. The results obtained in the characterization (linearity, repeatability, detection threshold, residue, angular response, stability of stored information, etc.) show the optimum performance of this dosimetric system in its application to environmental gamma dose monitoring. Based on these results, two operational procedures have been developed for the application of this Dosimetric System, specially in Quality Assurance Monitoring Programs around Nuclear Plants in Spain. (author)

Reliability of sprinkler systems. Exploration and analysis of data from nuclear and non-nuclear installations

International Nuclear Information System (INIS)

Roenty, V.; Keski-Rahkonen, O.; Hassinen, J.P.

2004-12-01

Sprinkler systems are an important part of fire safety of nuclear installations. As a part of effort to make fire-PSA of our utilities more quantitative a literature survey from open sources worldwide of available reliability data on sprinkler systems was carried out. Since the result of the survey was rather poor quantitatively, it was decided to mine available original Finnish nuclear and non-nuclear data, since nuclear power plants present a rather small device population. Sprinklers are becoming a key element for the fire safety in modern, open non-nuclear buildings. Therefore, the study included both nuclear power plants and non-nuclear buildings protected by sprinkler installations. Data needed for estimating of reliability of sprinkler systems were collected from available sources in Finnish nuclear and non-nuclear installations. Population sizes on sprinkler system installations and components therein as well as covered floor areas were counted individually from Finnish nuclear power plants. From non-nuclear installations corresponding data were estimated by counting relevant things from drawings of 102 buildings, and plotting from that sample needed probability distributions. The total populations of sprinkler systems and components were compiled based on available direct data and these distributions. From nuclear power plants electronic maintenance reports were obtained, observed failures and other reliability relevant data were selected, classified according to failure severity, and stored on spreadsheets for further analysis. A short summary of failures was made, which was hampered by a small sample size. From non-nuclear buildings inspection statistics from years 1985.1997 were surveyed, and observed failures were classified and stored on spreadsheets. Finally, a reliability model is proposed based on earlier formal work, and failure frequencies obtained by preliminary data analysis of this work. For a model utilising available information in the non-nuclear

Nuclear Fuel Cycle Information System. A directory of nuclear fuel cycle facilities. 2009 ed

International Nuclear Information System (INIS)

2009-04-01

The Nuclear Fuel Cycle Information System (NFCIS) is an international directory of civilian nuclear fuel cycle facilities, published online as part of the Integrated Nuclear Fuel Cycle Information System (iNFCIS: http://www-nfcis.iaea.org/). This is the fourth hardcopy publication in almost 30 years and it represents a snapshot of the NFCIS database as of the end of 2008. Together with the attached CD-ROM, it provides information on 650 civilian nuclear fuel cycle facilities in 53 countries, thus helping to improve the transparency of global nuclear fuel cycle activities

Solar System constraints to general f(R) gravity

International Nuclear Information System (INIS)

Chiba, Takeshi; Smith, Tristan L.; Erickcek, Adrienne L.

2007-01-01

It has been proposed that cosmic acceleration or inflation can be driven by replacing the Einstein-Hilbert action of general relativity with a function f(R) of the Ricci scalar R. Such f(R) gravity theories have been shown to be equivalent to scalar-tensor theories of gravity that are incompatible with Solar System tests of general relativity, as long as the scalar field propagates over Solar System scales. Specifically, the parameterized post-Newtonian (PPN) parameter in the equivalent scalar-tensor theory is γ=1/2, which is far outside the range allowed by observations. In response to a flurry of papers that questioned the equivalence of f(R) theory to scalar-tensor theories, it was recently shown explicitly, without resorting to the scalar-tensor equivalence, that the vacuum field equations for 1/R gravity around a spherically symmetric mass also yield γ=1/2. Here we generalize this analysis to f(R) gravity and enumerate the conditions that, when satisfied by the function f(R), lead to the prediction that γ=1/2

Space nuclear power systems for extraterrestrial basing

International Nuclear Information System (INIS)

Lance, J.R.; Chi, J.W.H.

