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Sample records for apres irradiation neutronique

  1. Chemical transformations associated with neutronic irradiation of telluric acid; Transformations chimiques associees a l'irradiation neutronique de l'acide teliurique

    Energy Technology Data Exchange (ETDEWEB)

    Bertet, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1963-01-15

    The chemical transformations which arise from irradiation of telluric acid with neutrons have been studied under several experimental conditions. The effects of the reaction (n, {gamma} ) on Te{sup VI} and of the isomeric transitions {sup 131m}Te{sup VI} {yields} {sup 131}Te and {sup 129m}Te{sup VI} {yields} {sup 129}Te, and the oxidation states of {sup 131}I formed by {beta} decay of {sup 131}Te have been investigated in detail. The Szilard-Chalmers effect has been put in evidence. Retention (R) depends on the isomeric state of Rd-Te and is higher for the metastable isotopes. R increases with the time of irradiation. R seems to be independent of the medium which is used for dissolving telluric acid irradiated in the solid state. Higher values of R are found if the acid is irradiated in neutral or alkaline solution; irradiation in acid solution leads to lower values for R. Retention for {sup 131}Te{sup VI} and {sup 129}Te{sup VI} formed by isomeric transition depends on the pH of the solution where this disintegration occurs. For instance, with {sup 129}Te, R is greater in 6 M NaOH (80 per cent) than in 3 M HCI (40 per cent). The relative amounts of the oxidation states of {sup 131}I (reduced fraction (I{sup -}, IO{sup -}, I{sub 2}), iodate and periodate) depend on the medium, both if the acid is irradiated in the solid state and it is irradiated in solution. In the first case, the reduced fraction increases from 12 to 89 per cent when the dissolving medium is changed from neutral to 0.8 M HNO{sub 3}. In the second case, the reduced fraction is 90 per cent in neutral or acid solution and 64 per cent in 0.5 M KOH. It has been shown, furthermore, that microamounts of Te{sup VI} are formed in certain cases. (author) [French] Les transformations chimiques accompagnant l'irradiation neutronique de l'acide tellurique ont ete etudiees dans differentes conditions experimentales. On a examine notamment les consequences de la reaction (n, {gamma}) sur Te{sup VI

  2. Thyroid tumors after irradiation; Tumeurs de la thyroide apres irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Schlumberger, M. [Centre de Lutte Contre le Cancer Gustave-Roussy, 94 - Villejuif (France)

    1995-12-31

    Epidemiological studies have shown an increased incidence of thyroid tumors after external irradiation during childhood. These studies have shown a long latency and have pointed out risk factors, related either to the subject (young age, female sex) or to the radiation (dose, fractionation, protection). Irradiation by Iodine 131 in adulthood does not seen to increase the risk of thyroid tumor but in childhood data are too scarce to allow any conclusion. Similarly, the risks following low radiation doses and/or protected radiation exposure are still matter of debate. (author). 41 refs., 5 tabs., 1 fig.

  3. Study of boron carbide evolution under neutron irradiation; Contribution a l'etude de l'evolution du carbure de bore sous irradiation neutronique

    Energy Technology Data Exchange (ETDEWEB)

    Simeone, D. [CEA/Saclay, Dept. de Mecanique et de Technologie (DMT), 91 - Gif-sur-Yvette (France)]|[Universite Blaise Pascal, Clermont-Ferrand II, (CNRS), 63 - Aubiere (France)

    1999-07-01

    Owing to its high neutron efficiency, boron carbide (B{sub 4}C) is used as a neutron absorber in control rods of nuclear plants. Its behaviour under irradiation has been extensively studied for many years. It now seems clear that brittleness of the material induced by the {sup 10}B(n,{alpha}){sup 7}Li capture reaction is due to penny shaped helium bubbles associated to a high strain field around them. However, no model explains the behaviour of the material under neutron irradiation. In order to build such a model, this work uses different techniques: nuclear microprobe X-ray diffraction profile analysis and Raman and Nuclear Magnetic Resonance Spectroscopy to present an evolution model of B{sub 4}C under neutron irradiation. The use of nuclear reactions produced by a nuclear microprobe such as the {sup 7}Li(p,p'{gamma}){sup 7}Li reaction, allows to measure lithium profile in B{sub 4}C pellets irradiated either in Pressurised Water Reactors or in Fast Breeder Reactors. Examining such profiles enables us to describe the migration of lithium atoms out of B{sub 4}C materials under neutron irradiation. The analysis of X-ray diffraction profiles of irradiated B{sub 4}C samples allows us to quantify the concentrations of helium bubbles as well as the strain fields around such bubbles.Furthermore Raman spectroscopy studies of different B{sub 4}C samples lead us to propose that under neutron irradiation. the CBC linear chain disappears. Such a vanishing of this CBC chain. validated by NMR analysis, may explain the penny shaped of helium bubbles inside irradiated B{sub 4}C. (author)

  4. Breast cancers and leukaemias after irradiation. Cancers du sein et leucemies apres irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Vathaire, F. de (Centre de Lutte Contre le Cancer Gustave-Roussy, 94 - Villejuif (France))

    1994-01-01

    The influence of new data or recent re-analysis concerning the risks of breast cancer and leukaemia after irradiation is summarized in this article. The risk of breast cancer, particularly after irradiation during childhood, seems to be more important than estimated previously. Because the pattern of risk after irradiation seems to be multiplicative and since breast cancer is very frequent among western populations, these new findings may have important consequences in public health. Despite leukaemias have been known for a long time to be a radioinduced tumour, very little information is available about the effects of age at irradiation and dose rate. (author). 9 refs., 2 tabs.

  5. Recovery and radio-resistance in mice after external irradiation; Restauration et radio-resistance chez la souris apres irradiation externe

    Energy Technology Data Exchange (ETDEWEB)

    Le Guillou, S. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1965-07-01

    The author presents a literature study concerning recovery from external irradiation and an analysis of experimental data (which appear to suggest the idea of a radio-resistance in animals), as well as the hypotheses put forward for explaining this phenomenon. The author then describes an experiment carried out on mice whose LD 50/30 days increased from 1005 to 1380 rads and for which it was shown that an increase occurs in the number of certain anti-bodies circulating after a low dose of {gamma} irradiation. (author) [French] L'auteur presente une etude bibliographique de la restauration apres irradiation externe et une analyse des donnees experimentales qui paraissent suggerer la notion de radioresistance chez les animaux ainsi que les hypotheses cherchant a expliquer ce phenomene. Il relate ensuite une experience realisee sur des souris dont la DL 50/30 jours est passee de 1005 a 1380 rads et dans laquelle est montree l'augmentation de certains anticorps circulant apres une faible dose d'irradiation gamma. (auteur)

  6. Understanding and predicting the behaviour of silver base neutron absorbers under irradiations; Comprehension et prediction du comportement sous irradiation neutronique d`alliages absorbants a base d`argent

    Energy Technology Data Exchange (ETDEWEB)

    Desgranges, C

    1998-12-31

    The effect of neutron irradiation induced transmutations on the swelling of AgInCd (AIC) alloys used as neutron absorber in the control rods of Pressurized Water Reactors has been studied both experimentally and theoretically. Effective atomic volumes have been determined in synthetic AgCdInSn alloys with various compositions and containing fcc and hc phases, representative of irradiated AIC (Sn is a transmutation product). Swelling is shown to result first from the transmutation of Ag into Cd and of In into Sn, both with larger effective volume than the mother atom, and second from grain boundaries precipitation of s still less dense hc phase when solid solubility of transmuted products is exceeded. For both fcc and hc phases, we have determined profiles at the temperatures in the vicinity of the operating temperature. Unusual characteristics of second phase growth at grain boundaries induced by transmutations are identified on a simple binary alloy model: kinetics is controlled by irradiation temperature which scales diffusivities and flux which scales transmutation rates, as well as by the grain size in the underlying matrix. To address the AgInCdSn alloys, a novel technique is proposed to model diffusion in multicomponent alloys. It is based on a linearization of a simple atomistic model. With a single set of parameters, for each phase, our model well reproduces our interdiffusion measurements in quaternary alloys as well as existing interdiffusion experiments in binary alloys. Finally this diffusion model implemented with a moving interface algorithm is used to model the growth of the second phase induced by transmutation in the AIC under irradiation. (authors) 74 refs.

  7. Regulation mechanisms of the FLT3-ligand after irradiation; Mecanismes de regulation du FLT3-ligand apres irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Prat-Lepesant, M

    2005-06-15

    The hematopoietic compartment is one of the most severely damaged after chemotherapy, radiotherapy or accidental irradiations. Whatever its origin, the resulting damage to the bone marrow remains difficult to evaluate. Thus, it would be of great interest to get a biological indicator of residual hematopoiesis in order to adapt the treatment to each clinical situation. Recent results indicated that the plasma Flt3 ligand concentration was increased in patients suffering from either acquired or induced aplasia, suggesting that Flt3 ligand might be useful as a biological indicator of bone marrow status. We thus followed in a mouse model as well as in several clinical situations the variations in plasma Flt3 ligand concentration, after either homogeneous or heterogeneous irradiations. These variations were correlated to the number of hematopoietic progenitors and to other parameters such as duration and depth of pancytopenia. The results indicated that the concentration of Flt3 ligand in the blood reflects the bone marrow status, and that the follow-up of plasma Flt3 ligand concentration could give predictive information about the bone marrow function and the duration and severity of pancytopenia and thrombocytopenia. Nevertheless, the clinical use of Flt3 ligand as a biological indicator of bone marrow damage require the knowledge of the mechanisms regulating the variations in plasma Flt3 ligand concentration. We thus developed a study in the mouse model. The results indicated that the variations in plasma Flt3 ligand variations were not solely due to a balance between its production by lymphoid cells and its consumption by hematopoietic cells. Moreover, we showed that T lymphocytes are not the main regulator of plasma Flt3 ligand concentration as previously suggested, and that other cell types, possibly including bone marrow stromal cells, might be strongly implicated. These results also suggest that the Flt3 ligand is a main systemic regulator of hematopoiesis

  8. Re-irradiation after salvage mastectomy for local recurrence after a conservative treatment: a retrospective analysis of twenty patients (Nancy: 1988-2001); Re-irradiation parietale apres mastectomie de rattrapage pour recidive d'un cancer du sein apres traitement conservateur: etude retrospective sur 20 patientes (Nancy: 1988-2001)

    Energy Technology Data Exchange (ETDEWEB)

    Racadot, S.; Marchal, C.; Charra-Brunaud, C.; Peiffert, D.; Bey, P. [Centre Alexis-Vautrin, Service de Radiotherapie, 54 - Vandoeuvre-les-Nancy (France); Verhaeghe, J.L. [Centre Alexis-Vautrin, Service de Chirurgie, 54 - Vandoeuvre-les-Nancy (France)

    2003-12-01

    Purpose. - To retrospectively assess the efficacy of post-mastectomy re-irradiation for local relapse of breast cancer. Patients and methods. - Twenty patients, initially treated by conservative surgery and radiotherapy (50 Gy in 25 fractions over 5 weeks) were treated from 1998 to 2001 for a local relapse by salvage mastectomy and re-irradiation (either electron or photon beams). Mean age was 53 years (31-71). Reasons for re-irradiation were that the local relapses were inflammatory (4 pts), multifocal (5 pts), cutaneous (5 pts), involved the nipple (3 pts) or because the surgical margins (either muscle or skin) were involved (3 pts). The median dose of re-irradiation was 45 Gy (33-65) in 15 fractions over 33 days. Mean follow-up was 48 months (5-97). Results. - Fifteen patients remained free of a second local recurrence and 10 were still alive, without metastasis. Neither the dose of re-irradiation nor the irradiated surfaces were prognostic factors of local control (P = 0.877 and P = 0.424). Five patients developed radiation-induced pneumonitis without functional respiratory impairment. The incidence of pneumonitis seemed to be related to the biological dose of re-irradiation (P = 0.037). Other late complications occurred such as pigmentation changes (12 pts), telangiectasia (8 pts), chondritis (2 pts), parietal fibrosis (7 pts), rib fractures (4 pts), severe pain (11 pts) and lymphedema (2 pts). The increase in biological equivalent dose was highly statistically linked with the occurrence of disabling pain (P = 0.0123). Conclusion. - Parietal re-irradiation achieves good and lasting local control with an acceptable rate of acute complications but with a risk of disabling late sequelae such as severe pain. (author)

  9. Therapeutic approaches of hematopoietic syndrome after serious accidental global irradiation. Ex vivo expansion interest of hematopoietic cells; Approches therapeutiques du syndrome hematopoietique apres irradiation globale accidentelle grave. Interet de l`expansion ex vivo des cellules hematopoietiques

    Energy Technology Data Exchange (ETDEWEB)

    Thierry, D.

    1994-12-31

    Aplasia is one of the main syndrome, appearing after one global accidental irradiation by one ionizing radiation source. The hematopoietic syndrome is characterized by a peripheric blood cell number fall; the cell marrow is reduced too.

  10. APR-2 Tropical Cyclone Observations

    Science.gov (United States)

    Durden, S. L.; Tanelli, S.

    2011-01-01

    The Second Generation Airborne Precipitation Radar (APR-2) participated in the Genesis and Rapid Intensification Processes (GRIP) experiment in August and September of 2010, collecting a large volume of data in several tropical systems, including Hurricanes Earl and Karl. Additional measurements of tropical cyclone have been made by APR-2 in experiments prior to GRIP (namely, CAMEX-4, NAMMA, TC4); Table 1 lists all the APR-2 tropical cyclone observations. The APR-2 observations consist of the vertical structure of rain reflectivity at 13.4 and 35.6 GHz, and at both co-polarization and crosspolarization, as well as vertical Doppler measurements and crosswind measurements. APR-2 normally flies on the NASA DC-8 aircraft, as in GRIP, collecting data with a downward looking, cross-track scanning geometry. The scan limits are 25 degrees on either side of the aircraft, resulting in a roughly 10-km swath, depending on the aircraft altitude. Details of the APR-2 observation geometry and performance can be found in Sadowy et al. (2003).The multiparameter nature of the APR-2 measurements makes the collection of tropical cyclone measurements valuable for detailed studies of the processes, microphysics and dynamics of tropical cyclones, as well as weaker systems that are associated with tropical cyclone formation. In this paper, we give a brief overview of how the APR-2 data are processed. We also discuss use of the APR-2 cross-track winds to estimate various quantities of interest in in studies of storm intensification. Finally, we show examples of the standard products and derived information.

  11. Study of the new properties of magnetite and hematite after transformation by irradiation and by grinding; Etude des nouvelles proprietes de la magnetite et de l`hematite apres transformation par irradiation et par mecanosynthese

    Energy Technology Data Exchange (ETDEWEB)

    Meillon, S.

    1996-01-26

    We have investigated the evolution of magnetite (Fe{sub 3}O{sub 4}) and hematite ({alpha}Fe{sub 2}0{sub 3}) when faced with high energy heavy ions (5.9 6 GeV Pb) irradiation, fast neutron irradiation, and grinding. Magnetite is formed by a ceramic treatment. Heating hematite particles to about 1300 deg (under inert atmosphere) results in a conversion to magnetite. The damage induced in magnetite by high energy ion irradiation (electronic excitation) has the form of extended spherical defects (discontinuous latent tracks) in the ion wakes. High resolution electron microscopy observations have indicated only slight atomic displacements without profound modification of the structure (absence of an amorphous phase), even after high fluences (3*10{sup 12} Pb.cm{sup -2}). The results obtained by Moessbauer spectroscopy, by magnetization measurements and by low field hysteresis loops determination are coherently interpreted using a model based on magnetoelastic concepts. This model explains the restoration of the magnetic properties of magnetite after irradiation. The damage induced in magnetite and hematite following fast neutron irradiation was studied by thermal neutron diffraction. A very small variation of the lattice parameter has been observed for magnetite. The distribution of the magnetic moments of the iron ions in the tetrahedral and octahedral sites is not modified. For hematite, we have observed an expansion along the c-axis of hexagonal unit cell. This result is coherent with the results obtained by grinding. Finally, the observation of original direct phase transformation by the mechanical action of grinding is reported: hematite transforms into maghemite. As previously observed after fast neutron irradiation, here again the transition from an hexagonal (hematite) to a f.c.c lattice (maghemite) is accompanied by an expansion along the c-axis direction of the lattice. The transformation occurs through a shear sequence of oxygen planes. (Abstract Truncated)

  12. Cytosteatonecrosis after breast accelerated conformational partial irradiation at 40 Gy in 10 fractions a week: multicentre prospective study; Cytosteatonecrose apres irradiation partielle acceleree conformationnelle du sein a 40 Gy en 10 fractions par semaine: etude prospective multicentrique

    Energy Technology Data Exchange (ETDEWEB)

    Levy, A.; Bourgier, C. [Institut Gustave-Roussy, Villejuif (France); Taghian, A.; Ancukiewicz, M.; MacDonald, S.; Smith, B. [Massachusetts General Hospital, Boston MA (United States); Hirsch, A.; Kachnic, L. [Boston Medical Center, Boston MA (United States); Recht, A. [Beth Israel Deaconess Medical Center, Boston MA (United States)

    2011-10-15

    Conformational accelerated partial irradiation is always more often used but the optimal dose is not yet known. Therefore, the authors report an assessment of the cytosteatonecrosis rate within a multicentre prospective study which delivered 40 Gy over 5 days. They analyse and comment the results obtained on a range of more than 150 women treated for breast cancer. Results are discussed in terms of age, tumour size. The method resulted in an acceptable cytosteatonecrosis rate in comparison with other accelerated partial irradiation. But a more precise assessment of the toxicity rate requires further investigations. Short communication

  13. Rectum and vesicle toxicity risk factors after prostate conformal irradiation (of 70 or 80 Gy); Facteurs de risque de toxicite rectale et vesicale apres irradiation conformationelle prostatique (de 70 ou 80 Gy)

    Energy Technology Data Exchange (ETDEWEB)

    Chira, C.; Le Prise, E.; Lahbabi, K.; Lafond, C.; Manens, J.P.; Crevoisier, R. de [Centre Eugene-Marquis, 35 - Rennes (France); Bossi, A. [Institut Gustave-Roussy, 94 - Villejuif (France); Vincendeau, S. [CHU Pontchaillou, 35 - Rennes (France); Bayat, S.; Rossille, D. [Rennes-1 Univ., Inserm U936, 35 (France)

    2009-10-15

    Purpose: Identification of delayed rectal or vesical toxicity risk factors, linked to the patients or to irradiation, in case of exclusive prostate conformal radiotherapy. conclusion: the risk of toxicity is not only increased by the high doses of irradiation ( 70 to 80 Gy) but also by average doses (40 to 50 Gy) delivered in a broad volume of organ at risk. The predictive mathematic models for the toxicity (N.T.C.P. for normal tissue complication probability) are being validated. in this series (constants adjustment). (N.C.)

  14. Respirators: APR Issuer Self Study 33461

    Energy Technology Data Exchange (ETDEWEB)

    Chochoms, Michael [Los Alamos National Laboratory

    2016-07-13

    Respirators: APR Issuer Self-Study (course 33461) is designed to introduce and familiarize employees selected as air-purifying respirator (APR) issuers at Los Alamos National Laboratory (LANL) with the responsibilities, limitations, procedures, and resources for issuing APRs at LANL. The goal is to enable these issuers to consistently provide proper, functioning APRs to authorized users

  15. Spontaneous radiopathological evolution and after medical treatment in two models of localized irradiation. Evolution radiopathologique spontanee et apres traitement medical dans deux modeles d'accident d'irradiation localisee

    Energy Technology Data Exchange (ETDEWEB)

    Lefaix, J.L.; Daburon, F.; Tricaud, Y. (CEA Centre d' Etudes de Fontenay-aux-Roses, 92 (France). Dept. de Pathologie Experimentale)

    1992-09-01

    Pathophysiological evolution of a [sup 192]Ir [gamma]-rays radio-induced muscular lesion was studied in experimental models developed in pigs and rabbits to simulate accidents which occurred among humans. Cutaneous and muscular radionecrosts started from early epithelial, microvascular and vascular lesions and late muscular and connective tissue lesions. Our therapeutic studies in pigs showed the interest of an early surgical treatment a minima. In rabbits, the association of non-steroidal anti-inflammatory (flurbiprofene) and haemorrheological agent (trimetazidine) among 10 other medical treatments, given for 8 weeks after an irradiation of a 80 Gy dose at the skin surface, involved a dose reduction factor of 2, with regards to the evolution of the skin injuries and the deep muscular fibronecrotic process. Tabs.

  16. Influence of melanocytes in the ex-vivo reconstructed epidermal melanin unit following an acute UV irradiation; Role des melanocytes dans l'unite epidermique de melanisation reconstruite ex-vivo apres une irradiation UV aigue

    Energy Technology Data Exchange (ETDEWEB)

    Cario-Andre, M

    2000-11-15

    Influence of melanocytes in skin pigmentation is well documented, however its photo-protective role has given rise to controversy. The role of melanocytes have been investigated on reconstructed epidermis with 100 % of keratinocytes or 95 % of keratinocytes and 5 % of melanocytes. In a first time, the effect of an acute UVB dose has been studied on both reconstructed epidermis, next we have investigated UVA and UVA+B effects on these epidermis. Following irradiation, the presence of melanocytes in reconstructed epidermis protects against apoptosis without protecting significantly against DNA damage formation (CPD, 6-4PP) and protects against UV-induced unbalance of the SOD/catalase ratio (antioxidants enzymes). On the contrary, the presence of melanocytes in reconstructed epidermis amplifies lipids and proteins oxidations but seems to protect against DNA oxidations. Melanocytes differ from keratinocytes by their melanin content and their more important concentration in polyunsaturated fatty acids. To evaluate what is the part of melanin and the part of polyunsaturated fatty acids in epidermal UV responses, reconstructed epidermis with keratinocytes have been supplemented with polyunsaturated fatty acid. This study indicates that polyunsaturated fatty acids are responsible for lipids and proteins oxidations and that melanin protect against DNA oxidation induced by lipid peroxidation. All these studies demonstrate that, model of reconstructed epidermis and epidermis in-vivo have the same behaviour following UV irradiation. In the last part, sunscreens and antioxidants have been tested on reconstructed epidermis and have demonstrated that model of reconstructed epidermis is suitable for photo-protective molecules screening. (author)

  17. Diagnostic Strategy in APR1400

    International Nuclear Information System (INIS)

    These features may bring out changes in operator tasks, changing the characteristics of tasks, or creating new tasks. Diagnostic strategy for identifying anomaly may be different especially in APR1400 from that in the analog control room due to the change of human-system interface, i.e. alarm system and display system. Since the first plant of APR1400 is being built at this moment, it is not known what strategies the operators will adopt in diagnosis tasks in the new operating environment. In this light, this paper aims at investigating operator's diagnostic strategies which are appropriate for APR1400. In order to collect data, several different approaches which are complementary are used to identify diagnostic strategies in the digital control room: analysis on audio/video recording of operation, observation in the simulator, and interview with the operators. The result shows that the digital control room introduces new strategies in the diagnosis, compared with the analog control room, and also changed the characteristics of strategies, mostly, by getting more support from the computerized system. This paper investigated how the digitalized control room may influence operator's diagnostic strategies. Several different approaches, i. e., audio/video record, observation of training, and the interview with operators, were used to gather information about the operator's behaviors. As a conclusion, this paper figured out that the digital control room introduces new strategies in the diagnosis, compared with the analog control room, and also changed the characteristics of the strategies, mostly, by getting more support from the computerized system. The operators interviewed also commented that the diagnosis in the APR1400 is quicker, more correct, and easier, compared with the analog control room

  18. Mechanistic studies of APR-246 in leukemia

    OpenAIRE

    Ali, Dina Mahmoud

    2013-01-01

    PRIMA-1and its analog APR-246 are novel drugs that restore the active conformation of mutated and unfolded p53 protein and induce apoptosis and cell death in various tumors in pre-clinical models. We first aimed to explore the effects of APR-246 alone and in combination with other drugs in acute myeloid leukemia (AML) in vitro. APR-246 induced dose-dependent apoptosis and increased active caspase-3 and p53 protein levels as well as the Bax/Bcl-2 ratio independently of TP53...

  19. Contribution à l’évaluation des incertitudes sur les sections efficaces neutroniques, pour les réacteurs à neutrons rapides

    OpenAIRE

    Privas, Edwin

    2015-01-01

    La thèse a essentiellement été motivée par la volonté croissante de maîtriser les incertitudes des données nucléaires, pour des raisons de sûreté nucléaire. Elle vise en particulier les sections efficaces indispensables aux calculs neutroniques des réacteurs rapides au sodium de Génération IV (RNR-Na), et les moyens permettant de les évaluer.Le principal objectif de la thèse est de fournir et montrer l’intérêt de nouveaux outils permettant de réaliser des évaluations cohérentes, avec des ince...

  20. Coping Capability of APR Against Fukushima Accidents

    International Nuclear Information System (INIS)

    Major threats on Fukushima Daiichi plant are earthquake, tsunami, SBO (Station Black Out), and hydrogen burning and explosion. Following the 9.1 magnitude earthquake, tsunami of 15m-height caused Emergency Diesel Generator (EDG) trouble and SBO. APR+ (Advanced Power Reactors Plus) has been basically designed to have the seismic design basis of Safe Shutdown Earthquake (SSE) 0.3g, a 4-train safety concept based on N+2 design philosophy, and a Passive Auxiliary Feedwater System (PAFS). Safety issues on the Fukushima-type accident have been extensively reviewed to enhance APR+ safety. After the review, many items was selected in the APR+ standard design to cope with the accidents. The items can be categorized as follows; Design of structure and equipment against earthquakes and coastal flooding, Integrity of electric power, cooling, and fire protection systems on inundation, Countermeasures against severe accident, and Emergency response and emergency medical systems. The key items include enhancement of seismic design for Main Control Room (MCR) and capability of cooling water intake, improvement of facilities entrance such as a water tight door against tsunami or flood, provision for external cooling water of PCCT (Passive Condensate Cooling Tank), diversity design for emergency electric power sources, and capability extension of a battery for supporting the 72-hour copying time. These items to enhance the safety will have been applied to the APR+ design. Consequently, APR+ can provide higher reliability and safety against tsunami and earthquake

  1. Absolute measurement of {beta} activities and application to the determination of neutronic densities; Mesure absolue d'activites {beta} et application a la determination des densites neutronique

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, R. [Commissariat a l' Energie Atomique, Lab. du Fort de Chatillon, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1951-01-15

    M. Berthelot, to my entrance to the ''Commissariat a l 'Energie Atomique'', proposed me to study the absolute measurement of neutron densities. Very quickly the problem of the absolute activity of {beta} sources became the central object of this work. In a first part, we will develop the methods of absolute determination for {beta} activities. The use of a 4{pi} counter permits to get the absolute activity of all beta radioactive source, susceptible to be put as thin leaf and of period superior than some minutes. The method is independent of the spectra of the measured radioelement. we will describe in the second part some applications which use neutron densities measurement, neutron sources intensities and ratio of cross sections of capture of thermal neutrons. (M.B.) [French] M. Berthelot, a mon entree au ''Commissariat a l 'Energie Atomique'', m'a propose d'etudier la mesure absolue des densites neutroniques. Tres rapidement le probleme de l'activite absolue des sources beta est devenu l'objet central de ce travail. Dans une premiere partie, on abordera les methodes de determination absolue des activites beta. L'utilisation d'un compteur 4{pi} permet d 'obtenir l'activite absolue de toute source radioactive beta, susceptible d'etre mise sous forme de feuille mince et de periode superieure a quelques minutes. La methode est independante du spectre du radioelement mesure. On decrira dans la seconde partie quelques applications a des mesures de densites neutroniques, d'intensites de sources de neutrons et de rapport de sections efficaces de capture de neutrons thermiques. (M.B.)

  2. Separate Effect Test for APR+ DVI+

    International Nuclear Information System (INIS)

    DVI and FD are our own design features adopted into APR1400. This study focuses on improving their performance for the APR+. From a preliminary study, conceptual design for DVI+ has been developed. Various separate effect tests were performed to evaluate the performance of the design concept and to develop a basic design. For DVI+ design, tests for DVI duct performance and vibration characteristics were performed. For FD+ design, sensitivity tests for major design parameters were performed. This study also includes a development of design for the reactor flow distribution test as well as FD+ overall performance test

  3. Les interventions après feu

    OpenAIRE

    Toutchkov, M.; Duché, Y.; Prevosto, B.; Quesney, T.; Vennetier, M.

    2013-01-01

    This chapter presents various post-fire management options for Pinus halepensis stands / Ce chapitre présente les différentes manière de gérer l'après-feu dans les peuplements de pin d'Alep incendiés

  4. An experimental model of acute encephalopathy after total body irradiation in the rat: effect of Ginkgo biloba extract (EGb 761); Effet de l'extrait de Ginkgo biloba (EGb 761) chez le rat sur un modele experimental d'encephalopathie aigue apres irradiation corporelle totale

    Energy Technology Data Exchange (ETDEWEB)

    Lamproglou, I.; Bok, B. [Hopital Bichat, 75 - Paris (France); Boisserie, G.; Mazeron, J.J.; Baillet, F. [Hopital Pitie-Salpetriere, 75 - Paris (France); Drieu, K. [IHB-IPSEN, 75 - Paris (France)

    2000-06-01

    To define the therapeutic effect of Ginkgo biloba extract (EGb 761) in an experimental model of acute encephalopathy following total body irradiation in rats. Ninety four-month-old rats received 4.5 Gy total body irradiation (TBI) at day 1 while 15 rats received sham irradiation. A behavioural study based on a conditioning test of negative reinforcement, the one-way avoidance test, was performed test, was performed after irradiation. Orally treatment was started one day (study A) or twenty two days (study B) after irradiation and repeated daily for twelve days. In the irradiated group, three subgroups were defined according to the treatment received: EGb 761 (50 mg/kg), EGb 761 (100 mg/kg), water. This work comprised two consecutive studies. In study A (45 rats) the one-way avoidance test was administered daily from day 7 to day 14. In study B (45 rats) the behavioural test was performed from day 28 to day 35. Study A (three groups of 15 rats): following TBI, irradiated rats treated with water demonstrated a significant delay in a learning the one-way avoidance test in comparison with sham-irradiated rats (P < 0.0002) or irradiated rats treated with EGb 761 (50 mg/kg; P < 0.007) or EGb 761 (100 mg/kg; P < 0.0002). The irradiated rats, treated with EGb 761 (50 or 100 mg/kg) did not differ from the sham-irradiated controls. Study B (three groups of 15 rats): the irradiated rats, treated with water of EGb 761 (50 or 100 mg/kg) did not differ from the sham-irradiated controls. (authors)

  5. Containment performance analysis for EU APR1400

    International Nuclear Information System (INIS)

    During a severe accident, as the last barrier of DID (Defense In Depth) strategy, the containment has an important role to limit the release of the radioactive material to environment. The containment should be able to maintain its structural integrity to prevent the release of the radioactive materials contained in it. In this paper, the behavior of pressure and temperature in the containment is evaluated for various accident conditions. EU APR1400 (European APR1400) is equipped with RDS (Rapid Depressurization System), HMS (Hydrogen Mitigation System), SACSS (Severe Accident Containment Spray System), and PECS (Passive Ex vessel Cooling System) to mitigate the severe accident consequences and eventually to keep the containment integrity. Depending on the availabilities of these mitigation systems, the containment undergoes different transients in pressure and temperature

  6. Role of lymph node irradiation in patients free of nodal involvement after neoadjuvant chemotherapy for breast cancer; Role de l'irradiation ganglionnaire chez les patientes indemnes d'envahissement ganglionnaire apres chimiotherapie neoadjuvante pour un cancer du sein

    Energy Technology Data Exchange (ETDEWEB)

    Daveau, C.; Stevens, D.; Brain, E.; Berges, O.; Gardner, M.; Villette, S.; Moisson, P.; De la Lande, B.; Labib, A.; Le Scodan, R. [Centre Rene-Huguenin, 92 - Saint-Cloud (France)

    2009-10-15

    The results suggest that an only breast irradiation is not associated to a higher risk of local recurrence or death in patients with a classified pN0 breast cancer after neoadjuvant chemotherapy. (N.C.)

  7. Role of lymph node irradiation in breast cancer patients with negative pathologic node status after neo-adjuvant chemotherapy: The Rene-Huguenin Cancer Center experience; Role de l'irradiation ganglionnaire chez les patientes indemnes d'envahissement ganglionnaire apres chimiotherapie neoadjuvante pour un cancer du sein: experience du centre Rene-Huguenin

    Energy Technology Data Exchange (ETDEWEB)

    Daveau, C.; Labib, A.; Berges, O.; Moisson, P.; De la Lande, B.; Le Scodan, R. [Departement de radiotherapie, centre Rene-Huguenin, hopital Rene Huguenin, institut Curie, 92 - Saint-Cloud (France); Stevens, D. [Departement de biostatistiques, centre Rene-Huguenin, 92 - Saint-Cloud (France)

    2010-12-15

    Purpose: Neo-adjuvant chemotherapy generally induces significant changes in the pathological extent of disease. This potential down-staging challenges the standard indications of adjuvant radiation therapy. We assessed the utility of lymph node irradiation in breast cancer patients with pathological N0 status (pN0) after neo-adjuvant chemotherapy and breast-conserving surgery. Patients and materials: Among 1054 breast cancer patients treated with neo-adjuvant chemotherapy in our institution between 1990 and 2004, 248 patients with clinical N0 or N1-N2 lymph node status at diagnosis had pN0 status after neo-adjuvant chemotherapy and breast-conserving surgery. Cox regression analysis was used to identify factors influencing locoregional recurrence-free survival, disease-free survival and overall survival. Results: All 248 patients received breast irradiation, and 158 patients (63.7%) also received lymph node irradiation. With a median follow-up of 88 months, the 5-year locoregional recurrence-free survival and overall survival rates were respectively 89.4% and 88.7% with lymph node irradiation and 86.2% and 92% without lymph node irradiation (no significant difference). Survival was poorer among patients who did not have a pathological complete primary tumor response (pCR) (hazards ratio [HR] = 3.05; 95% CI, 1.17 to 7.99) and in patients with N1-N2 clinical status at diagnosis ([HR] = 2.24; 95% CI, 1.15 to 4.36). Lymph node irradiation did not significantly affect survival. Conclusions: Relative to combined breast and local lymph node irradiation, isolated breast irradiation does not appear to be associated with a higher risk of locoregional relapse or death among breast cancer patients with pN0 status after neo-adjuvant chemotherapy. These results need to be confirmed in a prospective study. (authors)

  8. Contribution à l'algorithmique et à la programmation efficace des nouvelles architectures parallèles comportant des accélérateurs de calcul dans le domaine de la neutronique et de la radioprotection

    OpenAIRE

    Jérôme, Dubois

    2011-01-01

    Dans le domaine des sciences et technologies, la simulation numérique est un élément-clé des processus de recherche ou de validation. Grâce aux moyens informatiques modernes, elle permet des expérimentations numériques rapides et moins coûteuses que des maquettes réelles, sans pour autant les remplacer totalement, mais permettant de réaliser des expérimentations mieux calibrées. Dans le domaine de la physique des réacteurs et plus précisément de la neutronique, le calcul de valeurs propres es...

  9. Apreçamento de derivativos bidimensionais

    Directory of Open Access Journals (Sweden)

    Hugo Daniel de Oliveira Azevedo

    2005-09-01

    Full Text Available Neste artigo analisamos o apreçamento de contratos que tenham seus resultados atrelados a mais de um ativo subjacente, em especial, opções bidimensionais. Para isto usamos a fórmula desenvolvida por Margrabe (1978 e o modelo de árvores de Rubinstein (1991a. Em seguida apresentamos exemplos práticos de opções bidimensionais e apreçamos estas opções. Além disto, sugerimos a incorporação de outros instrumentos, negociados no exterior, ao mercado de derivativos brasileiro.In this article we analyze the pricing of contracts that have their payoffs linked to more than one underlying asset, in special, bidimensional options. To achieve this purpose we use the formula developed by Margrabe (1978 and the tree model of Rubinstein (1991a. Next, we present practical examples of bidimensional options and price these options. Moreover we suggest the incorporation of two other instruments, negotiated abroad, to the Brazilian derivative markets

  10. Design Characteristics of the Passive Auxiliary Feedwater System in APR+

    International Nuclear Information System (INIS)

    The passive auxiliary feedwater system (PAFS) is a typical passive safety system implemented for the APR+. The auxiliary feedwater system (AFWS) in the APR1400, which is the reference plant of the APR+, consists of two motor driven pumps, two turbine driven pumps, two water storage tanks, and related pipes and valves. The AFWS feeds emergency water to steam generators to cool down the reactor coolant system when the main feedwater is lost. To enhance the safety, the PAFS replaces the AFWS with a passive condensation heat exchanger (PCHX), a passive condensation cooling tank (PCCT), and a few valves and pipes in the APR+ design. In this paper, we propose the design requirements and conceptual design of the PAFS in order to evaluate the operability of the PAFS, to develop the APR+'s general arrangements for the auxiliary building, and to identify the important parameters to be quantified by experiments

  11. Radio-induced neuropathology: from early effects to late sequelae. Rat behavioural and metabolic studies after sublethal total body irradiation; Neuropathologie radio-induite: des effets precoces aux sequelles tardives. Etudes comportementales et metaboliques chez le rat apres irradiation globale subletale

    Energy Technology Data Exchange (ETDEWEB)

    Martigne, A.P.

    2010-05-15

    The radioresistance dogma of Central Nervous System (CNS) is now obsolete. Recent progress in neuroscience allow us to reconsider the radiation-induced cognitive dysfunctions observed after radiation therapy or after a nuclear accident, and to devise appropriate diagnostic and therapeutic means. We have developed a Rat model to study the effects of total body irradiation at a sublethal dose (4.5 Gy). This leads to impaired learning and memory of a task being acquired during the first month - which is prevented by administration of a radioprotector (amifostine) - while it does not appear to affect retrograde memory. Early, an apoptotic wave occurs in the sub-ventricular zone, 5 to 9 hours after exposure, while neuro-genesis is suppressed. Two days after irradiation, the metabolic study conducted by NMR HRMAS (High Resolution Magic Angle Spinning) suggests the presence of cerebral oedema and the study of brain lipids in liquid NMR confirms the membrane damages (elevated cholesterol and phospholipids). The lipid profile is then normalized while a gliosis appears. Finally, 1 month post-irradiation, the elevation of GABA, an inhibitory neurotransmitter, in 2 separate brain structures, occurs simultaneously with a taurine decrease in the hippocampus that lasts 6 months. Our integrated model allows validating bio-markers measurable in vivo NMR spectroscopy - the next experimental stage - and testing new radiation-protective agents. (author)

  12. Design Characteristics of the APR+ Containment Spray System

    International Nuclear Information System (INIS)

    We, KEPCO E and C, are implementing APR+ design development phase II project, which is owned by the KHNP. The APR+ Containment Spray (CS) System is developed as a four (4) 100%-capacity train system which shares the pumps, heat exchangers, valves, and piping with the Shutdown Cooling (SC) System, meeting the N+2 design concept (capable of satisfying the safety function with a single failure and a concurrent component unavailability due to maintenance) and still maintaining the number and capacity of the system components similar to the APR1400 CS System and SC System combined. The design concept and system configuration of the APR+ CS System are presented

  13. Design Characteristics of the APR+ Containment Spray System

    Energy Technology Data Exchange (ETDEWEB)

    Doh, Gyu Bong; Park, Jong Ha; Chang, Jae Wang [KEPCO Engineering and Construction Co., Yongin (Korea, Republic of)

    2012-05-15

    We, KEPCO E and C, are implementing APR+ design development phase II project, which is owned by the KHNP. The APR+ Containment Spray (CS) System is developed as a four (4) 100%-capacity train system which shares the pumps, heat exchangers, valves, and piping with the Shutdown Cooling (SC) System, meeting the N+2 design concept (capable of satisfying the safety function with a single failure and a concurrent component unavailability due to maintenance) and still maintaining the number and capacity of the system components similar to the APR1400 CS System and SC System combined. The design concept and system configuration of the APR+ CS System are presented

  14. Performance analysis of a Passive Auxiliary Feedwater System in APR+

    International Nuclear Information System (INIS)

    The Advanced Power Reactor Plus (APR+), which is a GEN III+ reactor based on the APR1400, is being developed in Korea. In order to enhance the safety of the APR+, a passive auxiliary feedwater system (PAFS) has been adopted in the APR+. The PAFS replaces the conventional active auxiliary feedwater system (AFWS) by introducing a natural driving force mechanism while maintaining the system function of cooling the primary side and removing the decay heat. The purpose of this paper is to evaluate the performance of the PAFS under design basis events using best-estimated thermalhydraulic codes

  15. Vingt ans après…

    Directory of Open Access Journals (Sweden)

    François Burgat

    2002-05-01

    Full Text Available Le dixième numéro des Chroniques Yéménites, publié vingt ans après la création du Centre Français d'Archéologie et de Sciences Sociales de Sanaa reflète des ambitions souvent exprimées: donner une chance aux jeunes chercheurs et couvrir un large éventail disciplinaire au service de l'affirmation de la vocation régionale du Centre. Depuis Sanaa ou Paris, chercheurs, doctorants ou stagiaires, de l'Ecole normale supérieure, de l'INALCO, de l'Université de Sanaa et de bon nombre d'institu...

  16. Direct or photostimulated luminescence after X-Ray irradiation of divalent europium in alkaline earth compounds containing some halides; Luminescence directe ou photostimulee apres irradiation X de l'europium divalent dans des familles de composes alcalino-terreux comportant un halogene

    Energy Technology Data Exchange (ETDEWEB)

    Merigou, C

    1990-10-15

    With a view for digitizing of radiological images, the luminescent properties of divalent europium in diverse halogen compounds involving strontium or barium have been studied. In halogen-rich compounds (MCl{sub 2}, M{sub 4}OCl{sub 6}, M{sub 5}SiO{sub 4}Cl{sub 6},... where M is Sr or Ba), the thermal extinction of the emission begins only above 300 K. High densities of coloured spots have been produced with X-ray irradiation. The combining of these 2 features has led to the obtention of high yields for argon laser stimulated luminescence in the case of Sr{sub 5}SiO{sub 4}Cl{sub 5}Br:Eu halogen silicate. Although these yields are high they stay below that of BaXF:Eu which is usually used in photon-stimulated screens.

  17. Performance Analysis of APR+ PAFS for CDF evaluation

    International Nuclear Information System (INIS)

    The Advanced Power Reactor Plus (APR+), which is a GEN III+ reactor based on the APR1400, is being developed in Korea. In order to enhance the safety of the APR+, a passive auxiliary feedwater system (PAFS) has been adopted. The PAFS replaces the conventional active auxiliary feedwater system (AFWS) by introducing a natural driving force mechanism while maintaining the system functions of cooling the primary side and removing the decay heat. As the PAFS completely replaces the conventional active auxiliary feedwater system (AFWS), it is necessary to verify its cooling capacity for the core damage frequency (CDF) evaluation. This paper discusses the cooling performance of the PAFS in transient accidents

  18. Performance Analysis of APR+ PAFS for CDF evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Sang Hee; Kim, Han Gon [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2011-05-15

    The Advanced Power Reactor Plus (APR+), which is a GEN III+ reactor based on the APR1400, is being developed in Korea. In order to enhance the safety of the APR+, a passive auxiliary feedwater system (PAFS) has been adopted. The PAFS replaces the conventional active auxiliary feedwater system (AFWS) by introducing a natural driving force mechanism while maintaining the system functions of cooling the primary side and removing the decay heat. As the PAFS completely replaces the conventional active auxiliary feedwater system (AFWS), it is necessary to verify its cooling capacity for the core damage frequency (CDF) evaluation. This paper discusses the cooling performance of the PAFS in transient accidents

  19. Involvement of Stringent Factor RelA in Expression of the Alkaline Protease Gene aprE in Bacillus subtilis

    OpenAIRE

    Hata, Michihiro; Ogura, Mitsuo; Tanaka, Teruo

    2001-01-01

    Expression of Bacillus subtilis aprE, encoding an extracellular alkaline protease, is positively regulated by phosphorylated DegU, the regulator of a two-component regulatory system, DegS-DegU. We found that the expression of an aprE′-′lacZ fusion was greatly reduced in a disruption mutant with a mutation of relA, which encodes the stringent factor RelA. The level of DegU in the relA mutant was similar to that in the wild-type cell. A relA degU double mutation did not result in a further decr...

  20. The development of a passive auxiliary feedwater system in APR+

    International Nuclear Information System (INIS)

    The Advanced Power Reactor Plus (APR+) is being developed in Korea. APR+ is a GEN III+ reactor on the basis of the APR1400. To meet the requirements of GEN III+ reactors, the economics and the safety of the APR+ are further enhanced. One of the basic principles of APR+ safety systems is the adoption of hybrid safety systems. Passive safety systems replace the current active safety systems from an economic point of view. The passive aux. feedwater system (PAFS) is one of the passive safety features adopted in the APR+. The PAFS replaces the conventional active auxiliary feedwater system by introducing a natural driving force mechanism while maintaining the system's basic Junction of cooling down the primary side and removing the decay heat. In order to satisfy the single failure criterion, the PAFS is composed of two independent trains. Each train has one steam condensing heat exchanger of 100% capability and one PCCT (Passive Condensation Cooling water Tank) of 100% capability. Basic design is underway and separate effect tests and integral effect tests will be performed to demonstrate the performance of the PAFS. (authors)

  1. Monitoring and characterization of radioactive wastes by neutronic methods; Controle et caracterisation de dechets radioactifs par methodes neutroniques

    Energy Technology Data Exchange (ETDEWEB)

    Lyoussi, A. [CEA Cadarache, Dept. d' Etudes des Dechets, DED, Lab. de Developpement de Mesures Nucleaires, 13 - Saint Paul lez Durance (France)

    2001-07-01

    In order to characterize a radioactive waste parcel, different techniques of analysis and nondestructive testing were developed during these last years. The most used are the gamma spectrometry, the passive neutron counting, the neutron interrogation and the photon interrogation with a electron accelerator. The neutron measurement are divided in two families: the active measurement and the passive measurement. The passive methods consist in measuring the neutron radiation emitted spontaneously by the contaminant. The active methods consist in the detection of neutron radiation after an external neutron irradiation. In this article are exposed the principal needs that lead to develop the neutrons measurement. Then, the passive and active neutron measurements are described. (N.C.)