1989-01-01

Previous studies of nuclear and non-nuclear power systems for lunar bases are compared with recent studies by others. Power levels from tens of kW e for early base operation up to 2000 kW e for a self-sustaining base with a Closed Environment Life Support System (CELSS) are considered. Permanent lunar or Martian bases will require the use of multiple nuclear units connected to loads with a power transmission and distribution system analogous to earth-based electric utility systems. A methodology used for such systems is applied to the lunar base system to examine the effects of adding 100 kW e SP-100 class and/or larger nuclear units when a reliability criterion is imposed. The results show that resource and logistic burdens can be reduced by using 1000 kW e units early in the base growth scenario without compromising system reliability. Therefore, both technologies being developed in two current programs (SP-100 and NERVA Derivative Reactor (NDR) technology for space power) can be used effectively for extraterrestrial base power systems. Recent developments in NDR design that result in major reductions in reactor mass are also described. (author)

Management review of nuclear material control and accounting systems

International Nuclear Information System (INIS)

1975-06-01

Section 70.58, ''Fundamental Nuclear Material Controls,'' of 10 CFR Part 70, ''Special Nuclear Materials,'' requires, in paragraph 70.58(c), that certain licensees authorized to possess more than one effective kilogram of special nuclear material establish a management system to provide for the development, revision, implementation, and enforcement of nuclear material control and accounting procedures. Such a system must provide for a review of the nuclear material control system at least every 12 months. This guide describes the purpose and scope, personnel qualifications, depth of detail, and procedures that are acceptable to the NRC staff for the management review of nuclear material control systems required under paragraph 70.58(c) of 10 CFR Part 70. (U.S.)

Digitizing instrumentation and control systems in nuclear power plants. DAtF autumn meeting Leittec '96, October 8, 1996 in Koenigswinter

International Nuclear Information System (INIS)

Aleite, W.

1997-01-01

Recently, digitization for upgrading and retrofitting of instrumentation and control systems has been extended to German nuclear power plants, and initial action to commence modification started with a very suitable system, the limiters of the Neckar-1 reactor unit of GKN. This action is generally welcomed. Systems of the control room of relevance to safety -even if not belonging to priority classes - are systems for process information for example, or operator guidance, as well as diagnostic systems for inspection and maintenance. (orig./DG) [de

International Collaboration on Spent Fuel Disposition in Crystalline Media: FY17 Progress Report

Energy Technology Data Exchange (ETDEWEB)

Wang, Yifeng [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kainina, Elena [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jove-Colon, Carlos [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-09-01

Active participation in international R&D is crucial for achieving the Spent Fuel Waste Science & Technology (SFWST) long-term goals of conducting “experiments to fill data needs and confirm advanced modeling approaches” and of having a “robust modeling and experimental basis for evaluation of multiple disposal system options” (by 2020). DOE’s Office of Nuclear Energy (NE) has developed a strategic plan to advance cooperation with international partners. The international collaboration on the evaluation of crystalline disposal media at Sandia National Laboratories (SNL) in FY17 focused on the collaboration through the Development of Coupled Models and their Validation against Experiments (DECOVALEX-2019) project. The DECOVALEX project is an international research and model comparison collaboration, initiated in 1992, for advancing the understanding and modeling of coupled thermo-hydro-mechanical-chemical (THMC) processes in geological systems. SNL has been participating in three tasks of the DECOVALEX project: Task A. Modeling gas injection experiments (ENGINEER), Task C. Modeling groundwater recovery experiment in tunnel (GREET), and Task F. Fluid inclusion and movement in the tight rock (FINITO).