  2. The core design of the advanced power reactor plus (APR+)

    International Nuclear Information System (INIS)

    Advance Power Reactor Plus (APR+), a pressurized water reactor and an improved nuclear power reactor based on the Advanced Power Reactor 1400 MWe (APR1400) in Korea, has been developed with 18-month cycle operation strategy from its initial core. The APR+ core power is 4290 MWth which corresponds to a 1500 MWe class nuclear power plant. The reactor core consists of 257 fuel assemblies. Comparing with APR1400 core design, 16 fuel assemblies are added. Its cycle length is expected about 450 EFPD directly from initial core, although most of previous other plants had been started according to their annual or 15-month cycle operation schedule at their initial core and gone to 18-month after third - fourth cycle. In order to reduce the peaking power, fuel pin configurations of the assembly, are optimized by using some low enriched fuel pins and gadolinia bearings. APR+ core has been met the requirements as well as the above cycle length requirement; 1) peaking factor, 2) Negative MTC(Moderator Temperature Coefficient), 3) sufficient shutdown margin, 4) convergent Xenon stability Index. The maximum rod burnup and the discharge fuel assembly burnup are also satisfied those of the limit. It is expected to acquire the standard design approval by the end of 2012 by the Korean nuclear regulatory. (authors)

  3. Development of Reference Source Terms for EU-APR1400

    International Nuclear Information System (INIS)

    These source terms are developed for the typical U. S. NPP and do not reflect the design characteristics of EU-APR1400 (1,400 MWe PWR) which will be applied for the EUR certification in European countries. The process of developing the RST for EU-APR1400 is to undergo a similar process that NUREG-1465 had gone through when it came out with its proposed source terms. The purpose of this study is to develop the EU-APR1400 design-specific RST complied with the EUR. The Large LOCA is the reference equence used in the NUREG-1465 evaluation, whereas the EUAPR1400 risk-significant sequences are dominated by small LOCA and non-LOCA sequences. Moreover, when considering the EU-APR1400 has many design features to mitigate the consequences of severe accident phenomena, it is not surprising that the aspects of both release fractions and durations are distinctly different from NUREG-1465. This RST will be continuously updated to reflect to the design features of EU-APR1400, and then, be used as the reference for design purposes such as criteria satisfaction of radioactivity releases, equipment survivability, control room habitability for severe accident, and so on

  4. Study of human mesenchymal stem cells plasticity into radiation injured tissues in a N.O.D./S.C.I.D. mouse model: therapeutic approach of the multiple organ dysfunction; Etude de la capacite plastique des Cellules Souches Mesenchymateuses humaines (CSM) apres irradiation du tissu receveur: approche therapeutique de l'atteinte multiorgane radio-induite

    Energy Technology Data Exchange (ETDEWEB)

    Francois, S

    2006-01-15

    The therapeutic potential of bone marrow-derived human mesenchymal stem cells (h.M.S.C.) has recently been brought into the spotlight of many fields of research. One possible application of the approach is the repair of injured tissues arising from side effects of radiation treatments and accidents. The first challenge in cell therapy is to assess the quality of the cell and the ability to retain their differentiation potential during the expansion process. Efficient delivery to the sites of intended action is also necessary. We addressed both questions using h.M.S.C. cultured and then infused to Non Obese Diabetes/Severe Combined Immunodeficiency (N.O.D./S.C.I.D.) mice submitted to total body irradiation. Further, we tested the impact of additional local irradiation superimposed to total body irradiation (T.B.I.), as a model of accidental irradiation. Our results showed that the h.M.S.C. used for transplant have been expanded without significant loss in their differentiation capacities. After transplantation into adult unconditioned mice, h.M.S.C. not only migrate in bone marrow but also into other tissues. Total body irradiation increased h.M.S.C. implantation in bone marrow and muscle and further led to engraftment in brain, heart, and liver. Local irradiation, in addition to T.B.I., increased both specific homing of injected cells to the injured tissues and to other tissues outside the local irradiation field. M.S.C. may participate to restoration of intestinal homeostasis 3 days post abdominal irradiation. This study suggests that using the potential of h.M.S.C. to home to various organs in response to tissue injuries could be a promising strategy to repair the radiation induced damages. (author)

  5. System Response Analysis of LOCV for APR1400 Using KNAP

    International Nuclear Information System (INIS)

    Korea Electric Power Research Institute (KEPRI) of Korea Electric Power Corporation (KEPCO) has been developed the non-loss-of-coolant accident (non-LOCA) analysis methodology, called as the Korea Non-LOCA Analysis Package (KNAP), for the typical Optimized Power Reactor 1000 (OPR1000) plants. Considering current licensing methodology conducted by ABB-CE, however, the KNAP could be applied to Advanced Power Reactor 1400 (APR1400). In spite of some difference in components of two plant types, there is a close resemblance between their nuclear steam supply systems (NSSS). So, in this study, the loss of condenser vacuum (LOCV) event were analyzed using KNAP for APR1400 to estimate the feasibility of the application and the results were compared with those given in APR1400 Standard Safety Analysis Report (SSAR), which were calculated using the CESEC-III code of ABB-CE. Through the study, it was concluded that the KNAP could be applicable to APR1400 on the view point of LOCV event

  6. Verbal Communication in the APR1400 Advanced Control Room

    International Nuclear Information System (INIS)

    This paper introduces the characteristics of communication in advanced main controlghd rooms (MCRs) and some observations from a case study performed for APR1400 MCR. In advanced MCRs, operators need not maintain the same communication patterns as they do in conventional ones. For example, a senior reactor operator (SRO) does not have to rely on board operators for information acquisition and can get any information from his/her own workstation. This situation may also bring about new problems in MCRs such as lack of shared situation awareness and collaboration between MCR operators. To cope with these problems, the APR1400 MCR adapts several approaches in design and training for encouraging operators to communicate with each other. This paper introduces the possible changes of communication patterns and the countermeasures in design and training. Some findings from an integrated system validation for Shin Kori Units 3 and 4 are also presented

  7. Nuclear power protection systems performance study for APR 1400

    International Nuclear Information System (INIS)

    A study on plant protection system (PPS) of advanced power reactor (APR) 1400 which is one of the system to maintain nuclear power plant (NPP) operation safe and controllable has been conducted. The controllability aspect of NPP operation is an important aspect to assure the NPP operation safe and reliable. Accordingly, the study is limited in the performance of PPS. The method used in the study includes literature study, data collection, as well as review and analysis. The purpose of this study is to recognize that PPS performance can assure the NPP operation safely and controllable. The study concludes that there are several measurement parameters that actuate PPS systems to trip the reactor such as high pressurizer pressure, low pressurizer pressure, high containment building pressure and also manual trip. These parameters are measured by parallel sensor with parallel arrangement set on set point suitable with APR 1400 safety standard. (author)

  8. Preliminary Results Of LOCA Problem For APR1400 Reactor

    International Nuclear Information System (INIS)

    Several features of NPP with APR1400 nuclear reactor during a loss of coolant accident (LOCA) are investigated in this study. The report describes some main design characteristics of an engineering safety systems of APR1400 and the thermal hydraulic calculation results for steady-state using MARS and RELAP/SCDAPSIM codes. Large Break LOCA accident has been analyzed and evaluated based on acceptable criteria for ECCS given by US NRC. The results from cold leg break LOCA with broken area of 0.0465 m2 in case of high pressure safety injection system (HPSI) failed to operate or 2 and 4 HPSI pumps are activated. The preliminary results of this work is a part of collaboration between INST researchers and KAERI experts in using RELAP tool for safety analysis of NPPs. (author)

  9. Conceptual Design of Passive Containment Cooling System Based on APR+

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Byongguk; No, Heecheon [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2013-05-15

    Passive Auxiliary Feedwater System (PAFS) is expected to work well under extended SBO, but is vulnerable to extended SBO coupled with loss of coolant accident (LOCA). Various reactors have been developed, such as AP1000, ESBWR, and KERENA, with passive containment cooling systems (PCCSs) dealing with the accident scenario of SBO with LOCA. The performance of the PCCSs is already or almost validated. Though PCCS is well adopted into BWRs, there has been no success in PWRs with concrete containment. In this paper, we suggest a new PCCS based on APR+ and represent scoping analysis results. The Fukushima accident proved the importance of treating extended SBO. To deal with extended SBO with LOCA scenario, the PCCS based on APR+ is suggested and evaluated roughly for the first time as a PWR with concrete containment.

  10. Design features of Advanced Power Reactor (APR) 1400 steam generator

    International Nuclear Information System (INIS)

    Advanced Power Reactor 1400 (APR 1400) which is to achieve the improvement of the safety and economical efficiency has been developed by Korea Hydro and Nuclear Power Co., Ltd. (KHNP) with the support from industries and research institutes. The steam generator for APR 1400 is an evolutionary type from System 80+, which is the recirculating U-tube heat exchanger with integral economizer. Compared to the System 80+ steam generator, it is focused on the improved design features, operating and design conditions of APR 1400 steam generator. Especially, from the operation experience of Korean Standard Nuclear Power Plant (KSNP) steam generator, the lessons-learned measures are incorporated to prevent the tube wear caused by flow-induced vibration (FIV). The concepts for the preventive design features against FIV are categorized to two fields; flow distribution and dynamic response characteristics. From the standpoint of flow distribution characteristics, the egg-crate flow distribution plate (EFDP) is installed to prevent the local excessive flow loaded on the most susceptible tube to wear. The parametric study is performed to select the optimum design with the efficient mitigation of local excessive flow. ATHOS3 Mod-01 is used and partly modified to analyze the flow field of the APR 1400 steam generator. In addition, the upper tube bundle support is designed to eliminate the presence of tube with a low natural frequency. Based on the improved upper tube bundle support, the modal analysis is performed and compared with that of System 80+. Using the results of flow distribution and modal analysis, the two mechanisms of flow-induced vibration are investigated; fluid-elastic instability (FEI) and random turbulence excitation (RTE). (authors)

  11. Regulatory Approach for Oversight of APR1400 Constructions

    International Nuclear Information System (INIS)

    This presentation treats of the regulatory approach for the oversight of the APR 1400. It first introduces the licensing system in Korea and after that it describes the inspection program during the construction and commissioning, operation and finally decommissioning phase. Special emphasis is put on the installation inspection (52 items), cold functional inspections (77 items), hydrostatic and hot functional test inspection (23 items) and initial fuel loading and startup test inspections (33 items)

  12. Performance verification test for APR1400 fluidic device

    International Nuclear Information System (INIS)

    Using the full scale test facility called 'VAPER', five sets of repeatability tests have been carried out to verify the performance of the Fluidic Device which is adopted in the standard design of APR1400. Quality assurance program for the APR1400 Fluidic Device verification test has been developed and applied to each set of repeatability test procedure, and precise calibration for major measuring instruments has been performed. Thus, the highest reliability and integrity of the test results was ensured. Throughout the present tests, the repeatability of the major parameter related with APR1400 Fluidic Device performance has been sufficiently confirmed. Total K factor in the actual plant system would be about 16 at high flow condition and about 105 at low flow condition, which is similar to the design goal (about 17 at high flow condition and about 100 at low flow condition) The results of the present research contributes to the smooth construction of Sin-Kori units 3 and 4, and to the promotion of domestic analytic capability for the LOCA of advanced LWR

  13. Pseudomonas syringae evades host Immunity by degrading flagellin monomers with alkaline protease AprA

    OpenAIRE

    Pel, M.J.C.; Van Dijken, A.J.H.; Bardoel, B.W.; Seidl, M. F.; Van der Ent, S.; van Strijp, J. A. G.

    2014-01-01

    Bacterial flagellin molecules are strong inducers of innate immune responses in both mammals and plants. The opportunistic pathogen Pseudomonas aeruginosa secretes an alkaline protease called AprA that degrades flagellin monomers. Here, we show that AprA is widespread among a wide variety of bacterial species. In addition, we investigated the role of AprA in virulence of the bacterial plant athogen P. syringae pv. tomato DC3000. The AprA-deficient DC3000 ΔaprA knockout mutant was significantl...

  14. Engineering and Directed Evolution of a Ca2+ Binding Site A-Deficient AprE Mutant Reveal an Essential Contribution of the Loop Leu75–Leu82 to Enzyme Activity

    OpenAIRE

    Eliel R. Romero-García; Alfredo Téllez-Valencia; María F. Trujillo; José G. Sampedro; Hugo Nájera; Arturo Rojo-Domínguez; Jesús García-Soto; Mario Pedraza-Reyes

    2009-01-01

    An aprE mutant from B. subtilis 168 lacking the connecting loop Leu75–Leu82 which is predicted to encode a Ca2+ binding site was constructed. Expression of the mutant gene (aprEΔLeu75–Leu82) produced B. subtilis colonies lacking protease activity. Intrinsic fluorescence analysis revealed spectral differences between wild-type AprE and AprEΔL75–L82. An AprEΔL75–L82 variant with reestablished enzyme activity was selected by directed evolution. The no...

  15. Design of a load following controller for APR+ nuclear plants

    International Nuclear Information System (INIS)

    A load-following operation in APR+ nuclear plants is necessary to reduce the need to adjust the boric acid concentration and to efficiently control the control rods for flexible operation. In particular, a disproportion in the axial flux distribution, which is normally caused by a load-following operation in a reactor core, causes xenon oscillation because the absorption cross-section of xenon is extremely large and its effects in a reactor are delayed by the iodine precursor. A model predictive control (MPC) method was used to design an automatic load-following controller for the integrated thermal power level and axial shape index (ASI) control for APR+ nuclear plants. Some tracking controllers employ the current tracking command only. On the other hand, the MPC can achieve better tracking performance because it considers future commands in addition to the current tracking command. The basic concept of the MPC is to solve an optimization problem for generating finite future control inputs at the current time and to implement as the current control input only the first control input among the solutions of the finite time steps. At the next time step, the procedure to solve the optimization problem is then repeated. The support vector regression (SVR) model that is used widely for function approximation problems is used to predict the future outputs based on previous inputs and outputs. In addition, a genetic algorithm is employed to minimize the objective function of a MPC control algorithm with multiple constraints. The power level and ASI are controlled by regulating the control banks and part-strength control banks together with an automatic adjustment of the boric acid concentration. The 3-dimensional MASTER code, which models APR+ nuclear plants, is interfaced to the proposed controller to confirm the performance of the controlling reactor power level and ASI. Numerical simulations showed that the proposed controller exhibits very fast tracking responses.

  16. Review of APR+ Level 2 PSA. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Lehner, John R. [Brookhaven National Lab. (BNL), Upton, NY (United States); Mubayi, Vinod [Brookhaven National Lab. (BNL), Upton, NY (United States); Pratt, W. Trevor [Brookhaven National Lab. (BNL), Upton, NY (United States); Kim, Do Sam [Korea Institute of Nuclear Safety (KINS), Daejeon (Korea, Republic of); Cho, Yong Jin [Korea Institute of Nuclear Safety (KINS), Daejeon (Korea, Republic of); Cho, Sang Jin [Korea Institute of Nuclear Safety (KINS), Daejeon (Korea, Republic of); Kim, In Goo [Korea Institute of Nuclear Safety (KINS), Daejeon (Korea, Republic of)

    2012-02-17

    Brookhaven National Laboratory (BNL) assisted the Korea Institute of Nuclear Safety (KINS) in reviewing the Level 2 Probabilistic Safety Assessment (PSA) of the APR+ Advanced Pressurized Water Reactor (PWR) prepared by the Korea Hydro & Nuclear Power Co., Ltd (KHNP) and KEPCO Engineering & Construction Co., Inc. (KEPCO-E&C). The work described in this report involves a review of the APR+ Level 2 PSA submittal [Ref. 1]. The PSA and, therefore, the review is limited to consideration of accidents initiated by internal events. As part of the review process, the review team also developed three sets of Requests for Additional Information (RAIs). These RAIs were provided to KHNP and KEPCO-E&C for their evaluation and response. This final detailed report documents the review findings for each technical element of the PSA and includes consideration of all of the RAIs made by the reviewers as well as the associated responses. This final report was preceded by an interim report [Ref. 2] that focused on identifying important issues regarding the PSA. In addition, a final meeting on the project was held at BNL on November 21-22, 2011, where BNL and KINS reviewers discussed their preliminary review findings with KHNP and KEPCO-E&C staffs. Additional information obtained during this final meeting was also used to inform the review findings of this final report. The review focused not only on the robustness of the APR+ design to withstand severe accidents, but also on the capability and acceptability of the Level 2 PSA in terms of level of detail and completeness. The Korean nuclear regulatory authorities will decide whether the PSA is acceptable and the BNL review team is providing its comments for KINS consideration. Section 2.0 provides the basis for the BNL review. Section 3.0 presents the review of each technical element of the PSA. Conclusions and a summary are presented in Section 4.0. Section 5.0 contains the references.

  17. Design of a Load Following Controller for APR+ Nuclear Plants

    International Nuclear Information System (INIS)

    The load-following operation of an APR+ nuclear plants is required to restrain the adjustment of boric acid concentration and to efficiently control the control rods for the flexibility of the operation. Especially, axial flux distribution disproportion that is usually caused by load-following operation in a reactor core induces xenon oscillation because the absorption cross-section of xenon is extremely large and its effects in a reactor are delayed by the iodine precursor. Rapid and smooth power maneuvering has its benefits in view of the economical and safe operation of reactors, so it is required that the controller is efficiently designed. Therefore, the load-following operation of an APR+ nuclear plants needs the ultimate automatic control and the advanced control method that satisfies the conditions such as the flexibility, safety and convenience. A model predictive control (MPC) method is applied to design an automatic load-following controller for the integrated thermal power level and axial shape index (ASI) control for an APR+ nuclear plants. Some tracking controllers use only the current tracking command. On the other hand, since MPC considers future commands in addition to the current tracking command, the MPC can achieve better tracking performance. Therefore, the MPC has been applied very much to the control of industrial process systems. The basic concept of the MPC is to solve an optimization problem for generating finite future control inputs at current time and to implement as the current control input only the first control input among the solutions of the finite time steps. At the next time step, the second control input is not implemented and the procedure to solve the optimization problem is then repeated. The power level and the ASI are controlled by the regulating control banks and part-strength control banks together with the automatic adjustment of boric acid concentration. The 3-dimensional MASTER code, which models the APR+ nuclear

  18. Pseudomonas syringae evades host immunity by degrading flagellin monomers with alkaline protease AprA.

    Science.gov (United States)

    Pel, Michiel J C; van Dijken, Anja J H; Bardoel, Bart W; Seidl, Michael F; van der Ent, Sjoerd; van Strijp, Jos A G; Pieterse, Corné M J

    2014-07-01

    Bacterial flagellin molecules are strong inducers of innate immune responses in both mammals and plants. The opportunistic pathogen Pseudomonas aeruginosa secretes an alkaline protease called AprA that degrades flagellin monomers. Here, we show that AprA is widespread among a wide variety of bacterial species. In addition, we investigated the role of AprA in virulence of the bacterial plant pathogen P. syringae pv. tomato DC3000. The AprA-deficient DC3000 ΔaprA knockout mutant was significantly less virulent on both tomato and Arabidopsis thaliana. Moreover, infiltration of A. thaliana Col-0 leaves with DC3000 ΔaprA evoked a significantly higher level of expression of the defense-related genes FRK1 and PR-1 than did wild-type DC3000. In the flagellin receptor mutant fls2, pathogen virulence and defense-related gene activation did not differ between DC3000 and DC3000 ΔaprA. Together, these results suggest that AprA of DC3000 is important for evasion of recognition by the FLS2 receptor, allowing wild-type DC3000 to be more virulent on its host plant than AprA-deficient DC3000 ΔaprA. To provide further evidence for the role of DC3000 AprA in host immune evasion, we overexpressed the AprA inhibitory peptide AprI of DC3000 in A. thaliana to counteract the immune evasive capacity of DC3000 AprA. Ectopic expression of aprI in A. thaliana resulted in an enhanced level of resistance against wild-type DC3000, while the already elevated level of resistance against DC3000 ΔaprA remained unchanged. Together, these results indicate that evasion of host immunity by the alkaline protease AprA is important for full virulence of strain DC3000 and likely acts by preventing flagellin monomers from being recognized by its cognate immune receptor. PMID:24654978

  19. Quality Control of Concrete Structure For APR1400 Construction

    International Nuclear Information System (INIS)

    Nuclear structure shall be constructed to protect internal facilities in the normal operation against external accidents such as the radiation shielding, earthquakes and to be leak-proof of radioactive substances to the external environment in case of loss of coolants. containment and auxiliary building of nuclear power plants are built in reinforced concrete structures to maintain these protection functions. Nuclear structures shall be designed to ensure soundness in operation since they are located on the waterfront where is easy do drain the cooling water and so deterioration and damage of concrete structures caused by seawater can occur. Durability is ensured for concrete structures of APR1400, a Korea standard NPP, in compliance with all safety requirements. In particular, owners perform quality control directly on the production and pouring of cast in place concrete for the concrete structure construction to make sure concrete structures established with quality homogeneity and durability. This report is to look into the quality control standard and management status of cast in place concrete for APR1400 construction

  20. Severe Accident Management Strategy for EU-APR1400

    International Nuclear Information System (INIS)

    In EU-APR1400, the dedicated instrumentation and mitigation features for SAM are being developed to keep the integrity of containment and to prevent the uncontrolled release of fission products. In this paper, SAM strategy for EU-APR1400 was introduced in stages. It is still under development and finally the Severe Accident Management Guidance will be completed based on this SAM Strategy. Severe accidents in a nuclear power plant are defined as certain unlikely event sequences involving significant core damage with the potential to lead to significant releases according to EUR 2.1.4.4. Even though the probability of severe accidents is extremely low, the radiation release may cause serious effect on people as well as environment. Severe Accident Management (SAM) encompasses those actions which could be considered in recovering from a severe accident and preventing or mitigating the release of fission products to the environment. Whether those actions are successful or not, depending on a progression status of a severe accident to mitigate the consequences of severe accident phenomena to limit the release of radioactive materials keeping the leak tightness of the Primary Containment, and finally to restore transient severe accident progression into a controlled and safe states

  1. Analysis on the Direct Vessel Injection Line Break Accident at APR+ Standard Design

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Youngho; Yang, Huichang [TUEV Rheinland Korea Ltd., Seoul (Korea, Republic of); Kim, Kap [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-10-15

    APR+ (Advanced Power Reactor +) is the newest design variation of APR1400. The main characteristics of APR+, compared with APR1400, are passive safety systems and dedicated systems for severe accident mitigation. APR+ is under review for standard design certification. In this study, thermal hydraulic analysis on the Direct Vessel Injection (DVI) line break accident postulated in APR+ design was performed. Comparisons of the major parameters which can represent the overall accident behavior during DVI line break accident, several discrepancies between this study and reference data were found and such discrepancies include actuation timing of SIPs and SITs, and also include parameter behaviors of break flow rate and PCT at the accident initiation. These differences were mainly from the different thermal hydraulic models in simulation codes. The behavioral differences for break flow as well as peak cladding temperatures will be examined further as a next step for this study.

  2. Performance validation of advanced safety features of APR

    International Nuclear Information System (INIS)

    This paper briefly introduces recent progress, which is mainly being performed at KAERI, in design and performance validation tests of advanced safety features for the APR+ (Advanced Power Reactor plus). The main safety technologies included in the APR+ standard design improvement are an advanced Direct Vessel Injection Plus (DVI+), Fluidic Device Plus (FD+), and Passive Auxiliary Feedwater System (PAFS). The validation tests of advanced safety features are performed using scaled down model testes. They include: 1/5-Scale air-water test, DVI+ duct vibration test, full scale duct injection test, 1/240-Scale PAFS separate effect test, and ATLAS-PAFS integral effect test. The other design verification tests are also performed. They include: Full scale 3-Fuel assembly cross flow test, 1/5-Scale reactor flow distribution test (to be performed, under construction), Core simulator calibration developing test for core flow test, Full scale advanced Fluidic Device (FD+), CEDM test-to be performed, and IVR and core capture test. The core flow and reactor flow tests are being performed by both experimental and CFD (Computational Fluid Dynamics) analysis for the test facility development. The ECC bypass test is performed using 1/5-scale air-water test facility. The duct test facility. The 1/5-scale core barred vibration test with DVI duct is also performed under the both wet and dry condition. The design goal of PAFS is replacing an auxiliary feedwater system with a passive Steam Generator (SG) secondary cooling system of APR+. In PAFS, the core decay heat is ideogram in the Passive Condensation Cooling Tank (PCCT). The PCCT is located on the top of Auxiliary building. To validate the cooling performance of PAFS, a separate effect test loop has been constructed at KAERI (Korea Atomic Energy Research Institute), which is named PASCAL (PAFS Condensing heat removal Assessment Loop). To quantify the tube heat transfer coefficient of the horizontal heat exchanger, a full scale

  3. Écrire (d’après

    Directory of Open Access Journals (Sweden)

    Denis Saint-Amand

    2009-03-01

    Full Text Available De l’allusion à la citation, de l’emprunt criard au plagiat déguisé, les jeux d’influences et d’aller-retour avec tel ou tel modèle, grand ou mineur, ont toujours participé de l’élaboration du texte littéraire. Si l’intertextualité est sans aucun doute née en même temps que l’écriture (ou quelques minutes après et que, comme ont pu le montrer notamment Jacques-Philippe Saint-Gérand et Daniel Sangsue, les facettes multiples qu’elle déploie ont toujours suscité l’attention des hommes de lettre...

  4. Écrire (d’)après

    OpenAIRE

    Denis Saint-Amand

    2009-01-01

    De l’allusion à la citation, de l’emprunt criard au plagiat déguisé, les jeux d’influences et d’aller-retour avec tel ou tel modèle, grand ou mineur, ont toujours participé de l’élaboration du texte littéraire. Si l’intertextualité est sans aucun doute née en même temps que l’écriture (ou quelques minutes après) et que, comme ont pu le montrer notamment Jacques-Philippe Saint-Gérand et Daniel Sangsue, les facettes multiples qu’elle déploie ont toujours suscité l’attention des hommes de lettre...

  5. 14 CFR Appendix H to Part 23 - Installation of An Automatic Power Reserve (APR) System

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Installation of An Automatic Power Reserve (APR) System H Appendix H to Part 23 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT... AIRPLANES Pt. 23, App. H Appendix H to Part 23—Installation of An Automatic Power Reserve (APR) System...

  6. Pseudomonas syringae evades host immunity by degrading flagellin monomers with alkaline protease AprA

    NARCIS (Netherlands)

    Pel, Michiel J C; van Dijken, Anja J H; Bardoel, Bart W; Seidl, Michael F; van der Ent, Sjoerd; van Strijp, Jos A G; Pieterse, Corné M J

    2014-01-01

    Bacterial flagellin molecules are strong inducers of innate immune responses in both mammals and plants. The opportunistic pathogen Pseudomonas aeruginosa secretes an alkaline protease called AprA that degrades flagellin monomers. Here, we show that AprA is widespread among a wide variety of bacteri

  7. Pseudomonas syringae evades host Immunity by degrading flagellin monomers with alkaline protease AprA

    NARCIS (Netherlands)

    Pel, M.J.C.; Van Dijken, A.J.H.; Bardoel, B.W.; Seidl, M.F; Van der Ent, S.; Van Strijp, J.A.G.

    2014-01-01

    Bacterial flagellin molecules are strong inducers of innate immune responses in both mammals and plants. The opportunistic pathogen Pseudomonas aeruginosa secretes an alkaline protease called AprA that degrades flagellin monomers. Here, we show that AprA is widespread among a wide variety of bacteri

  8. Thermal-hydraulic Analysis of SGTR for Supporting PSA in APR+

    International Nuclear Information System (INIS)

    The Advanced Power Reactor Plus (APR+) is being developed in Korea. To enhance the safety of the APR+, a passive auxiliary feedwater system (PAFS) has been adopted in the APR+. The PAFS completely replaces the conventional active auxiliary feedwater system (AFWS). It is operated by a natural driving force mechanism when demanding auxiliary feedwater. It could maintain the system function of cooling the primary side and remove the decay heat while operated PAFS. For estimating the safety of APR+ design, the probabilistic safety assessment (PSA) of APR+ is performed. As the PAFS replaces the conventional AFWS, it is required to verify the cooling capacity of PAFS for the accurate evaluation. For this reason, this paper discusses the cooling performance of the PAFS while transient accidents

  9. An ATWS Analysis for EU-APR1400 Following the European Utility Requirement

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Minshin; Lee, Cheolshin; Sohn, Jongjoo [KEPCO Engineering and Construction Company., Inc., Daejeon (Korea, Republic of)

    2013-05-15

    This paper presents the results of the evaluation of the ATWS events with respect to Reactor Coolant System (RCS) overpressure and re-criticality for the European APR1400 (EU-APR1400) according to European Utility Requirement (EUR). This paper evaluates the ATWS impact on the EU-APR1400 by applying EUR. Based on the results of safety analysis for ATWS events, all the acceptance criteria for EUR can be satisfied due to the proper functioning of ATWS mitigation systems. However the four events are investigated only in this paper, and hence the results of this paper can not be concluded that the EU-APR1400 design satisfy all requirements for the EUR. Therefore, a further study for all Design Basis Event Category 2 (DBC2) events with ATWS needs to be performed in order to assess the comprehensive impact of ATWS events for the EU-APR1400 design.

  10. Sexual dysfunctions after prostate cancer radiation therapy; Dysfonctions sexuelles apres irradiation pour cancer de la prostate

    Energy Technology Data Exchange (ETDEWEB)

    Droupy, S. [Service d' urologie-andrologie, CHU Caremeau, 30 - Nimes (France)

    2010-10-15

    Sexual dysfunctions are a quality of life main concern following prostate cancer treatment. After both radiotherapy and brachytherapy, sexual function declines progressively, the onset of occurrence of erectile dysfunction being 12-18 months after both treatments. The pathophysiological pathways by which radiotherapy and brachytherapy cause erectile dysfunction are multi-factorial, as patient co-morbidities, arterial damage, exposure of neurovascular bundle to high levels of radiation, and radiation dose received by the corpora cavernosa at the crurae of the penis may be important in the aetiology of erectile dysfunction. Diagnosis and treatment of postradiation sexual dysfunctions must integrate pre-therapeutic evaluation and information to provide to the patient and his partner a multidisciplinary sexual medicine management. (authors)

  11. Gamma irradiation effect on the enzymatic activities of horseradish and apple peroxidases

    International Nuclear Information System (INIS)

    The behavior at low-dose exposure (0.033-0.4 kGy) of horseradish peroxidase (HRP) and of two different purified fractions of apple (Jonathan cultivar) peroxidases (named APR1S and APR2S) was studied. The HRP solutions were added with either 0.32 M fructose or glucose in order to study their effect on enzymes activity response under γ (137Cs, dose rate 0.4 kGy/h) irradiation. The obtained results showed similar behavior between HRP-sugar-added solution and apple fraction with higher oligosaccharides content (APR2S) undergoing low-dose treatment. The same pattern was observed between unglycosylated HRP and APR1S with lower oligosaccharides content. These similarities gave us the possibility to conclude that the presence of oligosaccharides, in more or less quantities, influences in the same way the peroxidases activity, from different plant species, exposed to γ irradiation

  12. Development of Core Simulator (CoSi) for APR1400 And Analysis of LPPT Result using APR1400-CoSi

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Sang-Rae; Kim, Yong-Bae; Lee, Eun-Ki [KHNP-CRI, Daejeon (Korea, Republic of)

    2014-10-15

    According to NRC guidelines, Low Power Physics Test (LPPT) is required to be performed in low temperature/low pressure (160 .deg. C/42.2 kg/cm{sup 2}) as well as NOT/NOP (291.3 .deg. C/158.2 kg/cm{sup 2}) because Shin-Kori Unit 3 is FOAK nuclear power plant. Low Power Physics Test (LPPT) is essential to verify the nuclear design and robustness of reactor safety. LPPT consists of initial criticality, Point of Adding Heat (POAH), All Rod Out (ARO) Boron Concentration, Isothermal Temperature Coefficient (ITC), Control Rod Worth measurements and so on. KHNP-CRI has developed the Core Simulator for APR1400 (APR1400-CoSi) in order to improve the ability performing the LPPT. Especially, APR1400-CoSi has enhanced capability to calculate the full Core neutronic parameters by revising RAST-K that is three dimensional real time core kinetic program. APR1400-CoSi has been developed for education-training of Low Power Physics Test(LPPT). Particularly, APR1400-CoSi has an enhanced capability to calculate the full core neutronic parameters by revising RAST-K which is a three dimensional real time core kinetics program. Low Power Physics Test (LPPT) was performed using APR1400-CoSi and the results showed very similar values with the predicted ones. In other words, the initial core model of Shin-Kori Unit 3 in APR1400-CoSi system has been verified to be appropriate enough. Also, it was confirmed that the test range of Low Power Physics Test (LPPT) reamains effective even though the largest incremental bank reactivity is inserted in core by analyzing the power change during the rod SWAP test.

  13. Development of Core Simulator (CoSi) for APR1400 And Analysis of LPPT Result using APR1400-CoSi

    International Nuclear Information System (INIS)

    According to NRC guidelines, Low Power Physics Test (LPPT) is required to be performed in low temperature/low pressure (160 .deg. C/42.2 kg/cm2) as well as NOT/NOP (291.3 .deg. C/158.2 kg/cm2) because Shin-Kori Unit 3 is FOAK nuclear power plant. Low Power Physics Test (LPPT) is essential to verify the nuclear design and robustness of reactor safety. LPPT consists of initial criticality, Point of Adding Heat (POAH), All Rod Out (ARO) Boron Concentration, Isothermal Temperature Coefficient (ITC), Control Rod Worth measurements and so on. KHNP-CRI has developed the Core Simulator for APR1400 (APR1400-CoSi) in order to improve the ability performing the LPPT. Especially, APR1400-CoSi has enhanced capability to calculate the full Core neutronic parameters by revising RAST-K that is three dimensional real time core kinetic program. APR1400-CoSi has been developed for education-training of Low Power Physics Test(LPPT). Particularly, APR1400-CoSi has an enhanced capability to calculate the full core neutronic parameters by revising RAST-K which is a three dimensional real time core kinetics program. Low Power Physics Test (LPPT) was performed using APR1400-CoSi and the results showed very similar values with the predicted ones. In other words, the initial core model of Shin-Kori Unit 3 in APR1400-CoSi system has been verified to be appropriate enough. Also, it was confirmed that the test range of Low Power Physics Test (LPPT) reamains effective even though the largest incremental bank reactivity is inserted in core by analyzing the power change during the rod SWAP test

  14. Implementation of Low Boron Core for APR1400 Initial Cycle

    International Nuclear Information System (INIS)

    Low boron capability of a nuclear power plant is rather a qualitative specification requiring the nuclear power plant to be shut down by control rods alone at any time of a plant cycle according to EUR. The reduction of soluble boron is beneficial since it gives the reduction of the corrosive effects in the plant system and improves plant safety giving more negative MTC. Thus, it is necessary to reduce the amount of soluble boron for the criticality to achieve the low boron capability. However, the reduction of soluble boron has its own set of specific challenges that must be overcome. There are two methods to enable the reduction of soluble boron without modifying plant system significantly. The goal of this study is to investigate the loading pattern to achieve the soluble boron reduction for Shin-Kori Unit 5 APR1400 initial core using the low and high content gadolinia burnable absorbers with standard fuel rod enrichment and to verify the feasibility of low boron core with conventional gadolinia burnable absorbers only. For this study, KARMA has been employed to solve 2-D Transport equation, and ASTRA is used for full core analysis. It was possible to achieve the low boron core for APR1400 Cycle 1 using extended usage of two types of gadolinia burnable absorbers sacrificing fuel cycle economy a little bit while enhancing plant safety significantly. Gd rod patterns within an assembly were optimized through geometrical weighting and loading pattern was developed based on these patterns. The amount of soluble boron reduction achieved is 45.4%. The improvement in plant safety is significant resulting in the reduction of least negative best-estimate MTC by about 4 pcm. Also shutdown margin is increased slightly for low boron core. However, the behavior of axial power shape turns out to be undesirable showing a relatively large fluctuation caused by the more negative MTC. It was found that the low boron core might impose kind of operational difficulty. It is usually

  15. Extended Station Blackout Coping Capabilities of APR1400

    Directory of Open Access Journals (Sweden)

    Sang-Won Lee

    2014-01-01

    Full Text Available The Fukushima Dai-ichi nuclear power plant accident shows that an extreme natural disaster can prevent the proper restoration of electric power for several days, so-called extended SBO. In Korea, the government and industry performed comprehensive special safety inspections on all domestic nuclear power plants against beyond design bases external events. One of the safety improvement action items related to the extended SBO is installation of external water injection provision and equipment to RCS and SG. In this paper, the extended SBO coping capability of APR1400 is examined using MAAP4 to assess the effectiveness of the external water injection strategy. Results show that an external injection into SG is applicable to mitigate an extended SBO scenario. However, an external injection into RCS is only effective when RCS depressurization capacity is sufficiently provided in case of high pressure scenarios. Based on the above results, the technical basis of external injection strategy will be reflected on development of revised severe accident management guideline.

  16. APR+ PAFS Cooling Performance Analysis using RELAP5

    International Nuclear Information System (INIS)

    To enhance safety and reliability of nuclear power plant in domestic industry, passive safety system design has been introducing. Especially, passive auxiliary feedwater system (PAFS) has been applied to the advanced power reactor plus (APR+). PAFS is a facility that replaces an active auxiliary feedwater system (AFWS) in the existing plant. The system function is to remove the generating heat of primary system during transient and accidents unless main feedwater system is available. PAFS consists of a passive condensate cooling tank (PCCT), a heat exchanger, valves, and pipes as shown in Fig. 1. PAFS design is considered that its performance ensure the safety function. But it is difficult that the performance of PAFS is determined quantitatively unlike AFWS. Because AFWS can be controlled on its flow and enthalpy but PAFS can't be controlled on them. The characteristic of passive safety system can be changed along transient and accident. Therefore some considerations are required about how to determine the PAFS performance and how to find the conservative condition to evaluate it in respect to transient and accidents

  17. Conceptual design of passive containment cooling system based on APR+

    International Nuclear Information System (INIS)

    The accident of the Fukushima nuclear power plant left a profound message toward the need for a passive cooling system which can operate under the extended station blackout. These days, nuclear institutions in Korea are developing Advanced Power Reactor Plus (APR+). Its distinct characteristic lies on the passive auxiliary feed water system (PAFS) which removes decay heat to a passive condensation cooling tank (PCCT) by natural convection. Though the system is expected to work well under station blackout, the system becomes useless under the loss of coolant accident (LOCA) combined with station blackout. This paper aims at using existing heat exchangers of PAFS and PCCT under LOCA to cool the reactor as well as the containment in a fully passive way. To enhance the condensation rate of heat exchangers in PCCT, we need to produce convective flow in the PCCS heat exchangers. Therefore, the whole region of the concrete containment is divided into 3 chambers: inner, outer, PCCS chambers. An outer chamber is disposed to collect non-condensable gas. The condensate is stored in a condensate storage tank (CST) and injected into the reactor by gravity. This system makes a closed circuit to work indefinitely. A scoping analysis for the containment pressure is performed as a function of various parameters: outer chamber volume and number of tubes in heat exchangers. (author)

  18. Modal analysis of an ECC duct for APR+ reactor barrel

    International Nuclear Information System (INIS)

    Advanced Power Reactor Plus (APR+) provides four Direct Vessel Injection (DVI) ducts on the reactor barrel to enhance the performance of Emergency Core Cooling System (ECCS). Several studies on safety analysis have verified the excellent performance of the DVI duct. In this study, from the viewpoint of mechanical integrity, modal analyses of two full-scaled DVI ducts have been presented; both numerical analysis and modal tests have been performed in air and water. It was found that the numerical simulation and modal test coincide with each other. The DVI duct is a thin shell of 5 mm thickness, so that harmonic responses to RCP blade passing frequencies should be checked. The dominant passing frequencies are known to be 20, 40, 60, 120 and 240 Hz. In addition, an interesting thing in this study is that added mass effect by coolant seems to be so significant that the natural frequency of the ducts under water could be considerably low as compared with those in air; the natural frequency under water is 60 % lower than that in air. (author)

  19. Verification of SAMG entry condition for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Yun, Junghyun; Kim, Taewan; Kim, Jonghyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    In the wake of the Fukushima accident, severe accident management has become important more than ever. While Emergency Operating Procedures (EOPs) focuses on cooling down the core during a design basis accident, the prime objective of severe accident management guideline (SAMG) is to prevent the release of radioactive material into the environment during a severe accident. Only one fixed value of core exit temperature (CET) has been applied for several decades to different types of nuclear power plants (NPPs) in Korea. Although the different types of NPPs have different cladding materials and system designs, the identical CET, i. e., 650 .deg. C, is applied as the entry condition to the SAMG of all the NPPs (except CANDU plants), i. e., Westinghouse type, OPR1000, and APR1400. In this paper, the transition point is re-evaluated for dominant severe accident sequences; station black-out (SBO), small break loss of coolant accident (SBLOCA), and me dium break loss of coolant accident (MBLOCA). In cases of SBO and SBLOCA, the current SAMG entry condition seems proper, while it needs to be reconsidered for MBLOCA case.

  20. APR+ PAFS Cooling Performance Analysis using RELAP5

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kyung Jin; Hong, Soon Joon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2011-05-15

    To enhance safety and reliability of nuclear power plant in domestic industry, passive safety system design has been introducing. Especially, passive auxiliary feedwater system (PAFS) has been applied to the advanced power reactor plus (APR+). PAFS is a facility that replaces an active auxiliary feedwater system (AFWS) in the existing plant. The system function is to remove the generating heat of primary system during transient and accidents unless main feedwater system is available. PAFS consists of a passive condensate cooling tank (PCCT), a heat exchanger, valves, and pipes as shown in Fig. 1. PAFS design is considered that its performance ensure the safety function. But it is difficult that the performance of PAFS is determined quantitatively unlike AFWS. Because AFWS can be controlled on its flow and enthalpy but PAFS can't be controlled on them. The characteristic of passive safety system can be changed along transient and accident. Therefore some considerations are required about how to determine the PAFS performance and how to find the conservative condition to evaluate it in respect to transient and accidents

  1. Study on Maintenance Personnel Development Plan For The Exported APR1400 Commissioning

    International Nuclear Information System (INIS)

    This paper indicates ways to develop maintenance personnel for the exported APR1400 commissioning. The exported APR1400 has not been experienced ay maintenance yet, and requirements for maintenance personnel have not been clarified yet. Based on sound maintenance experience, KEPCO Plant Service and Engineering Company (KEPCO KPS) has studied on maintenance training and career requirement to establish a development plan of the maintenance personnel for the exported nuclear power plant. By defining manpower and training requirement, and mobilization plan, we expect to secure reliability of the exported APR1400

  2. Current status of integrated HFE V and V system of APR1400

    International Nuclear Information System (INIS)

    The first Advanced Light Water Reactor called Advanced Power Reactor (APR1400) has many specific features such as passive safety features, digital I and C, and digitalized main control room design. This digital-based neo-concept main control room design needs comprehensive verification and validation process to get the license for construction. An integrated system for APR1400 MMIS design validation is under development by KEPRI with the participating of KHNP. The facility which is based on the NUREG/CR-6393 and ANS3.5 can simulate all of the dynamic functions and responses of APR1400, and measure the human factors by using conventional subject methods and measuring the operator's biological signals. This system will be used in human factors V and V process of the PRM (NUREG0711) of APR1400 MMIS design. (authors)

  3. Development of human factors validation system for the advanced control room of APR1400

    International Nuclear Information System (INIS)

    A human factors validation system for the main control room (MCR) of Advanced Power Reactor 1400 MWe (APR1400) has been developed as it adopts digitalized human-system interfaces (HSIs). The integrated validation system is composed of process/plant models, HSIs, and the human performance evaluation support system (HUPESS). A real-time thermal-hydraulic code, RELAP5 R/T, was used and modified to simulate the dynamic characteristics of the APR1400, and simulation software, 3KeyMaster, was used to model the balance of plant systems. The HSIs developed in this study include all facilities in the APR1400 MCR, such as large display panels, 3 identified operator workstations, and a safety console. In addition, the remote shutdown workstation has been developed. The display systems in the HSIs have been developed using ProcSee, which is a software tool for developing and displaying dynamic graphical user interfaces. This paper describes the configurations of HSIs including display systems, the dynamic models of the APR1400 simulator, the instructor station, and the HUPESS. This paper also presents the results of plant simulation performance tests at transient compared with the results of RELAP5/MOD3.3 calculations. The human factors validation system for the advanced control room of APR1400 provides high degrees of physical, functional, and dynamic fidelities, and can be used in the validation process of the APR1400 HSI design. (author)

  4. Reliability enhancement of APR + diverse protection system regarding common cause failures

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Y. G.; Kim, Y. M.; Yim, H. S. [KEPCO Engineering and Construction Company, Inc., 1045 Daedeok-Daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Lee, S. J. [Chungnam National Univ., 99 Daehak-ro, Yuseong-gu, Daejeon 305-764 (Korea, Republic of)

    2012-07-01

    The Advanced Power Reactor Plus (APR +) nuclear power plant design has been developed on the basis of the APR1400 (Advanced Power Reactor 1400 MWe) to further enhance safety and economics. For the mitigation of Anticipated Transients Without Scram (ATWS) as well as Common Cause Failures (CCF) within the Plant Protection System (PPS) and the Emergency Safety Feature - Component Control System (ESF-CCS), several design improvement features have been implemented for the Diverse Protection System (DPS) of the APR + plant. As compared to the APR1400 DPS design, the APR + DPS has been designed to provide the Safety Injection Actuation Signal (SIAS) considering a large break LOCA accident concurrent with the CCF. Additionally several design improvement features, such as channel structure with redundant processing modules, and changes of system communication methods and auto-system test methods, are introduced to enhance the functional reliability of the DPS. Therefore, it is expected that the APR + DPS can provide an enhanced safety and reliability regarding possible CCF in the safety-grade I and C systems as well as the DPS itself. (authors)

  5. Reliability enhancement of APR + diverse protection system regarding common cause failures

    International Nuclear Information System (INIS)

    The Advanced Power Reactor Plus (APR +) nuclear power plant design has been developed on the basis of the APR1400 (Advanced Power Reactor 1400 MWe) to further enhance safety and economics. For the mitigation of Anticipated Transients Without Scram (ATWS) as well as Common Cause Failures (CCF) within the Plant Protection System (PPS) and the Emergency Safety Feature - Component Control System (ESF-CCS), several design improvement features have been implemented for the Diverse Protection System (DPS) of the APR + plant. As compared to the APR1400 DPS design, the APR + DPS has been designed to provide the Safety Injection Actuation Signal (SIAS) considering a large break LOCA accident concurrent with the CCF. Additionally several design improvement features, such as channel structure with redundant processing modules, and changes of system communication methods and auto-system test methods, are introduced to enhance the functional reliability of the DPS. Therefore, it is expected that the APR + DPS can provide an enhanced safety and reliability regarding possible CCF in the safety-grade I and C systems as well as the DPS itself. (authors)

  6. Evaluation of irradiated coating material specimens

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Jin; Nam, Seok Woo; Cho, Lee Moon [RCS Korea Co., Ltd., Seoul (Korea, Republic of)

    2007-12-15

    Evaluation result of irradiated coating material specimens - Coating material specimens radiated Gamma Energy(Co 60) in air condition. - Evaluation conditions was above 1 X 10{sup 4} Gy/hr, and radiated TID 2.0 X 10{sup 6} Gy. - The radiated coating material specimens, No Checking, Cracking, Flaking, Delamination, Peeling and Blistering. - Coating system at the Kori no. 1 and APR 1400 Nuclear power plant, evaluation of irradiated coating materials is in accordance with owner's requirement(2.0 X 10{sup 6} Gy)

  7. Neutronic exposure and early increase of IL-6, IL-8 and G-csf seric levels in non human primates; Elevation precoce des concentrations seriques d`IL-6, d`IL-8 et de G-CSF apres exposition neutronique

    Energy Technology Data Exchange (ETDEWEB)

    Van Uye, A.; Agay, D.; Edgard, L.; Cruz, C.; Mestries, J.C. [Centre de Recherches du Service de Sante des Armees, La Tronche, 38 - Grenoble (France)

    1997-12-31

    The aim of the work was to study some of the early events that trigger radiation-induced inflammatory response. Blood kinetic profiles of IL-6, IL-8 and G-CSF were monitored in male adult baboons (Papio sp.) within the first 24 hours following the exposure to a 6 Gy mixed neutron-gamma field. (authors)

  8. Engineering and Directed Evolution of a Ca2+ Binding Site A-Deficient AprE Mutant Reveal an Essential Contribution of the Loop Leu75–Leu82 to Enzyme Activity

    Directory of Open Access Journals (Sweden)

    Eliel R. Romero-García

    2009-01-01

    Full Text Available An aprE mutant from B. subtilis 168 lacking the connecting loop Leu75–Leu82 which is predicted to encode a Ca2+ binding site was constructed. Expression of the mutant gene (aprEΔLeu75–Leu82 produced B. subtilis colonies lacking protease activity. Intrinsic fluorescence analysis revealed spectral differences between wild-type AprE and AprEΔL75–L82. An AprEΔL75–L82 variant with reestablished enzyme activity was selected by directed evolution. The novel mutations Thr66Met/Gly102Asp located in positions which are predicted to be important for catalytic activity were identified in this variant. Although these mutations restored hydrolysis, they had no effect with respect to thermal inactivation of AprEΔL75–L82  T66M  G102D. These results support the proposal that in addition to function as a calcium binding site, the loop that connects β-sheet e3 with α-helix c plays a structural role on enzyme activity of AprE from B. subtilis 168.