Basic research in support of innovative fuels design for the Generation IV systems (F-BRIDGE project)

International Nuclear Information System (INIS)

Valot, Carole; Bertolus, Marjorie; Konings, Rudy; Somers, Joe; Groot, Sander de

2010-01-01

F-BRIDGE (Basic Research in support of Innovative Fuels Design for the GEN IV systems) is a 4-year project which started in 2008. It seeks to bridge the gap between basic research and technological applications for generation IV nuclear reactor systems. One of the challenges for the next generation of reactors is to significantly increase the efficiency in designing innovative fuels. The object of the F-BRIDGE project is to complement the empirical approach by a physically-based description of fuel and cladding materials to enable a rationalization of the design process and a better selection of promising fuel systems. Advanced modelling and separate effects experiments are carried out in order to obtain more exact physical descriptions of ceramic fuels and cladding, at relevant scales from the atomic to the macroscopic scale. Research is also focused on assessing and improving 'sphere-pac' fuel, a composite-ceramics concept which has shown promise. The project activities can be broken down into four main areas: (i) Basic research investigations using a multi-scale approach in both experimentation and modelling to enable the generation of missing basic data, the identification of relevant mechanisms and the development of appropriate models; (ii) Transfer between technological issues and basic research by bringing together within the same project materials scientists, engineers and end-users; (iii) Assessment of the drawbacks and benefits of the sphere-pac fuel application to various Generation IV systems; (iv) Education and training to promote research in the field of fuel materials, to ensure the exchange of results and ideas among the participants and to link the project with other related European or international initiatives. The project relies on the complementary expertise of 19 partners: nuclear and non nuclear research organisations, universities, a nuclear engineering company, as well as technology and project management consultancy small and medium

Consequences of the nuclear energy moratorium as demanded by the F.D.P. central committee

International Nuclear Information System (INIS)

1977-08-01

If the construction of nuclear power plants is to be tied to the first partial construction licence for the Germany reprocessing centre, as the F.D.P. especially demands lately (note: superseded since the Party Congress) then this would lead unavoidably to a 3- to 10-year nuclear energy moratorium with extremely serious consequences for the electricity supply and the employment situation in the FRG. In view of the significance of the impending energy policy decisions, the Deutsches Atomforum urges all those responsible in Bund and Laender, to take these interconnections very seriously. Only by solving the apparent conflict between further nuclear energy expansion and reprocessing, can preconditions be created for the realization of an adequate electricity supply which, at the same time, is not harmful to the environment, without serious consequences for energy and employment policies. The fact that these consequences will not be visible until in the eighties, may not be a reason for postponing decisions which have to be taken now. (orig./HP) [de

Nuclear fuel cycle simulation system (VISTA)

International Nuclear Information System (INIS)

2007-02-01

The Nuclear Fuel Cycle Simulation System (VISTA) is a simulation system which estimates long term nuclear fuel cycle material and service requirements as well as the material arising from the operation of nuclear fuel cycle facilities and nuclear power reactors. The VISTA model needs isotopic composition of spent nuclear fuel in order to make estimations of the material arisings from the nuclear reactor operation. For this purpose, in accordance with the requirements of the VISTA code, a new module called Calculating Actinide Inventory (CAIN) was developed. CAIN is a simple fuel depletion model which requires a small number of input parameters and gives results in a very short time. VISTA has been used internally by the IAEA for the estimation of: spent fuel discharge from the reactors worldwide, Pu accumulation in the discharged spent fuel, minor actinides (MA) accumulation in the spent fuel, and in the high level waste (HLW) since its development. The IAEA decided to disseminate the VISTA tool to Member States using internet capabilities in 2003. The improvement and expansion of the simulation code and the development of the internet version was started in 2004. A website was developed to introduce the simulation system to the visitors providing a simple nuclear material flow calculation tool. This website has been made available to Member States in 2005. The development work for the full internet version is expected to be fully available to the interested parties from IAEA Member States in 2007 on its website. This publication is the accompanying text which gives details of the modelling and an example scenario

F4/80 inhibits osteoclast differentiation via downregulation of nuclear factor of activated T cells, cytoplasmic 1.

Science.gov (United States)

Kang, Ju-Hee; Sim, Jung-Sun; Zheng, Ting; Yim, Mijung

2017-04-01

Osteoclastogenesis is an essential process in bone metabolism, which can be induced by RANKL stimulation. The F4/80 glycoprotein is a member of the EGF-transmembrane 7 (TM7) family and has been established as a specific cell-surface marker for murine macrophages. This study aimed to identify the role of F4/80 in osteoclastogenesis. Using mouse bone marrow-derived macrophages (BMMs), we observed that the mRNA level of F4/80 was dramatically reduced as these cells differentiated into osteoclasts. Furthermore, osteoclastogenesis was decreased in F4/80 high BMMs compared to F4/80 -/low BMMs. The inhibitory effect of F4/80 was associated with decreased expression of nuclear factor of activated T cells, cytoplasmic 1 (NFATc1). Ectopic overexpression of a constitutively active form of NFATc1 rescued the anti-osteoclastogenic effect of F4/80 completely, suggesting that the anti-osteoclastogenic effect of F4/80 was mainly due to reduction in NFATc1 expression. As an underlying mechanism, we demonstrated that the presence of F4/80 abrogated the effect of RANKL on the phosphorylation of CREB and activated the expression of IFN-β, which are restored by cyclic AMP. Collectively, our results demonstrate that the presence of F4/80 suppresses RANKL-induced osteoclastogenesis by impairing the expression of NFATc1 via CREB and IFN-β. Therefore, F4/80 may hold therapeutic potential for bone destructive diseases.

The role of IL-17 in psoriasis.

Science.gov (United States)

Malakouti, Mona; Brown, Gabrielle Elena; Wang, Eva; Koo, John; Levin, Ethan C

2015-02-01

Psoriasis is a chronic skin condition traditionally believed to involve the Th1 pathway. Recently, the IL-23/Th17/IL-17 pathway has been highlighted in the pathogenesis of psoriasis and other autoimmune inflammatory conditions. From a clinician's perspective, we sought to review the basic science data relevant to IL-17's role in psoriasis pathogenesis. We performed a Pubmed and Web of Knowledge search for English articles starting from 1990 that discussed the Th17 pathway. Search terms such as "IL-17" and "psoriasis" were utilized. The IL-17 pathway is regulated by IL-23, a cytokine that is vital for the expansion and maintenance of the Th17 cell population. Th17 derived cytokines (IL-17A, IL-17F, IL-17A/F and IL-22) were elevated in both psoriasis-like murine models and human psoriatic lesional biopsies. Ixekizumab (anti-IL-17A) treatment of psoriasis was found to normalize levels of IL-17 downstream gene products. Both preclinical and clinical studies support the central role of IL-17 in the pathogenesis of psoriasis.

A philosophy for space nuclear systems safety

International Nuclear Information System (INIS)

Marshall, A.C.

1992-01-01

The unique requirements and contraints of space nuclear systems require careful consideration in the development of a safety policy. The Nuclear Safety Policy Working Group (NSPWG) for the Space Exploration Initiative has proposed a hierarchical approach with safety policy at the top of the hierarchy. This policy allows safety requirements to be tailored to specific applications while still providing reassurance to regulators and the general public that the necessary measures have been taken to assure safe application of space nuclear systems. The safety policy used by the NSPWG is recommended for all space nuclear programs and missions

Nuclear excited power generation system

International Nuclear Information System (INIS)

Parker, R.Z.; Cox, J.D.