  9. Economics enhancement of APR1400 through the application of new construction methods

    International Nuclear Information System (INIS)

    The development of APR1400 (formerly KNGR) project is one of Korea's national G-7 projects, sponsored by the government and KHNP (Korea Hydro and Nuclear Power Co., Ltd.). APR1400, an evolutionary standard reactor with a thermal output of 4000MWt, upgrades the safety and economic competitiveness of nuclear power, incorporating cutting-edge advanced technologies, while standing on the proven experience of Optimized Power Reactor 1000(OPR1000, formerly KSNP) design. APR1400 has been adopted as the design for Shin-Kori Units 3 and 4. APR1400 development project consisted of three phases in order to check and make only necessary adjustments at the end of each phase and the standard design certification (DC) was issued in May 2002. The project set up the top-tier requirements for the design's safety, economy, operability, maintainability, and construct ability in the earliest design stage. The requirements have been evaluated periodically during the design process, and the results of each evaluation were reflected in the final design. Shin-Kori Units 3 and 4 are the first APR1400 projects, and will be built near the Kori NPP site, where four units are currently in operation and two OPR1000 (Improved Korean Standard Nuclear Power Plant) units called Shin-Kori Units 1 and 2 are under construction. Shin-Kori Units 3 and 4 will be constructed based on APR1400 standardized design, while incorporating the site characteristics and construction and operation experiences of OPR1000. This paper describes new construction methods to improve economics and construct ability of APR1400 to meet the target schedule, which is set to 41.5 months from the first concrete pouring to the fuel loading for the Nth plant. The new construction methods consist of 'Open Top Method' for installation of major NSSS equipment, 'Large Modularization' for the Building Structures, Reactor Vessel Internals and Major Components and deck plate method, etc

  10. Experimental and MARS code simulation of DVI line 25% and 50% break LOCAs using SNUF for APR1400

    International Nuclear Information System (INIS)

    APR1400, is an evolutionary PWR (Pressurized Water Reactor) based on the well-proven OPR1000 design. The APR1400 has adopted DVI (Direct Vessel Injection) system instead of CLI (Cold Leg Injection) system as advanced safety features of ECCS (Emergency Core Cooling System). The configuration of the improved ECCS in the APR1400 is completely different from that in the OPR1000 in which pipes for the safety water injection are connected to the cold leg. In APR1400, the safety water injection pipes are directly connected to the RPV (Reactor Pressure Vessel). Thus, the safety water injection system in the APR1400 is called the DVI (Direct Vessel Injection) system. Moreover, safety water injections by the HPSI (High Pressure Safety Injection) pumps are mechanically separately in the APR1400.

  11. GOTHIC Simulation of APR1400 Auxiliary Charging Pump room heat up

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Hui-Un; Heo, Sun [KHNP, Daejeon (Korea, Republic of)

    2014-10-15

    As a part of the Advanced Power Reactor 1400 (APR1400) U. S. Nuclear Regulatory Commission Design Certification (NRC DC) project, we have been investigating Auxiliary Charging Pump (ACP) room heat up. With reference to the design specification of the ACP room, we determined input information and developed a GOTHIC model of the APR1400 ACP room. This calculation model is described herein, and representative results from the calculation are presented as well. The results of the present paper are used to determine the integrity of ACP operating in the accident. APR 1400 GOTHIC model was developed for ACP room heat up calculation. Calculation results confirm that door opening is cooling the room properly. It is found that the difference due to the surface option of heat conductors is insignificant. Based on this result, further studies should be performed to confirm integrity of ACP.

  12. Evaluation of ex-vessel steam explosion load for APR1400 using IFCI

    International Nuclear Information System (INIS)

    The load of ex-vessel steam explosion for APR1400 is evaluated using the IFCI 6.0 code developed by US NRC. The IFCI code is applied to analyse the FCI experiments of FARO-28, KROTOS-44 and TROI-13 as a code V/V process. The load of ex-vessel steam explosion for APR1400 is calculated based on the conditions applied during the code V/V and the load was compared with the analysis result of licence. The IFCI analysis result shows that the integrity of cavity might not be guaranteed once a steam explosion occurs and the result is in contrast with that of licence

  13. Evolution of glycaemia during irradiation syndrome; Evolution de la glycemie au cours du syndrome d'irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Raisonnier, A. [Commissariat a l' Energie Atomique, Fontenay aux Roses (France). Centre d' Etudes Nucleaires

    1967-03-15

    The evolution of glycaemia following irradiation has been followed in the rat and pig. The results concerning a case of human accidental exposure have also been included. The author has tried to see whether the observed variations are reproducible and have a prognostic value. (author) [French] L'evolution de la glycemie a ete suivie, chez le rat et le porc, apres irradiation. Les resultats relatifs a une irradiation accidentelle humaine sont egalement rapportes. L'auteur cherche a definir si les variations observees sont reproductibles et ont une valeur pronostique. (auteur)

  14. The Alberta Pregnancy Outcomes and Nutrition (APrON) cohort study : rationale and methods

    NARCIS (Netherlands)

    Kaplan, Bonnie J.; Giesbrecht, Gerald F.; Leung, Brenda M. Y.; Field, Catherine J.; Dewey, Deborah; Bell, Rhonda C.; Manca, Donna P.; O'Beirne, Maeve; Johnston, David W.; Pop, Victor J.; Singhal, Nalini; Gagnon, Lisa; Bernier, Francois P.; Eliasziw, Misha; McCargar, Linda J.; Kooistra, Libbe; Farmer, Anna; Cantell, Marja; Goonewardene, Laki; Casey, Linda M.; Letourneau, Nicole; Martin, Jonathan W.

    2014-01-01

    The Alberta Pregnancy Outcomes and Nutrition (APrON) study is an ongoing prospective cohort study that recruits pregnant women early in pregnancy and, as of 2012, is following up their infants to 3 years of age. It has currently enrolled approximately 5000 Canadians (2000 pregnant women, their offsp

  15. Assessment of Capability of MARS Code for Safety Evaluation of APR+ PAFS

    International Nuclear Information System (INIS)

    In South Korea, advanced power reactor plus (APR+), as a Korean specific reactor, is currently under development for the export strategy. In order to raise competitiveness of the APR+ in the world market, it is necessary to develop the original technology for the improved technology, economics, and safety features. For this purpose, a passive auxiliary feedwater system (PAFS) was adopted as an improved safety design concept of APR+: and then there have been many efforts to develop the PAFS. According to PAFS design concept, PAFS can completely replace the auxiliary feedwater system. When the design basis accident, in which feedwater is not available, occurs, the PAFS can remove the residual heat in the core and then prevent the core damage. In order to develop the safety evaluation system for APR+ PAFS, it is required to assess the calculation capability of MARS code for the passive system with the horizontal type heat exchanger. For this purpose, the main contents of this study are: 1) to simulate the TH phenomena such as natural circulation and horizontal condensation heat transfer in NOKO experiment using MARS-KS, 2) to compare the simulation results between RELAP5 and MARS for PAFS input model

  16. CFD Simulation of Acoustic-Induced Vibration in Main Steam Line of APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Sang Gyu; Kim, Tae Jun; Kim, Han Gon [Korea Hydro and Nuclear Power, Daejeon (Korea, Republic of)

    2012-05-15

    In recently, many boiling water reactors (BWRs) implement extended power uprate (EPU) to increase economic benefits. After EPU, Quad Cities power plant has been experienced damage of steam dryers due to acoustic-induced vibration. Acoustic resonance is produced by the interaction between the sound field and an unstable shear layer when the dry steam flows across the closed branch pipes such as safety relief valve(SRV). The unsteady vortices are separated at the leading edge of branch pipe and generated fluctuating pressure wave. After this experience, US-NRC issued that the licensee for new type of reactor should perform a vibration assessment program for an adverse flow effect in the main steam line in accordance with regulatory guideline 1.20 revision 3. In Korea, KHNP CRI implements comprehensive vibration program for steam generator of APR1400 and evaluates acoustic-induced vibration in main steam line using a commercial CFD code, ANSYS CFX 13.0. This paper deals with benchmark analysis to obtain applicability and reliability of commercial code for prediction of acoustic resonance phenomenon in case of single branch pipe test. Based on the benchmark analysis, analysis of main steam line in APR1400 plant is performed. In case of APR1400, five main steam safety valves are installed in the main steam line. Finally, this paper shows a prediction result of acoustic induced vibration characteristic in main steam system of APR1400

  17. An integral effect test on the feedwater line break of APR1400 with the ATLAS facility

    International Nuclear Information System (INIS)

    An integral effect test on the feedwater line break (FLB) was performed with the ATLAS facility for an APR1400 as a typical secondary system transient. The objectives of the present FLB tests are to understand the accident progression of the FLB scenario based on the APR1400 preliminary safety analysis report (PSAR) and to assess the prediction capability of system analysis codes such as the MARS, RELAP5, TRACE and SPACE. The main concern of the present FLB test is the peak RCS pressure and the major parameters affecting the peak RCS pressure are the break size, the break location, potential for reverse flow, initial pressurizer level and the initial SG level. The present test is performed for a break on the pipe connected to the economizer with a typical break size. The initial steady-state conditions and the sequence of event of FLB scenario for the APR1400 were successfully simulated with the ATLAS facility. In the present paper, major thermal-hydraulic phenomena such as the system pressures, the collapsed water levels, and the break flow rate are presented and discussed. It could be concluded that the APR1400 has the capability of coping with the hypothetical FLB scenario with an adequate set of controlling devices and proper setpoints. This integral effect test data could also be used to evaluate the prediction capability of existing safety analysis codes of MARS, RELAP5 and SPACE and to identify any code deficiency for an FLB simulation. (author)

  18. Assessment of Capability of MARS Code for Safety Evaluation of APR+ PAFS

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Seong Su; Lee, Byung Chul [Seoul National University, Seoul (Korea, Republic of); Park, Ju Yeop; Seul, Kwang Won [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2011-05-15

    In South Korea, advanced power reactor plus (APR+), as a Korean specific reactor, is currently under development for the export strategy. In order to raise competitiveness of the APR+ in the world market, it is necessary to develop the original technology for the improved technology, economics, and safety features. For this purpose, a passive auxiliary feedwater system (PAFS) was adopted as an improved safety design concept of APR+: and then there have been many efforts to develop the PAFS. According to PAFS design concept, PAFS can completely replace the auxiliary feedwater system. When the design basis accident, in which feedwater is not available, occurs, the PAFS can remove the residual heat in the core and then prevent the core damage. In order to develop the safety evaluation system for APR+ PAFS, it is required to assess the calculation capability of MARS code for the passive system with the horizontal type heat exchanger. For this purpose, the main contents of this study are: 1) to simulate the TH phenomena such as natural circulation and horizontal condensation heat transfer in NOKO experiment using MARS-KS, 2) to compare the simulation results between RELAP5 and MARS for PAFS input model

  19. Greta Kaits 9. apr. 1928 - 29. aug. 1946 : [luuletused] / Mats Traat

    Index Scriptorium Estoniae

    Traat, Mats, 1936-

    2008-01-01

    Sisu : Greta Kaits 9. apr. 1928 - 29. aug. 1946 ; Villem Hänilane 1898 - 1952 ; Peeter Pedak 1897 - 1953 ; Max Äidse 1903 - 1959 ; Lavinia Laidam ; Buchard Pruus ; Sergei Krivokopõtov ; Allan Luht 5. VII 1962 - 17. V 2007 ; Karl Saarmets 9. III 1924 - 14. IX 1981 ; Raimo Ritsik

  20. Calculation of fuel and moderator temperature coefficients in APR1400 nuclear reactor by MVP code

    International Nuclear Information System (INIS)

    In this project, these fuel and moderator temperature coefficients were calculated in APR1400 nuclear reactor by MVP code. APR1400 is an advanced water pressurized reactor, that was researched and developed by Korea Experts, its electric power is 1400 MW. The neutronics calculations of full core is very important to analysis and assess a reactor. Results of these calculation is input data for thermal-hydraulics calculations, such as fuel and moderator temperature coefficients. These factors describe the self-safety characteristics of nuclear reactor. After obtaining these reactivity parameters, they were used to re-run the thermal hydraulics calculations in LOCA and RIA accidents. These thermal-hydraulics results were used to analysis effects of reactor physics parameters to thermal hydraulics situation in nuclear reactors. (author)

  1. Analysis of Air Cooling Performance in the Coil Stack Assembly for APR+ CEDMs

    International Nuclear Information System (INIS)

    The control element drive mechanisms (CEDMs) are electromechanical devices for withdrawing, inserting, holding or tripping the control element assemblies (CEAs). The driving power for CEDMs is supplied by the coil stack assembly mounted on the motor housing assembly. The Coil Stack assembly is heated by the motor housing assembly contacted with reactor coolant as well as electric resistance of coil. The CEDMs are cooled by air ventilation. The cooling air around the CEDMs flows into the individual cooling shroud and extracts heat from the coil stacks while it passes between the shroud and coil housing. The cooling performance of the CEDMs is closely related to the geometry configuration of coil stack assembly. The expansion of air passage and additional cooling fins are considered to improve the cooling performance of APR+ CEDMs. In this study the optimal design conditions of APR+ CEDMs are investigated by flow analysis

  2. Available Driving Head Following a Loss-of-Coolant Accident in the APR1400 Design

    International Nuclear Information System (INIS)

    The objective of in-vessel downstream effect (IDE) evaluation is to demonstrate that there is reasonable assurance that sufficient long-term core cooling (LTCC) is achieved with debris and chemical products which are postulated to be transported to the reactor vessel. To maintain LTCC, it should be demonstrated that the available head to drive emergency core cooling (ECC) flow into the core is greater than the head loss across the core due to possible debris buildup. In this paper, the available driving heads following a loss-of-coolant accident (LOCA) in the APR1400 design were presented. The available driving heads of the APR1400 design were calculated in case of HL break, CL break, and CL break after HLSO operation at the recirculation start time (700 seconds after ECC start). The break size spectrum will be analyzed to calculate the available driving head when the loop seal reformation happens after a small break LOCA

  3. External Reactor Vessel Cooling Strategy Application for APR1400 Station Blackout Scenarios

    International Nuclear Information System (INIS)

    In Korea, all NPPs implemented post-Fukushima measures. In U. S., the approach is to expand B5b strategy to build up FLEX strategies utilizing portable equipment. With portable pumps and connections, one can mitigate and respond to wide range of accidents. In this study, we examined the feasibility of cavity flooding using portable pumps for ERVC and its effectiveness in responding to extended SBO scenarios. The external reactor vessel cooling (ERVC) is one of important severe accident management (SAM) strategies adopted for APR1400. ERVC strategy is to remove decay heat from molten corium in lower plenum by submerging the vessel with water. The strategy requires water injection into cavity and APR1400 uses shutdown cooling pumps for this purpose, requiring electricity. Recent Fukushima accident shows the importance of mitigation capability against extended SBO scenarios

  4. Preliminary System Response Analysis of Rod Ejection Accident for APR1000

    International Nuclear Information System (INIS)

    Korea Electric Power Co. (KEPCO) has designed the Advanced Power Reactor 1000 (APR1000) plants implementing the advanced safety features to Optimized Power Reactor 1000 (OPR1000) plants. Prior to developing the detail design, the preliminary design project has been launched since the end of 2009 as a feasibility study. In spite of some difference in safety- related design concepts of two plant types, they could be treated as the same plants considering the main features or systems. In this study, the rod ejection accident (REA) event was analyzed using Korea Non-LOCA Analysis Package (KNAP) hot spot model (HSM) for APR1000 to examine the feasibility of the design concepts and the results were compared with those values calculated by the Safety Analysis Report (SAR) conditions of typical OPR1000 plants. Through the study, it was concluded that the design concepts and the analysis package could be applicable on the view point of REA

  5. External Reactor Vessel Cooling Strategy Application for APR1400 Station Blackout Scenarios

    Energy Technology Data Exchange (ETDEWEB)

    Tran, Quang Diep Khanh; Oh, Seung Jong [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of); Ro, Seo Mi [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    In Korea, all NPPs implemented post-Fukushima measures. In U. S., the approach is to expand B5b strategy to build up FLEX strategies utilizing portable equipment. With portable pumps and connections, one can mitigate and respond to wide range of accidents. In this study, we examined the feasibility of cavity flooding using portable pumps for ERVC and its effectiveness in responding to extended SBO scenarios. The external reactor vessel cooling (ERVC) is one of important severe accident management (SAM) strategies adopted for APR1400. ERVC strategy is to remove decay heat from molten corium in lower plenum by submerging the vessel with water. The strategy requires water injection into cavity and APR1400 uses shutdown cooling pumps for this purpose, requiring electricity. Recent Fukushima accident shows the importance of mitigation capability against extended SBO scenarios.

  6. CFD Analysis of Flow Characteristics in the PAFS PCCT for APR +

    International Nuclear Information System (INIS)

    The passive auxiliary feedwater system (PAFS) is one of the passive safety features adopted in the APR+. The PAFS has two independent high-pressure closed loops; each loop has a heat exchanger (U-tube bundles) submerged in a PCCT water pool. The PAFS cools the secondary system by heat transfer in a horizontal Utube in the PCCT. The cooling water in the PCCT is maintained at atmospheric pressure, so that boiling heat transfers at the surface of the U-tube and natural convection occurs in the PCCT water pool. The conventional system codes, such as the RELAP5 /Mod3.3 and the MARS codes, are inadequate for flow pattern analysis of this system. The purpose of this study is to analyze the flow characteristics in the PAFS PCCT for APR + utilizing a CFD code, CFX

  7. CFD Analysis of Flow Characteristics in the PAFS PCCT for APR +

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Mun Soo; Chun, Jong [KHNP, Daejeon (Korea, Republic of)

    2010-10-15

    The passive auxiliary feedwater system (PAFS) is one of the passive safety features adopted in the APR+. The PAFS has two independent high-pressure closed loops; each loop has a heat exchanger (U-tube bundles) submerged in a PCCT water pool. The PAFS cools the secondary system by heat transfer in a horizontal Utube in the PCCT. The cooling water in the PCCT is maintained at atmospheric pressure, so that boiling heat transfers at the surface of the U-tube and natural convection occurs in the PCCT water pool. The conventional system codes, such as the RELAP5 /Mod3.3 and the MARS codes, are inadequate for flow pattern analysis of this system. The purpose of this study is to analyze the flow characteristics in the PAFS PCCT for APR + utilizing a CFD code, CFX

  8. The Gravity Makeup on the LORHR Event during Mid-loop Operation for APR1400

    International Nuclear Information System (INIS)

    This paper is to investigate means of the available gravity makeup after the event to prevent or sustain the core uncovery and fuel failure for the typical advanced power reactor nuclear power plants (APR1400). Unlike the OPR1000 (optimized power reactor 1000 nuclear power plants), the refueling water storage tank of APR1400 cannot be used for gravity makeup since it is located on the bottom of the containment with a lower elevation than the reactor vessel. So, the other means of gravity makeup and their effect on the core uncovery are accounted. The use of the water used for the cask loading pit (CLP) during refueling or the safety injection line filling tank (SIFT), which are not designed for gravity makeup during the event, and safety injection tanks (SITs) are considered as the alternative source of makeup feed. The results show that gravity makeup of a SIT provides a sufficient operator action time for the LORHR with the station black out (SBO) during the mid-loop operation for the APR1400. From the LORHR event analysis, the effective means of gravity makeup for APR1400 to cope with this event concurrent loss of all AC power is determined as the gravity feed using SITs. Other means for gravity makeup using CLP or SIFT, which are not designed to mitigate the LORHR event, are evaluated as not effective to the event due to the large flow resistances and the low elevation head to overcome the system pressure increase during the LORHR. The use of one SIT and two SITs for the LORHR provides the core uncovery times as 3 hr 8 min and 4 hr 32 min extending 1 hr 15 min and 2 hr 38 min from the base case, respectively

  9. Acute exercise does not induce an acute phase response (APR) in Standardbred trotters

    OpenAIRE

    Kristensen, Lena; Buhl, Rikke; Nostell, Katarina; Bak, Lars; Petersen, Ellen; Lindholm, Maria; Jacobsen, Stine

    2014-01-01

    The purpose of the study was to investigate whether acute strenuous exercise (1600- to 2500-m race) would elicit an acute phase response (APR) in Standardbred trotters. Blood levels of several inflammatory markers [serum amyloid A (SAA), haptoglobin, fibrinogen, white blood cell count (WBC), and iron], muscle enzymes [creatinine kinase (CK) and aspartate transaminase (AST)], and hemoglobin were assessed in 58 Standardbred trotters before and after racing. Hemoglobin levels increased and iron ...

  10. APR-5000-XLS阵列封装返工系统

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    APR-5000-XLS阵列封装返工系统可处理BGA,CSP,LGA(Land Grid Army),Micro SMD,MLF(Micro Lead Frame),BCC(Bumped Chip Component)多种封装。其可处理的板尺寸达610mm×610mm(24.5”×24.5”),厚度达6.35mm(0.25”)。

  11. Critical heat flux for APR1400 lower head vessel during a severe accident

    International Nuclear Information System (INIS)

    Highlights: ► Studied boiling on downward-facing hemispherical vessel with asymmetric thermal insulator. ► Scaled the APR1400 lower head linearly down by 1/10 including ICI tubes and shear keys. ► Performed thermal analysis using ANSYS V11.0 to determine the internal temperature and heat flux. ► Performed tests to obtain the CHF with saturated demineralized water at atmospheric pressure. ► Measured CHF accounting for 3D random flow effect expected in the APR1400 application. -- Abstract: Corium Ablation Stopper Apparatus (CASA) has a downward-facing hemispherical vessel and geometrically asymmetric thermal insulator of the Advanced Power Reactor 1400 MWe (APR1400) scaled linearly down by 1/10, as well as sixty-one in-core instrumentation (ICI) tubes and four shear keys. The heated vessel plays a pivotal role in CASA depending on the configuration of the oxide pool and metal layer to bring about the focusing effect expected of a molten pool in the lower head during a severe accident. The heated vessel was designed through a trial-and-error method and thermal analysis. Thermal analysis was performed using ANSYS V11.0 to investigate the effect of the internal temperature and heat flux on the integral hemispherical copper vessel. The CASA tests were carried out to obtain the critical heat flux (CHF) with saturated and demineralized water at the atmospheric pressure (0.1 MPa). The CHF in the metal layer through the hemispherical channel was found to be lower than that in the ULPU-2400 configuration V data through the streamlined thermal insulator. The experimental CHF was measured and obtained through the CASA hemispherical heated surface accounting for the three-dimensional random flow effect expected in the APR1400 application

  12. The Gravity Makeup on the LORHR Event during Mid-loop Operation for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Cheol Woo; Lee, Yong Hee; Lee, Gyu Cheon; Kim, Shin Whan [KEPCO, Daejeon (Korea, Republic of)

    2015-05-15

    This paper is to investigate means of the available gravity makeup after the event to prevent or sustain the core uncovery and fuel failure for the typical advanced power reactor nuclear power plants (APR1400). Unlike the OPR1000 (optimized power reactor 1000 nuclear power plants), the refueling water storage tank of APR1400 cannot be used for gravity makeup since it is located on the bottom of the containment with a lower elevation than the reactor vessel. So, the other means of gravity makeup and their effect on the core uncovery are accounted. The use of the water used for the cask loading pit (CLP) during refueling or the safety injection line filling tank (SIFT), which are not designed for gravity makeup during the event, and safety injection tanks (SITs) are considered as the alternative source of makeup feed. The results show that gravity makeup of a SIT provides a sufficient operator action time for the LORHR with the station black out (SBO) during the mid-loop operation for the APR1400. From the LORHR event analysis, the effective means of gravity makeup for APR1400 to cope with this event concurrent loss of all AC power is determined as the gravity feed using SITs. Other means for gravity makeup using CLP or SIFT, which are not designed to mitigate the LORHR event, are evaluated as not effective to the event due to the large flow resistances and the low elevation head to overcome the system pressure increase during the LORHR. The use of one SIT and two SITs for the LORHR provides the core uncovery times as 3 hr 8 min and 4 hr 32 min extending 1 hr 15 min and 2 hr 38 min from the base case, respectively.

  13. An Experimental Investigation on APR1400 Penetration Weld Failure by Metallic Melt

    International Nuclear Information System (INIS)

    The penetrations are considered as the most vulnerable parts with respect to the reactor vessel failure when a core melt severe accident occurs and the corium reaches the lower head. Penetration tube failure modes can be divided into two categories; tube ejection out of the vessel lower head and rupture of the penetration tube outside the vessel. Tube ejection begins with degrading the penetration tube weld strength to zero as the weld is exposed to temperatures as high as the weld melting temperature, which is called weld failure, and then overcoming any binding force in the hole in the vessel wall that results from differential thermal expansion of the tube and vessel wall. Tube rupture assumes that the debris bed has melted the instrument tube inside the reactor and melt migrates down into the tube to a location outside the vessel wall where a pressure rupture can occur, thus breaching the pressure boundary. In the present paper, we have a focus on the tube ejection failure mode, specifically on the APR1400 weld failure by direct contact with a metallic melt. The objective is to investigate experimentally the ablation kinetics of an APR1400 penetration weld during the interactions with a metallic melt and to suggest the modification of the existing weld failure model. This paper involves the interaction experiments of two different metallic melts (metallic corium and stainless steel melts) with a weld specimen, and rough estimation of weld failure time. The interaction experiments between the metallic melts and an APR1400 penetration weld were performed to investigate the ablation kinetics of the penetration weld. Metallic corium and stainless steel melts were generated using an induction heating technique and interacted with a penetration weld specimen. The ablation rate of the weld specimen showed a range from 0.109 to 0..244 mm/s and thus the APR1400 penetration weld was estimated to be failed at hundreds of times after the interaction with the melt

  14. Food irradiation

    International Nuclear Information System (INIS)

    Food irradiation is a promising technology in which food products are exposed to a controlled amount of radiant energy to eliminate disease-causing bacteria. The process can also control parasites and insects, reduce spoilage and inhibit ripening and sprouting. Food irradiation is endorsed by the most important health organisations (WHO, CDC, USDA, FDA, EFSA, etc.) and allowed in nearly 40 Countries. It is to remember that irradiation is not a substitute either for comprehensive food safety programs or for good food-handling practices. Irradiated foods must be labelled with either the statement treated with radiation or treated by irradiation and the international symbol for irradiation, the radura. Some consumer associations suppose negative aspects of irradiation, such as increase of the number of free radicals in food and decrease of antioxidant vitamins that neutralize them

  15. Development of the Diverse Means for Reactor Shutdown Function of EU-APR1400

    International Nuclear Information System (INIS)

    This paper provides general descriptions of the EBS focusing on basic design characteristics such as system function, configuration and operation, and presents results from the preliminary verification of system performance. The diverse means for the reactor shutdown function of EU-APR1400 have been developed to comply with the diversity principle of the European design requirements of a new nuclear power plant. The preliminary verification of the EBS performance was done by the ATWS analysis. The analysis results show that the EBS was designed properly. Diversity is the fundamental principle in safety system design of a new nuclear power plant, which uses different mitigation measures to provide diverse ways of responding to a significant event. Regarding the diversity principle, EU-APR1400 (European APR1400) safety system should be in accordance with European design requirements. EBS (Emergency Boration System) is designed to provide the diverse means to shut down the reactor against ATWS (Anticipated Transient Without Scram) and to mitigate the event consequences in the EUAPR1400

  16. Assistant Personal Robot (APR): Conception and Application of a Tele-Operated Assisted Living Robot

    Science.gov (United States)

    Clotet, Eduard; Martínez, Dani; Moreno, Javier; Tresanchez, Marcel; Palacín, Jordi

    2016-01-01

    This paper presents the technical description, mechanical design, electronic components, software implementation and possible applications of a tele-operated mobile robot designed as an assisted living tool. This robotic concept has been named Assistant Personal Robot (or APR for short) and has been designed as a remotely telecontrolled robotic platform built to provide social and assistive services to elderly people and those with impaired mobility. The APR features a fast high-mobility motion system adapted for tele-operation in plain indoor areas, which incorporates a high-priority collision avoidance procedure. This paper presents the mechanical architecture, electrical fundaments and software implementation required in order to develop the main functionalities of an assistive robot. The APR uses a tablet in order to implement the basic peer-to-peer videoconference and tele-operation control combined with a tactile graphic user interface. The paper also presents the development of some applications proposed in the framework of an assisted living robot. PMID:27136552

  17. Single-tube condensation experiment in Passive Auxiliary Feedwater System of APR1400+

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Chang Wook; No, Hee Cheon; Yun, Bong Yo; Jeon, Byong Guk [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2012-05-15

    Conventional Korean nuclear power plants, Advanced Power Reactors (APR), are characterized by an active cooling system. However, Active cooling system may not prevent significant damage without any AC power source available for its operation as vividly illustrated through the recent Fukushima incident. In the APR1400+ to be designed, an independent passive cooling system was added in order to overcome the aforementioned shortcomings. In the Passive Auxiliary Feedwater System (PAFS), gravity force and density difference between steam and water are used. The system comprises of 240 condensation tubes to efficiently remove decay heat. Before applying the PAFS to APR1400+, the system's safety and heat removal performance must be verified. The present study experimentally evaluates the heat removal performance of a single tube in the PAFS. The objectives of SCOP (Single-tube Condensation experiment facility of PAFS) are the evaluation of the heat removal performance in the tube of the PAFS and database construction under various tube designs and test conditions. Reaching these objectives, we developed advanced measurement techniques for the amount of moisture, heat flux, and water film thickness.

  18. Assistant Personal Robot (APR: Conception and Application of a Tele-Operated Assisted Living Robot

    Directory of Open Access Journals (Sweden)

    Eduard Clotet

    2016-04-01

    Full Text Available This paper presents the technical description, mechanical design, electronic components, software implementation and possible applications of a tele-operated mobile robot designed as an assisted living tool. This robotic concept has been named Assistant Personal Robot (or APR for short and has been designed as a remotely telecontrolled robotic platform built to provide social and assistive services to elderly people and those with impaired mobility. The APR features a fast high-mobility motion system adapted for tele-operation in plain indoor areas, which incorporates a high-priority collision avoidance procedure. This paper presents the mechanical architecture, electrical fundaments and software implementation required in order to develop the main functionalities of an assistive robot. The APR uses a tablet in order to implement the basic peer-to-peer videoconference and tele-operation control combined with a tactile graphic user interface. The paper also presents the development of some applications proposed in the framework of an assisted living robot.

  19. Assistant Personal Robot (APR): Conception and Application of a Tele-Operated Assisted Living Robot.

    Science.gov (United States)

    Clotet, Eduard; Martínez, Dani; Moreno, Javier; Tresanchez, Marcel; Palacín, Jordi

    2016-01-01

    This paper presents the technical description, mechanical design, electronic components, software implementation and possible applications of a tele-operated mobile robot designed as an assisted living tool. This robotic concept has been named Assistant Personal Robot (or APR for short) and has been designed as a remotely telecontrolled robotic platform built to provide social and assistive services to elderly people and those with impaired mobility. The APR features a fast high-mobility motion system adapted for tele-operation in plain indoor areas, which incorporates a high-priority collision avoidance procedure. This paper presents the mechanical architecture, electrical fundaments and software implementation required in order to develop the main functionalities of an assistive robot. The APR uses a tablet in order to implement the basic peer-to-peer videoconference and tele-operation control combined with a tactile graphic user interface. The paper also presents the development of some applications proposed in the framework of an assisted living robot. PMID:27136552

  20. A Study on the Application of the Display Sharing Function In the APR1400 MCR

    International Nuclear Information System (INIS)

    APR1400 digital Main Control Room (MCR) has been applied to Korean Nuclear Power Plants since Shin-Kori 3 and 4. APR1400 MCR has the advantages to reduce the physical and mental workload and to increase situation awareness through integrated information of Compact Operator Console, Computerized Procedure System (CPS) and Large Display Panel (LDP). But although digital MCR has many advantages, it has a weak point that operators cannot easily oversee other operator's operational behavior like soft control actions. This environment makes it difficult to perform concurrent and independent verification from the viewpoint of human error prevention. This paper presents the application method and design of display sharing function through combination using Large Display Panel (LDP) and Information Flat Panel Display (IFPD) of operator console for more reliable operation than before. Because display sharing function is applied within the Information Processing System (IPS), it is required to maintain the system requirement of the IPS such as the CPU and network load. For quality assurance, display sharing function will be developed in accordance with Human Factors Engineering program (NUREG-0711) and Software Program Manual (SPM). We expect that this technology strengthen the reliable operation of the APR1400

  1. Single-tube condensation experiment in Passive Auxiliary Feedwater System of APR1400+

    International Nuclear Information System (INIS)

    Conventional Korean nuclear power plants, Advanced Power Reactors (APR), are characterized by an active cooling system. However, Active cooling system may not prevent significant damage without any AC power source available for its operation as vividly illustrated through the recent Fukushima incident. In the APR1400+ to be designed, an independent passive cooling system was added in order to overcome the aforementioned shortcomings. In the Passive Auxiliary Feedwater System (PAFS), gravity force and density difference between steam and water are used. The system comprises of 240 condensation tubes to efficiently remove decay heat. Before applying the PAFS to APR1400+, the system's safety and heat removal performance must be verified. The present study experimentally evaluates the heat removal performance of a single tube in the PAFS. The objectives of SCOP (Single-tube Condensation experiment facility of PAFS) are the evaluation of the heat removal performance in the tube of the PAFS and database construction under various tube designs and test conditions. Reaching these objectives, we developed advanced measurement techniques for the amount of moisture, heat flux, and water film thickness.

  2. Consideration of MAAP 5.0.2 ESF Model Characteristics for APR1400 NPP

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Mi Ro; Kim, Hyeong Taek [KHNP-CRI, Daejeon (Korea, Republic of)

    2014-10-15

    After the Fukushima accident, EPRI has developed the MAAP (Modular Accident Analysis Program) version 5 that is expected to make up the limitation of MAAP4, that is to say, the appropriateness of the model for the severe accident phenomena and the applicability to the phenomena in the spent fuel pool and the halfloop operation. Up to now, the newest version of MAAP is 5.0.2 (Build 5020000) that was released officially in December, 2013. In addition to this, it is expected that MAAP 5.0.3 version will be published sooner or later. As a kind of post-Fukushima measures, KHNP is developing the probabilistic safety assessment (PSA) and severe accident management guideline (SAMG) for low power and shutdown (LPSD) mode and MAAP 5.0.2 should be used in these projects as a major analysis program. So, first of all, it is necessary that the parameter file for domestic NPP should be upgraded as current Ver. MAAP4 to Ver. MAAP 5.0.2. KHNP has developed the draft version of parameter file for APR1400 type NPP and is being upgraded continuously. The Engineering Safety Features (ESF) model is one of the unique features of MAAP. In this study, we try to share the general information of the MAAP ESF model and the specific characteristics of APR1400 ESF model based on the newly developed MAAP 5.0.2 parameter file. Currently, while developing the LPSD PSA and LPSD SAMG as a kind of post-Fukushima measures, KHNP have the plan in order to upgrade the old parameter file based on MAAP4 to that based on MAAP5.0.2 for all domestic nuclear power plants. And, as the first effort, we are developing the MAAP 5.0.2 parameter file for APR1400 type NPP. In this study, we tried to develop the more accurate and reasonable ESF model of APR1400. In this process, we can find the distinctions and characteristics of specific ESF model and generalized ESF model of MAAP5.0.2. Also, we can eliminate the confusing concepts existed in the two models. So, it is judged that the newly developed MAAP5

  3. Evaluation of the Main Steam Line Break Accident for the APR+ Standard Design using MARS-KS

    Energy Technology Data Exchange (ETDEWEB)

    Park, M. H.; Kim, Y. S.; Hwang, Min Jeong; Sim, S. K. [Environment Energy Technology, Daejeon (Korea, Republic of); Bang, Young Seok [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    As a part of licensing evaluation of the APR+ (Advanced Power Reactor +) standard design, Korea Institute of Nuclear Safety(KINS) performed safety evaluation of the APR+ Standard Safety Analysis Report(SSAR). The results of the safety evaluation of the APR+ Main Steam Line Break(MSLB) accident is presented for the most limiting post-trip return-to-power case with the single failure assumption of the Loss Of Offsite Power(LOOP). MARS-KS regulatory safety analysis code has been used to evaluate safety as well as the system behavior during MSLB accident. The MARS-KS analysis results are compared with the results of the MSLB safety analysis presented in the SSAR of the APR+. Independent safety evaluation has been performed using MARS-KS regulatory safety analysis code for the APR+ MSLB accident inside containment for the limiting case of the full power post-trip return-to-power. The results of MARS-KS analysis were compared with the results of the MSLB safety analysis presented in the APR+ SSAR. Due to higher cooldown of the MARS-KS analysis, the MARS-KS analysis results in a higher positive reactivity insertion into the core by the negative moderator and fuel temperature reactivity coefficients than the APR+ SSAR analysis. Both results show no return-to-power during the limiting case of the MSLB inside containment. However, APR+ SSAR moderator temperature reactivity insertion should be evaluated against the MARS-KS moderator density reactivity insertion for is conservatism. This study also clearly shows asymmetric thermal hydraulic behavior during the MSLB accident at intact and affected sides of the downcomer and the core. These asymmetric phenomena should be further investigated for the effects on the system design.

  4. Evaluation of the Main Steam Line Break Accident for the APR+ Standard Design using MARS-KS

    International Nuclear Information System (INIS)

    As a part of licensing evaluation of the APR+ (Advanced Power Reactor +) standard design, Korea Institute of Nuclear Safety(KINS) performed safety evaluation of the APR+ Standard Safety Analysis Report(SSAR). The results of the safety evaluation of the APR+ Main Steam Line Break(MSLB) accident is presented for the most limiting post-trip return-to-power case with the single failure assumption of the Loss Of Offsite Power(LOOP). MARS-KS regulatory safety analysis code has been used to evaluate safety as well as the system behavior during MSLB accident. The MARS-KS analysis results are compared with the results of the MSLB safety analysis presented in the SSAR of the APR+. Independent safety evaluation has been performed using MARS-KS regulatory safety analysis code for the APR+ MSLB accident inside containment for the limiting case of the full power post-trip return-to-power. The results of MARS-KS analysis were compared with the results of the MSLB safety analysis presented in the APR+ SSAR. Due to higher cooldown of the MARS-KS analysis, the MARS-KS analysis results in a higher positive reactivity insertion into the core by the negative moderator and fuel temperature reactivity coefficients than the APR+ SSAR analysis. Both results show no return-to-power during the limiting case of the MSLB inside containment. However, APR+ SSAR moderator temperature reactivity insertion should be evaluated against the MARS-KS moderator density reactivity insertion for is conservatism. This study also clearly shows asymmetric thermal hydraulic behavior during the MSLB accident at intact and affected sides of the downcomer and the core. These asymmetric phenomena should be further investigated for the effects on the system design

  5. Irradiated planets

    International Nuclear Information System (INIS)

    We present models for the spectra emitted by irradiated planets and discuss the numerical methods used in the modeling. In addition, we show results of simple 3D calculations that are designed as a first step toward detailed multi-dimensional models of irradiated planets

  6. Food irradiation

    International Nuclear Information System (INIS)

    The paper discusses the need for effective and efficient technologies in improving the food handling system. It defines the basic premises for the development of food handling. The application of food irradiation technology is briefly discussed. The paper points out key considerations for the adoption of food irradiation technology in the ASEAN region (author)

  7. Food irradiation

    International Nuclear Information System (INIS)

    The author reviews in outline the present status of industrial gamma irradiation plants for food and medical sterilization and in particular lists commercial irradiation plants currently operating in the U.K., considering briefly plant design, efficiency, costs and dose control. (UK)

  8. Diverse Design Features of EU-APR1400 for Residual Heat Removal Function with Open RCS

    International Nuclear Information System (INIS)

    Diversity is the fundamental principle in safety system design of new nuclear power plants, which uses different mitigation measures to provide diverse ways of responding to a significant event. Regarding the diversity principle, EU-APR1400 (European APR1400) safety system should be in accordance with European design requirements. This paper provides how the core residual heat can be removed with open RCS (Reactor Coolant System) closure head condition using diverse cooling systems assuming a loss of SCS (Shutdown Cooling System). The loss of SCS results from a common cause failure of SCS or a loss of UHS (Ultimate Heat Sink). One of the postulated common cause failures which lead to the loss of SCS can be a manufacturing deficiency of shutdown cooling pumps, component cooling water pumps or essential service water pumps. The limiting event of the loss of SCS is the loss of UHS since the loss of UHS causes losses of safety systems including SCS, CCWS and ESWS. NO operator action inside the MCR (Main Control Room) during the first 30 minutes and outside the MCR during the first 60 minutes can be credited to recover the failed SCS. The diverse means of the EU-APR1400 for the residual heat removal function with RCS open condition have been developed to comply with the diversity principle of the European design requirements of new nuclear power plants. The results of the preliminary assessment show that the diverse design features are expected to satisfy the design criteria. In the future, more detailed design and assessment for this means will be performed considering interface requirements with completing the design of relevant systems and components

  9. Diverse Design Features of EU-APR1400 for Residual Heat Removal Function with Open RCS

    Energy Technology Data Exchange (ETDEWEB)

    Kweon, Hyeong Do; Lee, Keun Sung; Kim, Yong Soo; Kim, Sung Hwan [Korea Hydro and Nuclear Power Co., Ltd., Daejeon (Korea, Republic of)

    2014-05-15

    Diversity is the fundamental principle in safety system design of new nuclear power plants, which uses different mitigation measures to provide diverse ways of responding to a significant event. Regarding the diversity principle, EU-APR1400 (European APR1400) safety system should be in accordance with European design requirements. This paper provides how the core residual heat can be removed with open RCS (Reactor Coolant System) closure head condition using diverse cooling systems assuming a loss of SCS (Shutdown Cooling System). The loss of SCS results from a common cause failure of SCS or a loss of UHS (Ultimate Heat Sink). One of the postulated common cause failures which lead to the loss of SCS can be a manufacturing deficiency of shutdown cooling pumps, component cooling water pumps or essential service water pumps. The limiting event of the loss of SCS is the loss of UHS since the loss of UHS causes losses of safety systems including SCS, CCWS and ESWS. NO operator action inside the MCR (Main Control Room) during the first 30 minutes and outside the MCR during the first 60 minutes can be credited to recover the failed SCS. The diverse means of the EU-APR1400 for the residual heat removal function with RCS open condition have been developed to comply with the diversity principle of the European design requirements of new nuclear power plants. The results of the preliminary assessment show that the diverse design features are expected to satisfy the design criteria. In the future, more detailed design and assessment for this means will be performed considering interface requirements with completing the design of relevant systems and components.