1989-01-01

A power generation system is described, comprising: a gaseous core nuclear reactor; means for passing helium through the reactor, the helium being excited and forming alpha particles by high frequency radiation from the core of the gaseous core nuclear reactor; a reaction chamber; means for coupling chlorine and hydrogen to the reaction chamber, the helium and alpha particles energizing the chlorine and hydrogen to form a high temperature, high pressure hydrogen chloride plasma; means for converting the plasma to electromechanical energy; means for coupling the helium back to the gaseous core nuclear reactor; and means for disassociating the hydrogen chloride to form molecular hydrogen and chlorine, to be coupled back to the reaction chamber in a closed loop. The patent also describes a power generation system comprising: a gaseous core nuclear reactor; means for passing hydrogen through the reactor, the hydrogen being excited by high frequency radiation from the core; means for coupling chlorine to a reaction chamber, the hydrogen energizing the chlorine in the chamber to form a high temperature, high pressure hydrogen chloride plasma; means for converting the plasma to electromechanical energy; means for disassociating the hydrogen chloride to form molecular hydrogen and chlorine, and means for coupling the hydrogen back to the gaseous core nuclear reactor in a closed loop

Nuclear energy in Canada: the CANDU system

International Nuclear Information System (INIS)

Robertson, J.A.L.

1979-10-01

Nuclear electricity in Canada is generated by CANDU nuclear power stations. The CANDU reactor - a unique Canadian design - is fuelled by natural uranium and moderated by heavy water. The system has consistently outperformed other comparable nuclear power systems in the western world, and has an outstanding record of reliability, safety and economy. As a source of energy it provides the opportunity for decreasing our dependence on dwindling supplies of conventional fossil fuels. (auth)

Computer systems and nuclear industry

International Nuclear Information System (INIS)

Nkaoua, Th.; Poizat, F.; Augueres, M.J.

1999-01-01

This article deals with computer systems in nuclear industry. In most nuclear facilities it is necessary to handle a great deal of data and of actions in order to help plant operator to drive, to control physical processes and to assure the safety. The designing of reactors requires reliable computer codes able to simulate neutronic or mechanical or thermo-hydraulic behaviours. Calculations and simulations play an important role in safety analysis. In each of these domains, computer systems have progressively appeared as efficient tools to challenge and master complexity. (A.C.)

Multifragment disintegrations of expanding nuclear systems

International Nuclear Information System (INIS)

Gelbke, K.

1993-01-01

Two phase transitions are expected to exist in bulk nuclear matter: a liquid-gas phase transition and a deconfinement transition to a quark-gluon plasma. In studies of nucleus-nucleus collisions, conditions similar to those pertaining to phase transitions in infinite systems can be created, but the fundamental problem yet to be solved is the identification of remnant signatures uniquely related to either of these phase transitions. Nuclear systems at densities and temperatures corresponding to the liquid-gas coexistence region can be produced in intermediate energy nucleus-nucleus collisions; they are expected to decay into many intermediate mass fragments (IMF's: Z=3-20). Recent investigations with low-threshold electronic 4π detector arrays have firmly established the occurrence of multifragment disintegrations of hot nuclear systems and allowed to challenge various theoretical approaches. In this talk, an overview of pertinent experimental results on multifragmentation will be presented and discussed. it will be shown that current microscopic transport theories designed to treat the growth of density fluctuations predict fragment multiplicities much smaller than observed experimentally. Measurements of the time scales of fragment formation are consistent with statistical model calculations for expanding hot nuclear system which indicate that fragments may form during a rather narrow time interval after the system has cooled and expanded to a density below that of normal nuclear matter. The expansion rate (and hence the fragment multiplicity) is sensitive to the equation of state (EOS). However, a number of recent results provide increasing evidence that current theoretical treatments need to be refined to allow an experimental determination of the EOS

Recoil 18F chemistry. XI. High pressure investigation of 1,1-difluoroethane

International Nuclear Information System (INIS)

Manning, R.G.; Root, J.W.