  10. APR1400 l and C architecture with the advanced design feature including high reliability and maintainability

    International Nuclear Information System (INIS)

    The standard design of Advanced Power Reactor 1400 (APR1400) has been developed from 1992 to 2001 and obtained design certification from Korea Institute of Nuclear Safety (KINS) in 2002. The APR1400 standard design is being applied to the construction project of Shin-Kori 3, 4 nuclear power plants, which are scheduled to go into commercial operation in 2013 and 2014 respectively. Full digital I and C systems are adopted in safety and non-safety system of Shin-Kori 3, 4 to enhance safety and cost effectiveness of nuclear power plant. The NSSS/BOP control systems, which have been traditionally independent, are integrated in one DCS platform and one network to reduce the number of cabinets and improve system performance and maintainability. Safety grade I and C systems are designed to meet the regulatory requirements for real-time performance, reliability, single-failure criterion, independence, failure mode effect analysis (FMEA), defense-in-depth and diversity, deterministic control and communication, environmental qualification etc. Defense against common mode failure (CMF) of digital plant protection system is one of the key requirements in designing digital I and C systems. Diverse Protection System (DPS) is designed to be diverse from Plant Protection System (PPS) as a defense against common mode failure of digital plant protection system. Diverse manual ESF actuation is also designed to enforce plant safety against severe situation due to simultaneous all digital system failures of plant protection system. Currently, Shin-Kori 3,4 project is being constructed according to the detailed design based on standard design of APR1400 I and C system. Application of full digital I and C system in Shin-Kori 3,4 is expected to increase safety, reliability and maintainability. (authors)

  11. Irradiation damage

    International Nuclear Information System (INIS)

    There is considerable interest in irradiation effects in intermetallic compounds from both the applied and fundamental aspects. Initially, this interest was associated mainly with nuclear reactor programs but it now extends to the fields of ion-beam modification of metals, behaviour of amorphous materials, ion-beam processing of electronic materials, and ion-beam simulations of various kinds. The field of irradiation damage in intermetallic compounds is rapidly expanding, and no attempt will be made in this chapter to cover all of the various aspects. Instead, attention will be focused on some specific areas and, hopefully, through these, some insight will be given into the physical processes involved, the present state of our knowledge, and the challenge of obtaining more comprehensive understanding in the future. The specific areas that will be covered are: point defects in intermetallic compounds; irradiation-enhanced ordering and irradiation-induced disordering of ordered alloys; irradiation-induced amorphization

  12. Food irradiation

    International Nuclear Information System (INIS)

    Food irradiation can have a number of beneficial effects, including prevention of sprouting; control of insects, parasites, pathogenic and spoilage bacteria, moulds and yeasts; and sterilization, which enables commodities to be stored for long periods. It is most unlikely that all these potential applications will prove commercially acceptable; the extend to which such acceptance is eventually achieved will be determined by practical and economic considerations. A review of the available scientific literature indicates that food irradiation is a thoroughly tested food technology. Safety studies have so far shown no deleterious effects. Irradiation will help to ensure a safer and more plentiful food supply by extending shelf-life and by inactivating pests and pathogens. As long as requirement for good manufacturing practice are implemented, food irradiation is safe and effective. Possible risks of food irradiation are not basically different from those resulting from misuse of other processing methods, such as canning, freezing and pasteurization. (author)

  13. Irradiation damage

    Energy Technology Data Exchange (ETDEWEB)

    Howe, L.M

    2000-07-01

    There is considerable interest in irradiation effects in intermetallic compounds from both the applied and fundamental aspects. Initially, this interest was associated mainly with nuclear reactor programs but it now extends to the fields of ion-beam modification of metals, behaviour of amorphous materials, ion-beam processing of electronic materials, and ion-beam simulations of various kinds. The field of irradiation damage in intermetallic compounds is rapidly expanding, and no attempt will be made in this chapter to cover all of the various aspects. Instead, attention will be focused on some specific areas and, hopefully, through these, some insight will be given into the physical processes involved, the present state of our knowledge, and the challenge of obtaining more comprehensive understanding in the future. The specific areas that will be covered are: point defects in intermetallic compounds; irradiation-enhanced ordering and irradiation-induced disordering of ordered alloys; irradiation-induced amorphization.

  14. MARS calculation of PAFS (passive auxiliary feedwater system) heat exchanger in APR+

    International Nuclear Information System (INIS)

    APR+ (Advanced Power Reactor Plus), the next generation nuclear power plant in Korea, adopts PAFS (Passive Auxiliary Feedwater System) as one of the advanced safety feature. To design the condensation heat exchanger in PAFS, the two-phase flow phenomena in horizontal U-tube and PCCT (Passive Condensate Cooling Tank) were investigated by MARS calculation. By benchmarking with NOKO experimental result, MARS code showed a reasonable capability to quantitatively predict the condensation in horizontal tube heat exchanger. And the design of PAFS heat exchanger was proved to sufficiently remove the decay heat by the condensation heat transfer without any active auxiliary feedwater system

  15. MARS calculation of PAFS (passive auxiliary feedwater system) heat exchanger in APR+

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Byoung Uhn; Yun, Byong Jo; Bae, Sung Won; Choi, Ki Yong; Song, Chul Hwa [KAERI, Daejeon (Korea, Republic of); Cheon, Jong [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2009-07-01

    APR+ (Advanced Power Reactor Plus), the next generation nuclear power plant in Korea, adopts PAFS (Passive Auxiliary Feedwater System) as one of the advanced safety feature. To design the condensation heat exchanger in PAFS, the two-phase flow phenomena in horizontal U-tube and PCCT (Passive Condensate Cooling Tank) were investigated by MARS calculation. By benchmarking with NOKO experimental result, MARS code showed a reasonable capability to quantitatively predict the condensation in horizontal tube heat exchanger. And the design of PAFS heat exchanger was proved to sufficiently remove the decay heat by the condensation heat transfer without any active auxiliary feedwater system.

  16. Probability of Neutralization Estimation for APR1400 Physical Protection System Design Effectiveness Evaluation

    International Nuclear Information System (INIS)

    It is focusing on development of a new designing process which can be compatible to international standards such as IAEA1 and NRC2 suggest. Evaluation for the design effectiveness was found as one of the areas to improve. If a design doesn't meet a certain level of effectiveness, it should be re-designed accordingly. The effectiveness can be calculated with combination of probability of Interruption and probability of neutralization. System Analysis of Vulnerability to Intrusion (SAVI) has been developed by Sandia National Laboratories for that purpose. With SNL's timely detection methodology, SAVI has been used by U.S. nuclear utilities to meet the NRC requirements for PPS design effectiveness evaluation. For the SAVI calculation, probability of neutralization is a vital input element that must be supplied. This paper describes the elements to consider for neutralization, probability estimation methodology, and the estimation for APR1400 PPS design effectiveness evaluation process. Markov chain and Monte Carlo simulation are often used for simple numerical calculation to estimate PN. The results from both methods are not always identical even for the same situation. PN values for APR1400 evaluation were calculated based on Markov chain method and modified to be applicable for guards/adversaries ratio based analysis

  17. Analysis of a 12-Finger Rod Drop using RETRAN/MASTER Code System for APR1400

    International Nuclear Information System (INIS)

    The Optimized Power Reactor 1000 (OPR1000) has 4-finger and 12-finger Control Element Assemblies (CEAs). When the 12-finger CEA is dropped, Core Protection Calculator System (CPCS) shuts down the reactor to prevent fuel damage that could occur from the sudden reactor power peaking. By contrast, the improved CPCS of Advanced Power Reactor 1400 (APR1400), which has systems similar to those of the OPR1000, decreases reactor power rapidly using its Reactor Power Cutback System (RPCS) to avoid unwanted reactor trips caused by the CPCS during a 12- finger CEA drop event. RETRAN is a best-estimate code for transient analysis of Non-LOCA. The RETRAN control logic, which includes the function of reducing reactor power during a 12-Finger CEA drop, has been developed for the APR1400. A MATRAN program has also been developed. MATRAN is the interface program for realtime processing to connect RETRAN with MASTER code which is a nuclear analysis and design code. MATRAN supplies adequate feedback reactivities from the MASTER code to RETRAN code. The purpose of this study is to analyze the behavior of a nuclear reactor core and its primary system using conventional RETRAN analysis procedure and MATRAN program analysis procedure during a 12- finger CEA drop. In addition, the axial power distribution and Axial Shape Index (ASI) are produced by the MATRAN program and they are confirmed as within operation limits

  18. Advanced Design Features of APR1400 and Realization in Shin Kori Construction Project

    International Nuclear Information System (INIS)

    APR1400 adopted several advanced design features. To ensure their proper operation as a part of ShinKori 3,4 project, both experimental and analytical work are continuing. In this paper, work on the advanced design features related to enhanced safety is examined. APR1400 safety injection system consists of four independent trains which include four safety injection pump and tanks. A passive flow regulating device called fluidic device is installed in the safety injection tanks. Separate effect tests including a full scale fluidic device tests have been conducted. Integral system tests are in progress. Combination of these work with the analytical work using RELAP5/Mod3 would ensure the proper operation of the new safety injection systems. To mitigate severe accidents, hydrogen mitigation system using PARs and igniters is adopted. Also, active injection system and the streamlined insulation design are adopted to enhance the in-vessel retention capability with the external cooling of RPV strategy. Analytic work with supporting experiments is performed. We are certain that these preparatory work would help the successful adaptation of ADF in ShinKori project. (authors)

  19. Probability of Neutralization Estimation for APR1400 Physical Protection System Design Effectiveness Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Myungsu; Lim, Heoksoon; Na, Janghwan; Chi, Moongoo [Korea Hydro and Nuclear Power Co. Ltd. Central Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    It is focusing on development of a new designing process which can be compatible to international standards such as IAEA1 and NRC2 suggest. Evaluation for the design effectiveness was found as one of the areas to improve. If a design doesn't meet a certain level of effectiveness, it should be re-designed accordingly. The effectiveness can be calculated with combination of probability of Interruption and probability of neutralization. System Analysis of Vulnerability to Intrusion (SAVI) has been developed by Sandia National Laboratories for that purpose. With SNL's timely detection methodology, SAVI has been used by U.S. nuclear utilities to meet the NRC requirements for PPS design effectiveness evaluation. For the SAVI calculation, probability of neutralization is a vital input element that must be supplied. This paper describes the elements to consider for neutralization, probability estimation methodology, and the estimation for APR1400 PPS design effectiveness evaluation process. Markov chain and Monte Carlo simulation are often used for simple numerical calculation to estimate P{sub N}. The results from both methods are not always identical even for the same situation. P{sub N} values for APR1400 evaluation were calculated based on Markov chain method and modified to be applicable for guards/adversaries ratio based analysis.

  20. Experimental study on the operational and the cooling performance of the APR+ passive auxiliary feedwater system

    International Nuclear Information System (INIS)

    The passive auxiliary feedwater system (PAFS) is one of the advanced safety features adopted in the APR+ which is intended to completely replace the conventional active auxiliary feedwater system. The PAFS cools down the steam generator secondary side and eventually removes the decay heat from the reactor core by introducing a natural driving force mechanism; i.e., condensing steam in nearly-horizontal U-tubes submerged inside the passive condensation cooling tank (PCCT). With an aim of validating the cooling and operational performance of the PAFS, the separate effect test, PASCAL (PAFS Condensing Heat Removal Assessment Loop), is being performed to experimentally investigate the condensation heat transfer and natural convection phenomena in the PAFS. A single nearly-horizontal U-tube whose dimension is same as the prototypic U-tube of the APR+ PAFS is simulated in the PASCAL test. By performing the PASCAL test, the major thermal-hydraulic parameters such as local/overall heat transfer coefficients, fluid temperature inside the tube, wall temperature of the tube, and pool temperature distribution in the PCCT were produced not only to evaluate the current condensation heat transfer model but also to present database for the safety analysis related with the PAFS. (authors)

  1. Detection of the apr gene in proteolytic psychrotrophic bacteria isolated from refrigerated raw milk.

    Science.gov (United States)

    Martins, Maurilio L; de Araújo, Elza F; Mantovani, Hilário C; Moraes, Célia A; Vanetti, Maria C D

    2005-07-15

    Bacteria of the genus Pseudomonas have been associated with the spoilage of raw milk and dairy products due to the production of thermostable proteolytic enzymes. The apr gene encodes for alkaline metalloprotease in Pseudomonas and other related bacteria. Its presence in psychrotrophic proteolytic bacteria isolated from raw milk collected from cooling tanks was verified. A polymerase chain reaction (PCR) technique was used with degenerate primers. Total DNA from 112 isolates was pooled in different groups and then used as template for the amplification reactions. Controls consisted of DNA extracted from 26 cultures. An expected DNA fragment of 194 bp was detected in groups that contained bacteria identified as Pseudomonas. The PCR product was observed only when DNA from control cultures of Pseudomonas aeruginosa, Pseudomonas fluorescens, Serratia marcescens and Aeromonas hydrophila were used. A detection limit assay indicated that the apr gene could be directly amplified from pasteurized milk inoculated with 10(8) CFU/ml of P. fluorescens. With this method it was possible to detect proteolytic bacteria at 10(5) CFU/ml in reconstituted skim milk powder if cells were recovered for DNA extraction before amplification. PMID:15992619

  2. Thermal-hydraulic tests and analyses for the APR1400's development and licensing

    International Nuclear Information System (INIS)

    The program on Thermal-Hydraulic Evaluation by Testing and Analysis (THETA) for the development and licensing of the new design features in the APR1400 (Advanced Power Reactor-1400) is briefly introduced with a presentation on the research motivation and typical results of the separate effect tests and analyses of the major design features. The first part deals with multi-dimensional phenomena related to the safety analysis of the APR1400. One research area is related to the multi-dimensional behavior of the Safety Injection (SI) water in a reactor pressure vessel downcomer that uses a direct vessel injection type of SI system. The other area is associated with the condensation of steam jets and the resultant thermal mixing in a water pool; these phenomena are relevant to the depressurization of a Reactor Coolant System (RCS). The second part describes our efforts to develop new components for safety enhancements, such as a fluidic device as a passive SI flow controller and a sparger to depressurize the RCS. This work contributes to an understanding of the new thermal-hydraulic phenomena that are relevant to advanced reactor system designs; it also improves the prediction capabilities of analysis tools for multi-dimensional flow behavior, especially in complicated geometries

  3. Après-Coup in French Psychoanalysis: The Long Afterlife of Nachträglichkeit: The First Hundred Years, 1893 to 1993.

    Science.gov (United States)

    House, Jonathan; Slotnick, Julie

    2015-10-01

    Après-coup finds its origins in Freud's earliest psychoanalytic writings, but it was only half a century ago that French psychoanalysts rediscovered, clarified, and developed the concept and so brought it recognition as an essential Freudian concept. Because the history of après-coup is embedded in the French reading of Freud, this article will give an account of that reading in relation to après-coup. PMID:26485487

  4. Food irradiation

    International Nuclear Information System (INIS)

    Food treatment by means of ionizing energy, or irradiation, is an innovative method for its preservation. In order to treat important volumes of food, it is necessary to have industrial irradiation installations. The effect of radiations on food is analyzed in the present special work and a calculus scheme for an Irradiation Plant is proposed, discussing different aspects related to its project and design: ionizing radiation sources, adequate civil work, security and auxiliary systems to the installations, dosimetric methods and financing evaluation methods of the project. Finally, the conceptual design and calculus of an irradiation industrial plant of tubercles is made, based on the actual needs of a specific agricultural zone of our country. (Author)

  5. Fruits irradiation

    International Nuclear Information System (INIS)

    The objectives of this project in food irradiation are two-fold, to study the effect of irradiation in prolongation of useful storage life of fruits and to evaluate irradiation as a means of preserving fruits. However radiation is not intended to replace existing preservation processes but may be used in conjunction with current methods such as refrigeration, drying, fermentation etc. In fact radiation should combine with proper storage and packaging techniques in order to ensure maximum benefits. Ripening retardation of fruits by irradiation kinds of fruits: papaya, mango, rambutan, longan and durian. Changes in organoleptic properties of fruit flavor and taste, texture changes by taste panel estimation of significance level of results by statistical mathematical methods, chemical changes determination of climacteric peak in fruits by estimation of carbon dioxide evolution, vitamin C determination by Tillmann's method, carotenoid separation by thin layer chromatography, reducing sugars and acidity determination, volatile components of durian by gas-chromatography

  6. Food irradiation

    International Nuclear Information System (INIS)

    The preservation of food using irradiation may replace or be used in combination with traditional or conventional food preservation techniques. Studies have shown that the irradiation technique which uses less energy than other preservation methods is a potential way for reducing post harvest losses. However, economic feasibility among other constraints is the core factor to determine the success of the technique at commercial scale. The need and importance for considering this new technique in Malaysia are discussed here. (author)

  7. Food irradiation

    International Nuclear Information System (INIS)

    A worldwide standard on food irradiation was adopted in 1983 by codex Alimentarius Commission of the Joint Food Standard Programme of the Food and Agriculture Organization (FAO) of the United Nations and The World Health Organization (WHO). As a result, 41 countries have approved the use of irradiation for treating one or more food items and the number is increasing. Generally, irradiation is used to: food loses, food spoilage, disinfestation, safety and hygiene. The number of countries which use irradiation for processing food for commercial purposes has been increasing steadily from 19 in 1987 to 33 today. In the frames of the national programme on the application of irradiation for food preservation and hygienization an experimental plant for electron beam processing has been established in Inst. of Nuclear Chemistry and Technology. The plant is equipped with a small research accelerator Pilot (19 MeV, 1 kW) and industrial unit Electronika (10 MeV, 10 kW). On the basis of the research there were performed at different scientific institutions in Poland, health authorities have issued permissions for irradiation for; spices, garlic, onions, mushrooms, potatoes, dry mushrooms and vegetables. (author)

  8. Evaluation of Effect of N2 Gas on the Cooling Capability of Passive Auxiliary Feedwater System (PAFS) in APR+

    International Nuclear Information System (INIS)

    In Korea, Advanced Power Reactor Plus (APR+) has being developed by adding passive safety features to Advanced Power Reactor 1400MWe (APR1400). Passive Auxiliary Feedwater System (PAFS) is one of passive system adopted in the APR+ to replace the conventional active auxiliary feedwater system. Because PAFS removes decay heat from the reactor core, it is required to verify the performance of PAFS in postulated accidents cases. In addition, an effect of noncondensable gas on the heat removal capability of PAFS should be evaluated since the non-condensable gas may deteriorate a condensation heat transfer through the condensation heat exchanger in PAFS. In this study, the effect of N2 gas was evaluated using MARS

  9. Determination of a PWR key neutron parameters uncertainties and conformity studies applications; Determination des incertitudes liees aux grandeurs neutroniques d'interet des reacteurs a eau pressurisee a plaques combustible et applications aux etudes de conformite

    Energy Technology Data Exchange (ETDEWEB)

    Bernard, D

    2002-07-01

    The aim of this thesis was to evaluate uncertainties of key neutron parameters of slab reactors. Uncertainties sources have many origins, technologic origin for parameters of fabrication and physical origin for nuclear data. First, each contribution of uncertainties is calculated and finally, a factor of uncertainties is associated to key slab parameter like reactivity, isotherm reactivity coefficient, control rod efficiency, power form factor before irradiation and lifetime. This factors of uncertainties were computed by Generalized Perturbations Theory in case of step 0 and by directs calculations in case of irradiation problems. One of neutronic conformity applications was about fabrication and nuclear data targets precision adjustments. Statistic (uncertainties) and deterministic (deviations) approaches were studied. Then neutronics key slab parameters uncertainties were reduced and so nuclear performances were optimised. (author)

  10. Thermal-hydraulic evaluation of passive containment cooling system of improved APR+ during LOCAs

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Byong Guk; NO, Hee Cheon, E-mail: hcno@kaist.ac.kr

    2014-10-15

    Highlights: • Larger air holdup tanks are confirmed to be needed for PCCS through MARS simulation. • Condensation model in MARS gives lower heat transfer than Dehbi's correlation. • Heat transfer resistance of steam–air mixture is dominant for PCCS tubes. • Heat sink structures remove dominant amount of decay heat initially. • Flow instability is eased at higher tube inlet form loss, return level, and angle. - Abstract: Various reactor concepts and technologies have been devised and evaluated to ensure the integrity of the core and the containment under a prolonged station blackout. After the successful validation of the passive auxiliary feedwater system (PAFS) of Advanced Power Reactor Plus (APR+), Korea is considering an improved APR+ with a passive containment cooling system (PCCS). In a previous paper, we suggested a PCCS design based on APR+ and performed a scoping analysis. We performed a MARS simulation for the thermal hydraulic evaluation of the system behavior, including natural circulation through the Passive Condensation Cooling Tank (PCCT) water pool and inside PCCS tubes as well as steam–air mixture condensation inside the containment. Through a simulation using the MARS system code, we investigated the effect of air holdup tanks (AHTs) on reduction of the air fraction in the containment, the effects of several steam–air mixture condensation models, the role of heat structures, and the flow instability inside the PCCS tubes. We found that the presence of AHT reduced the number of required PCCS tubes by more than half and the heat resistance of the steam–air mixture side is dominant in terms of governing the overall performance of PCCS. The embedded MARS condensation model and Uchida's correlation gave lower heat transfer coefficients than Dehbi's correlation, and heat structures removed more decay heat than PCCS tubes. Finally, intense flow instability inside the PCCS tubes was observed and was mitigated by placing

  11. Le Chaebol après la crise financière de 1997

    Directory of Open Access Journals (Sweden)

    Chung-Yeol Park

    2008-11-01

    Full Text Available L’objet de cet article est de présenter les mutations subies par les Chaebols à la suite de la crise financière de 1997. La première section est consacrée à un bref rappel de la formation et du développement des Chaebols, ainsi qu’à une caractérisation des attributs de leur forme organisationnelle. Il s’agit ainsi d’indiquer la « forme  canonique » que revêtait le Chaebol avant la crise, afin de fixer des repères pour mesurer et évaluer l’ampleur et la nature des mutations intervenues après la crise de 1997. La deuxième et la troisième section proposent une analyse de la réforme financière et de la réforme du secteur des entreprises conduites en Corée après 1997 et largement influencées par le FMI. La quatrième section présente une analyse concrète des changements au sein de deux Chaebols majeurs (Hyundai et Samsung depuis la crise financière. A partir de ces études de cas et de données empiriques complémentaires sont mis en évidence tout à la fois les changements et la permanence dans la structure et le comportement des Chaebols, suite aux modifications institutionnelles introduites après la crise financière de 1997.The Chaebol after the 1997. Financial Crisis Changes and Continuity. The paper presents the changes undergone by the Korean Chaebols after the financial crisis of 1997. The first section shortly recalls the history of the birth and development of the Chaebols and presents their specific organizational traits.  The second and third sections are dedicated to the presentation of the financial reforms and of the reforms of the enterprises implemented in Korea after 1997. The fourth section presents two cases studies of the changes introduced after 1997 on two major chaebols : Hyundai Group and Samsung Group. These case studies and other more general empirical data are used to evaluate both the changes and the continuity in Chaebol’s organizational forms and behaviours after the 1997

  12. Analysis of Heat Removal Capability of PAFS (Passive Auxiliary Feedwater System) in APR (Advanced Power Reactor Plus)

    International Nuclear Information System (INIS)

    As passive safety features for nuclear power plants receive increasing attention, South Korea has designed PAFS (Passive Auxiliary Feedwater System) for APR+ (Advanced Power Reactor Plus). Because the PAFS replaces a conventional active auxiliary feedwater system and plays a role in the ultimate heat sink for decay heat, it is necessary to evaluate the heat removal capability of PAFS under postulated accidents conditions. Therefore, the performance analysis is carried out for two accident cases: Loss of Condenser Vacuum (LOCV) and Feedwater Line Break (FLB) accidents. For the analysis, MARS-KS code is used and MARS-KS model is developed by adding PAFS model to the existing APR1400 model

  13. Analysis of Heat Removal Capability of PAFS (Passive Auxiliary Feedwater System) in APR (Advanced Power Reactor Plus)

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Y. J.; Kang, K. H.; Yun, B. J. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-03-15

    As passive safety features for nuclear power plants receive increasing attention, South Korea has designed PAFS (Passive Auxiliary Feedwater System) for APR+ (Advanced Power Reactor Plus). Because the PAFS replaces a conventional active auxiliary feedwater system and plays a role in the ultimate heat sink for decay heat, it is necessary to evaluate the heat removal capability of PAFS under postulated accidents conditions. Therefore, the performance analysis is carried out for two accident cases: Loss of Condenser Vacuum (LOCV) and Feedwater Line Break (FLB) accidents. For the analysis, MARS-KS code is used and MARS-KS model is developed by adding PAFS model to the existing APR1400 model.

  14. Contribution to the algorithmic and efficient programming of new parallel architectures including accelerators for neutron physics and shielding computations; Contribution a l'algorithmique et a la programmation efficace des nouvelles architectures paralleles comportant des accelerateurs de calcul dans le domaine de la neutronique et de la radioprotection

    Energy Technology Data Exchange (ETDEWEB)

    Dubois, J.