1980-01-01

Nuclear recoil 18 F reactions in CH 3 CHF 2 have been investigated throughout the effective pressure range 0.3--190 atm. The principal reaction channel is F-to-HF abstraction for which the combined yield from quasithermal and energetic processes in the presence of 5 mole% H 2 S additive is 83.4% +- 0.2%. A reaction mechanism is proposed that involves the organic product forming channels F-for-F, F-for-αH, F-for-βH, F-for-CH 3 and F-for-CHF 2 . The results are compared with those reported for the 18 F+CH 3 CF 3 system

Nuclear plant-aging research on reactor protection systems

International Nuclear Information System (INIS)

Meyer, L.C.

1988-01-01

This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show the percentage of events for RTS and ESFAS classified by cause, components, and subcomponents for each of the Nuclear Steam Supply System vendors. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identified materials susceptible to aging, stressors, environmental factors, and failure modes for the RTS and ESFAS as generic instrumentation and control systems. Functional indicators of degradation are listed, testing requirements evaluated, and regulatory issues discussed

A new option for exploitage of future nuclear energy. Accelerator driven radioactive clean nuclear power system

International Nuclear Information System (INIS)

Ding Dazhao

2000-01-01

Nuclear energy is an effective, clean and safe energy resource. But some shortages of the nuclear energy system presently commercial available obstruct further development of the nuclear energy by heavy nuclear fission. Those are final disposal of the high level radioactive waste, inefficient use of the uranium resource and safety issue of the system. Innovative technical option is seeking for by the nuclear scientific community in recent ten years in aiming to overcome these obstacles, namely, accelerator driven sub-critical system (ADS). This hybrid system may bridge over the gap between presently commercial available nuclear power system and the full exploitation of the fusion energy. The basic principle of ADS is described and its capability in waste transmutation, conversion of the nuclear fuel are demonstrated by two examples--AD-fast reactor and AD-heavy water thermal reactor. The feasibility of ADS and some projects in US, Japan, etc are briefly discussed. The rationale in promoting the R and D of ADS in China is emphasized as China is at the beginning stage of its ambitious project in construction of the nuclear power

Costs related to radioactive residues from nuclear power

International Nuclear Information System (INIS)

1988-06-01

The nuclear power enterprises are responsible for proper actions for safe handling and final storage of spent nuclear fuel and radioactive waste from Swedish nuclear power facilities. The most important actions are to plan, build and operate necessary plants and systems. The nuclear power enterprises have designated Swedish Nuclear Fuel and Waste Management Co., (SKB), to perform these tasks. In this report calculations concerning costs to carry out these tasks are presented. The calculations are based upon a plan prepared by SKB. The plan is described in the report. As final storage of the long lived and highly radioactive waste is planned to take place in the 21st century continuing research and development may indicate new methods which may affect system design as well as costs in a simplifying way. Plants and systems already operational are: Transport systems for radioactive waste products; A central temporary storage for spent nuclear fuel, 'CLAB'; A final storage for radioactive waste from operating nuclear facilities, 'SFR 1'. (L.F.)

Nuclear Material Control and Accountability System Effectiveness Tool (MSET)

International Nuclear Information System (INIS)

Powell, Danny H.; Elwood, Robert H. Jr.; Roche, Charles T.; Campbell, Billy J.; Hammond, Glenn A.; Meppen, Bruce W.; Brown, Richard F.

2011-01-01

A nuclear material control and accountability (MC and A) system effectiveness tool (MSET) has been developed in the United States for use in evaluating material protection, control, and accountability (MPC and A) systems in nuclear facilities. The project was commissioned by the National Nuclear Security Administration's Office of International Material Protection and Cooperation. MSET was developed by personnel with experience spanning more than six decades in both the U.S. and international nuclear programs and with experience in probabilistic risk assessment (PRA) in the nuclear power industry. MSET offers significant potential benefits for improving nuclear safeguards and security in any nation with a nuclear program. MSET provides a design basis for developing an MC and A system at a nuclear facility that functions to protect against insider theft or diversion of nuclear materials. MSET analyzes the system and identifies several risk importance factors that show where sustainability is essential for optimal performance and where performance degradation has the greatest impact on total system risk. MSET contains five major components: (1) A functional model that shows how to design, build, implement, and operate a robust nuclear MC and A system (2) A fault tree of the operating MC and A system that adapts PRA methodology to analyze system effectiveness and give a relative risk of failure assessment of the system (3) A questionnaire used to document the facility's current MPC and A system (provides data to evaluate the quality of the system and the level of performance of each basic task performed throughout the material balance area (MBA)) (4) A formal process of applying expert judgment to convert the facility questionnaire data into numeric values representing the performance level of each basic event for use in the fault tree risk assessment calculations (5) PRA software that performs the fault tree risk assessment calculations and produces risk importance

Expert systems and nuclear safety

International Nuclear Information System (INIS)

Beltracchi, L.

1990-01-01

The US Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute have initiated a broad-based exploration of means to evaluate the potential applications of expert systems in the nuclear industry. This exploratory effort will assess the use of expert systems to augment the diagnostic and decision-making capabilities of personnel with the goal of enhancing productivity, reliability, and performance. The initial research effort is the development and documentation of guidelines for verifying and validating (V and V) expert systems. An initial application of expert systems in the nuclear industry is to aid operations and maintenance personnel in decision-making tasks. The scope of the decision aiding covers all types of cognitive behavior consisting of skill, rule, and knowledge-based behavior. For example, procedure trackers were designed and tested to support rule-based behavior. Further, these systems automate many of the tedious, error-prone human monitoring tasks, thereby reducing the potential for human error. The paper version of the procedure contains the knowledge base and the rules and thus serves as the basis of the design verification of the procedure tracker. Person-in-the-loop tests serve as the basis for the validation of a procedure tracker. When conducting validation tests, it is important to ascertain that the human retains the locus of control in the use of the expert system

Public concerns and alternative nuclear power systems

International Nuclear Information System (INIS)

Mayo, L.H.

1980-02-01

The basic task undertaken in this study was to assess the relative public acceptability of three general types of nuclear power systems as alternatives to the existing Light Water Reactor (LWR) system. Concerns registered toward nuclear power constituted the basic data for this assessment. The primary measure adopted for determining the significance of concerns was the degree of difficulty posed by the concern to the nuclear power decisional structure in the establishment and maintenance of norms to control risks or to advance intended energy objectives. Alleviations or exacerbations of concern resulting from particular attributes of alternative systems were measured from an LWR baseline

NCIS - a Nuclear Criticality Information System (overview)

International Nuclear Information System (INIS)

Koponen, B.L.; Hampel, V.E.

1983-07-01

A Nuclear Criticality Information System (NCIS) is being established at the Lawrence Livermore National Laboratory (LLNL) in order to serve personnel responsible for safe storage, transport, and handling of fissile materials and those concerned with the evaluation and analysis of nuclear, critical experiments. Public concern for nuclear safety provides the incentive for improved access to nuclear safety information

Structural materials for innovative nuclear systems (SMINS)

International Nuclear Information System (INIS)

2008-01-01

Structural materials research is a field of growing relevance in the nuclear sector, especially for the different innovative reactor systems being developed within the Generation IV International Forum (GIF), for critical and subcritical transmutation systems, and of interest to the Global Nuclear Energy Partnership (GNEP). Under the auspices of the NEA Nuclear Science Committee (NSC) the Workshop on Structural Materials for Innovative Nuclear Systems (SMINS) was organised in collaboration with the Forschungszentrum Karlsruhe in Germany. The objectives of the workshop were to exchange information on structural materials research issues and to discuss ongoing programmes, both experimental and in the field of advanced modelling. These proceedings include the papers and the poster session materials presented at the workshop, representing the international state of the art in this domain. (author)

Nuclear Hybrid Energy Systems FY16 Modeling Efforts at ORNL