    2011-10-13

    In science, simulation is a key process for research or validation. Modern computer technology allows faster numerical experiments, which are cheaper than real models. In the field of neutron simulation, the calculation of eigenvalues is one of the key challenges. The complexity of these problems is such that a lot of computing power may be necessary. The work of this thesis is first the evaluation of new computing hardware such as graphics card or massively multi-core chips, and their application to eigenvalue problems for neutron simulation. Then, in order to address the massive parallelism of supercomputers national, we also study the use of asynchronous hybrid methods for solving eigenvalue problems with this very high level of parallelism. Then we experiment the work of this research on several national supercomputers such as the Titane hybrid machine of the Computing Center, Research and Technology (CCRT), the Curie machine of the Very Large Computing Centre (TGCC), currently being installed, and the Hopper machine at the Lawrence Berkeley National Laboratory (LBNL). We also do our experiments on local workstations to illustrate the interest of this research in an everyday use with local computing resources. (author) [French] Les travaux de cette these concernent dans un premier temps l'evaluation des nouveaux materiels de calculs tels que les cartes graphiques ou les puces massivement multicoeurs, et leur application aux problemes de valeurs propres pour la neutronique. Ensuite, dans le but d'utiliser le parallelisme massif des supercalculateurs, nous etudions egalement l'utilisation de methodes hybrides asynchrones pour resoudre des problemes a valeur propre avec ce tres haut niveau de parallelisme. Nous experimentons ensuite le resultat de ces recherches sur plusieurs supercalculateurs nationaux tels que la machine hybride Titane du Centre de Calcul, Recherche et Technologies (CCRT), la machine Curie du Tres Grand Centre de Calcul (TGCC) qui

  15. Commercial irradiator

    International Nuclear Information System (INIS)

    Commercial irradiation, the treatment of products with gamma radiation principally using a Cobalt-60 source, had its beginnings in Europe and Australia 25 years ago. To date the most successful application of the process is the sterilization of medical products and, for a variety of reasons, gamma sterilization is now becoming dominant in this important field. Many other applications have been evaluated over the years and the most exciting is undoubtedly food irradiation for which there is a vast potential. The commercial feasibility of setting up and irradiation facility is a complex subject and the selection of Cobalt-60 gamma plant depends on a number of technical and economic considerations. The parameters which determine the design and capacity of the optimum plant include throughput, product size and dose requirements; a balance has to be struck between plant flexibility and overall economy. The Ansell irradiators are designed primarily for the sterilization of medical products although some experimental food irradiation has been done, particularly in Australia. (author)

  16. New tools for NTD vaccines: A case study of quality control assays for product development of the human hookworm vaccine Na-APR-1M74.

    Science.gov (United States)

    Pearson, Mark S; Jariwala, Amar R; Abbenante, Giovanni; Plieskatt, Jordan; Wilson, David; Bottazzi, Maria Elena; Hotez, Peter J; Keegan, Brian; Bethony, Jeffrey M; Loukas, Alex

    2015-01-01

    Na-APR-1(M74) is an aspartic protease that is rendered enzymatically inactive by site-directed mutagenesis and is a candidate antigen component in the Human Hookworm Vaccine. The mutant protease exerts vaccine efficacy by inducing antibodies that neutralize the enzymatic activity of wild type enzyme (Na-APR-1wt) in the gut of the hookworm, thereby depriving the worm of its ability to digest its blood meal. Previously, canines immunized with Na-APR-1(M74) and challenged with Ancylostoma caninum were partially protected against hookworm challenge infection, especially from the loss in hemoglobin observed in control canines and canine immunoglobulin (Ig) G raised against Na-APR-1 was shown to inhibit the enzymatic activity of Na-APR-1 wt in vitro, thereby providing proof of concept of Na-APR-1(M74) as a vaccine antigen. The mutated version, Na-APR-1(M74), was then expressed at the cGMP level using a Nicotiana benthamiana expression system (Fraunhofer, CMB, Delaware, MD), formulated with Alhydrogel®, and used to immunize mice in a dose-ranging study to explore the enzyme-neutralizing capacity of the resulting anti- Na-APR-1(M74) IgG. As little as 0.99 μg of recombinant Na-APR-1(M74) could induce anti Na-APR-1(M74) IgG in mice that were capable of inhibiting Na-APR-1w t-mediated digestion of a peptide substrate by 89%. In the absence of enzymatic activity of Na-APR-1(M74) as a surrogate marker of protein functionality, we developed an assay based on the binding of a quenched fluorescence-labeled inhibitor of aspartic proteases, BODIPY-FL pepstatin A (BDP). Binding of BDP in the active site of Na-APR-1 wt was demonstrated by inhibition of enzymatic activity, and competitive binding with unlabelled pepstatin A. BDP also bound to Na-APR-1(M74) which was assessed by fluorescence polarization, but with an ∼ 50-fold reduction in the dissociation constant. Taken together, these assays comprise a "toolbox" that could be useful for the analyses of Na-APR-1(M74) as it

  17. A MARS and MIDAS Linked Accident Simulation for Large LOCA in APR1400

    International Nuclear Information System (INIS)

    A linked calculation utilizing the design-basis code MARS and the severe accident code MIDAS has been accomplished for a station blackout simulation in APR1400. The MARS code was developed by using the RELAP3/MOD3 and COBRA-TF codes, while the MIDAS code is currently under a development process using the MELCOR code. The objectives of this paper are to explain how to identify the MAR-MIDAS linked calculation outlines and the technical problems, including the MARS data transfer method, the MIDAS input generation works and so on. For the performance verification of the MARS-MIDAS linked calculation, the MARS, MIDAS and their linkage system are run independently for the same initiating event, so that their data can be compared with each other after the selection of proper variables

  18. A MARS and MIDAS Linked Accident Simulation for Large LOCA in APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Young; Kim, K. R.; Kim, D. H.; Chung, B. D. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2006-07-01

    A linked calculation utilizing the design-basis code MARS and the severe accident code MIDAS has been accomplished for a station blackout simulation in APR1400. The MARS code was developed by using the RELAP3/MOD3 and COBRA-TF codes, while the MIDAS code is currently under a development process using the MELCOR code. The objectives of this paper are to explain how to identify the MAR-MIDAS linked calculation outlines and the technical problems, including the MARS data transfer method, the MIDAS input generation works and so on. For the performance verification of the MARS-MIDAS linked calculation, the MARS, MIDAS and their linkage system are run independently for the same initiating event, so that their data can be compared with each other after the selection of proper variables.

  19. Schemes of a MARS and MIDAS linked simulation for SBO in APR1400

    International Nuclear Information System (INIS)

    A linked calculation utilizing the design-basis code MARS and the severe accident code MIDAS has been accomplished for a station blackout simulation in APR1400. The MARS code was developed by using the RELAP3/MOD3 and COBRA-TF codes, while the MIDAS code is currently under a development process using the MELCOR code. In this paper, the MAR-MIDAS linked calculation outlines and the technical problems are presented, including the MARS data transfer method, the MARS and MIDAS node mapping and variable definition principles, the MIDAS input generation works and so on. For the performance verification of the MARS-MIDAS linked calculation, the MARS, MIDAS and their linkage system are run independently for the same initiating event, so that their data can be compared with each other after the selection of proper variables. (author)

  20. Signoles Aude, Le Hamas au pouvoir et après ?, Toulouse, Editions Milan, 2006.

    Directory of Open Access Journals (Sweden)

    Jean-François Legrain

    2007-11-01

    Full Text Available Dans les étroites limites imposées par la collection (absence totale de notes et de bibliographie, 112 p. en format réduit, le petit livre d’Aude Signoles, Le Hamas au pouvoir et après ?, commence à combler un vide de l’édition française. Le seul livre jusque là disponible en français et entièrement consacré à Hamas remonte à 7 années maintenant ; doté de nombreuses erreurs factuelles et faisant comme si Hamas était apparu avec l’autonomie des années 1990, il ignorait tout de son passé d’Ass...

  1. Study on MELCOR Modeling for Emergency External Water Injection Scenario of SBO in APR1400

    International Nuclear Information System (INIS)

    In the present study, a MELCOR model for APR1400 was developed and applied to analyze a SBO scenario selected to confirm the effectiveness of the means. In this analysis, the primary and secondary emergency cooling water injection were considered. Leakage from the Reactor Coolant Pump (RCP) seal and opening of the Atmosphere Dump Valve (ADV) were modeled as well to simulate the external pump injection strategy. In this study, the analysis results showed that the external injection strategy with an ADV manual opening could successfully cool down the reactor for a station blackout accident through its effective implementation. It was found that the RCP seal leakage rate is a sensitive parameter for depressurization of the RCS. In this regard, further study is needed to develop a realistic RCP seal leakage model, referring to detailed technical data

  2. Reliability analysis of protection system of advanced pressurized water reactor - APR 1400

    International Nuclear Information System (INIS)

    Reliability analysis was carried out for the protection system of the Korean Advanced Pressurized Water Reactor - APR 1400. The main focus of this study was the reliability analysis of digital protection system, however, towards giving an integrated statement of complete protection reliability an attempt has been made to include the shutdown devices and other related aspects based on the information available to date. The sensitivity analysis has been carried out for the critical components / functions in the system. Other aspects like importance analysis and human error reliability for the critical human actions form part of this work. The framework provided by this study and the results obtained shows that this analysis has potential to be utilized as part of risk informed approach for future design / regulatory applications

  3. Assessment of fluid flow characteristics for fluidic device in APR 1400

    International Nuclear Information System (INIS)

    New evolutionary light water reactors (LWRs) are being developed all over the world today. Some of those LWRs employ so-called passive safety components that use natural phenomena as the driving force such as expansion of pressurised gas, natural circulation, and so forth. These passive safety components and their systems are applied to improve the safety of nuclear power plants, further achieving not only to simplify the safety system, but also to improve its reliability and to provide a sufficient time margin to enable the operators to cope with accidents. The APR 1400 (Advanced Pressurised Water Reactor), which is a Korean Next Generation Reactor, adopted fluidic device as one of its passive pieces of safety equipment. The fluidic device is installed at the bottom of the inner space of the Safety Injection Tank (SIT) to control the flow rate of emergency cooling water during a large break loss of coolant accident (LBLOCA). During the past two years, a scale model test to obtain the required flow characteristics of the device under the APR 1400 specific conditions has been performed in Korea. The performance verification test was conducted to obtain the optimum characteristics and design data of full fluidic device (FD). In this study, the thermal-hydraulic characteristics for the fluidic device are analysed using SIMPLE algorithm with an aim to develop the assessment and verification guidelines for the APR 1400. To assess the flow characteristics for fluidic device, a three dimensional numerical model is developed and its results are compared with those of experiments. The fluid flow characteristics of the FD, which is passive flow control device in the SIT of APR-1400 are assessed using SIMPLE algorithm using FLUENT code and are compared with the experimental results. In this study, the fluid flow rate and pressure in the FD are predicted on the basis of the boundary condition at the entrance of supply port, control port, and discharge port respectively, so as

  4. Marrakech, un mois plus tard, 10 ans après

    Directory of Open Access Journals (Sweden)

    Bernard Debarbieux

    2011-06-01

    Full Text Available Il y a bientôt un mois, la place Jemma el Fna, dans la médina de Marrakech, et tout Marrakech avec elle, étaient secouées par un attentat terroriste. La ville en parle intensément, dans les rues, dans les cafés, dans les journaux. Il y a 10 ans, cette même place entrait dans le cercle des sites du patrimoine Mondial de l'Humanité. Jemma el Fna retentit cette semaine des festivités organisées pour célébrer cet anniversaire. La fête après le drame ? Comme pour oublier ? Certainement pas. Toujou...

  5. Development and Verification of MAAP5.0.3 Parameter file for APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Mi Ro; Kim, Hyeong Taek [KHNP-CRI, Daejeon (Korea, Republic of)

    2015-05-15

    After the Fukushima accident, EPRI has continuously upgrade the MAAP5 (Modular Accident Analysis Program version 5) that is expected to expand the limitation of MAAP4. As a result of those efforts, the MAAP5.0.2 (Build 5020000) was released officially in December, 2013. Also, in August, 2014, the newest version of MAAP5, MAAP 5.0.3 (Build 5030000), was officially released. The parameter file development is essential for severe accident analysis using MAAP code for specific plant. In 2014, KHNP developed the first draft version of MAAP 5.0.2 parameter file for APR1400 type NPP and had tested for some basic severe accident sequence. And, until now, KHNP has continuously complemented the first draft version of APR1400 type NPP parameter file for MAAP 5.0.2 and 5.0.3. In this study, we analysis the MCCI phenomena using MAAP 5.0.3 version with the 2''n''d draft version of APR1400 parameter file developed by KHNP. The purpose of this study is to compare the major difference in MAAP 5.0.2 and 5.0.3 MCCI model and to verify the appropriateness of the 2''n''d draft version of parameter file. The MCCI phenomena have been controversial issues in the severe accident progression, so there have been great efforts to solve them until now. As the part of these efforts, EPRI published MAAP 5.0.3 version which is known that the 'Lower head plenum model' and the 'MCCI model' was upgraded. KHNP have the plan in order to upgrade the old parameter file based on MAAP4 to that based on MAAP5.0.2 or higher version for all domestic nuclear power plants. So, we have continuously developed the MAAP 5.0.2 and 5.0.3 parameter file for APR1400 type NPP. In this study, we analyzed the MCCI phenomena using MAAP 5.0.3 and 2''n''d draft version parameter file. And we found some insight as belows; (1) The Melt Eruption Model can greatly affect the MCCI progression only in the case of limestone concrete in the wet cavity

  6. Vertical Seismic Responses of Seismically Isolated APR1400 Structures supported by Laminated Rubber Bearings

    International Nuclear Information System (INIS)

    The low horizontal shear stiffness of the isolator bearing is, typically, accompanied by large lateral displacements in the seismically isolated system. These large lateral displacements might lead to reductions in the vertical stiffness of the elastomeric or lead.rubber bearing (LRB). This paper summarizes the analytical study results performed with APR1400 model isolated with LRBs aimed at investigating the influence of vertical ground motion. Three types of earthquake motions are used as input motion. Floor response spectra are computed at the specific points of the structure to compare the vertical responses of seismically isolated structure to those of fixed base structure. The vertical responses of seismically isolated structure with LRBs might be increased than in the fixed base structure. This fact should be considered in the design stage. The vertical stiffness of the LRB should be reasonably estimated to design a seismically isolated nuclear structure

  7. Development and Verification of MAAP5.0.3 Parameter file for APR1400

    International Nuclear Information System (INIS)

    After the Fukushima accident, EPRI has continuously upgrade the MAAP5 (Modular Accident Analysis Program version 5) that is expected to expand the limitation of MAAP4. As a result of those efforts, the MAAP5.0.2 (Build 5020000) was released officially in December, 2013. Also, in August, 2014, the newest version of MAAP5, MAAP 5.0.3 (Build 5030000), was officially released. The parameter file development is essential for severe accident analysis using MAAP code for specific plant. In 2014, KHNP developed the first draft version of MAAP 5.0.2 parameter file for APR1400 type NPP and had tested for some basic severe accident sequence. And, until now, KHNP has continuously complemented the first draft version of APR1400 type NPP parameter file for MAAP 5.0.2 and 5.0.3. In this study, we analysis the MCCI phenomena using MAAP 5.0.3 version with the 2''n''d draft version of APR1400 parameter file developed by KHNP. The purpose of this study is to compare the major difference in MAAP 5.0.2 and 5.0.3 MCCI model and to verify the appropriateness of the 2''n''d draft version of parameter file. The MCCI phenomena have been controversial issues in the severe accident progression, so there have been great efforts to solve them until now. As the part of these efforts, EPRI published MAAP 5.0.3 version which is known that the 'Lower head plenum model' and the 'MCCI model' was upgraded. KHNP have the plan in order to upgrade the old parameter file based on MAAP4 to that based on MAAP5.0.2 or higher version for all domestic nuclear power plants. So, we have continuously developed the MAAP 5.0.2 and 5.0.3 parameter file for APR1400 type NPP. In this study, we analyzed the MCCI phenomena using MAAP 5.0.3 and 2''n''d draft version parameter file. And we found some insight as belows; (1) The Melt Eruption Model can greatly affect the MCCI progression only in the case of limestone concrete in the wet cavity

  8. Analysis Of Control Rod Ejection Of APR1400 By RELAP5

    International Nuclear Information System (INIS)

    This paper presents the analysis of Reactivity Induced Accident caused by ejection of a Control Element Assembly (CEA) from APR 1400 reactor vessel within 0.05 second. The initial condition were assumed as following: power level at 102%, delayed neutron fraction β = 412 pcm and CEA worth = 110 pcm. The analysis was simulated by RELAP5 code through two step: calculation of steady state and calculation of transient with initial condition mentioned as above. Some output results were presented with explanation: sequence of events corresponding to the time of the accident, the system behavior as power, reactivity feedback from fuel temperature changes (Doppler) as well as temperature, pressure, DNBR within 6 second of the accident. (author)

  9. Analysis Of Feedwater Line Break Of APR1400 By MARS Code

    International Nuclear Information System (INIS)

    This paper will deal with analysis of Feed water Line Break problem (FWLB) of the APR 1400 NPP with initial conditions: operation at 100% of power, double-ended break area of 0.058 m2 and the break location of the feedwater line between the check valve and the steam generator. The analysis was simulated by MARS code through two step: calculation for steady state and calculation for transient state with initial condition mentioned. Some output result were presented with explanation: sequence of events corresponding to the time of the accident, the system behavior as temperature, pressure, steam generator water levels as well as DNBR, etc. before and after the accident. (author)

  10. Preliminary Analysis of Ex-Vessel Steam Explosion using TEXAS-V code for APR1400

    International Nuclear Information System (INIS)

    The purpose of this study is to explore input development and the audit calculation using TEXAS-V code for ex-vessel steam explosion for a flooded reactor cavity of APR1400. TEXAS computational models are one of the simplified tools for simulations of fuel-coolant interaction during mixing, triggering and explosion phase. The models of TEXAS code were validated by performing the fundamental experimental investigation in the KROTOS facility at JRC, Ispra. The experiments such as KROTOS and FARO experiment are aimed at providing benchmark data to examine the effect of fuel-coolant initial conditions and mixing on explosion energetics with alumina and prototypical core material. TEXAS-V code used in this study was to analyze and predict the ex-vessel steam explosion for a reactor scale. The input deck to simulate the flooded reactor cavity of APR1400 is developed and base case calculation is performed. This study will provide a base for further study. The code will be of use for the evaluation and sensitivity study of ex-vessel steam explosion for ERVC strategy in the future studies. Analysis result of this study is similar to the result of other study. Through this study, it is found that TEXAS-V could be the used as a tool for predicting the steam explosion load on a reactor scale, as fast running computer code. In addition, TEXAS-V code could be to evaluate the impact of various uncertainties, which are not clearly understood yet, to provide a conservative envelope for the steam explosion

  11. Vinca irradiator

    International Nuclear Information System (INIS)

    The development programme of the VINCA radiosterilisation centre involves plans for an irradiator capable of working in several ways. Discontinuous operation. The irradiator is loaded for a certain period then runs automatically until the moment of unloading. This method is suitable as long as the treatment capacity is relatively small. Continuous operation with permanent batch loading and unloading carried out either manually or automatically (by means of equipment to be installed later). Otherwise the design of the apparatus is highly conventional. The source is a vertical panel submersible in a pool. The conveyor is of the 'bucket' type, with 4 tiers to each bucket. The batches pass successively through all possible irradiation positions. Transfert into and out of the cell take place through a maze, which also provides access to the cell when the sources are in storage at the bottom of the pool

  12. Separate and integral effect tests for validation of cooling and operational performance of the APR+ passive auxiliary feedwater system

    International Nuclear Information System (INIS)

    The passive auxiliary feedwater system (PAFS) is one of the advanced safety features adopted in the APR+, which is intended to completely replace the conventional active auxiliary feedwater system. With an aim of validating the cooling and operational performance of PAFS, an experimental program is in progress at KAERI, which is composed of two kinds of tests; the separate effect test and the integral effect test. The separate effect test, PASCAL (PAFS Condensing Heat Removal Assessment Loop), is being performed to experimentally investigate the condensation heat transfer and natural convection phenomena in PAFS. A single, nearly-horizontal U-tube, whose dimensions are the same as the prototypic U-tube of the APR+ PAFS, is simulated in the PASCAL test. The PASCAL experimental result showed that the present design of PAFS satisfied the heat removal requirement for cooling down the reactor core during the anticipated accident transients. The integral effect test is in progress to confirm the operational performance of PAFS, coupled with the reactor coolant systems using the ATLAS facility. As the first integral effect test, an FLB (feedwater line break) accident was simulated for the APR+. From the integral effect test result, it could be concluded that the APR+ has the capability of coping with the hypothetical FLB accident by adopting PAFS and proper set-points of its operation.

  13. Validating the AP[R] German Language Exam through a Curricular Survey of Third-Year College Language Courses

    Science.gov (United States)

    Bischof, Deborah Lokai

    2005-01-01

    Curriculum surveys are used periodically to validate the use of Advanced Place Program[R] (AP[R]) Exams as assessments of skills required for advanced college-level study. In the case of AP German Language, the target level is third-year college language study. This article presents results from a 2003 curriculum survey completed by third-year…

  14. Food irradiation

    International Nuclear Information System (INIS)

    The colloquium has been held on the occasion of the commissioning of a new linear electron accelerator. The 17 papers presented by the experts give a survey of the present status of food irradiation and related aspects. Every paper has been analysed and prepared for retrieval from the database. (orig.)

  15. Development of the Phenomena Identification Ranking Table (PIRT) for the Passive Auxiliary Feedwater System (PAFS) of the APR+

    International Nuclear Information System (INIS)

    The APR+ (Advanced Power Reactor plus) is a Gen- III+ pressurized water reactor (PWR) of which the standard design is currently being developed in Korea. This reactor adopts new design features which are believed to contribute not only to enhancement in nuclear safety but also to improvement in economic competitiveness. While the conventional nuclear power plants have utilized the active cooling systems, the APR+ adopts two types of passive safety features; an advanced fluidic device (FD+) and a passive auxiliary feedwater system (PAFS). The PAFS is one of the passive cooling systems of the APR+ which can replace an active system for auxiliary feedwater injection to a steam generator. A schematic diagram of the PAFS is shown in Fig. 1. It cools down the secondary system by heat transfer at horizontal heat exchangers in a PCCT (Passive Condensation Cooling Tank). High pressure steam flow from the steam generator is condensed in the horizontal heat exchanger, and the water in the PCCT pool is evaporated by a boiling heat transfer at the outside wall of the heat exchanger. With an aim of validating the cooling and operational performance of the PAFS, a separate effect test, PASCAL (PAFS Condensing heat removal Assessment Loop) is being performed at KAERI (Korea Atomic Energy Research Institute). In this study, Phenomena Identification and Ranking Table (PIRT) has been developed for identifying the major parameters affecting the thermal-hydraulic phenomena which originate from the adoption of the PAFS in the APR+. The PIRT process can be widely used to improve a safety analysis code for a new application and to establish experimental programs and to support the resolution of the licensing issues. The PIRT process used in this study follows the methodology previously applied in the APR1400 (Advanced Power Reactor 1400 MWe) PIRTs for large break loss of coolant accident (LBLOCA) and direct vessel injection (DVI) line break events

  16. Development of the Phenomena Identification Ranking Table (PIRT) for the Passive Auxiliary Feedwater System (PAFS) of the APR+

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chul Hwa; Chung, Bub Dong; Kang, Kyoung Ho; Kang, Han Ok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Yun, Byong Jo [Pusan National University, Busan (Korea, Republic of); Bang, Young Suk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Seong, Ho Je [KEPCO E and C, Yongin (Korea, Republic of); Hong, Soon Joon [FNC Technology Co. Ltd., Seoul (Korea, Republic of); Sim, Suk Ku [EN2t Inc., Daejeon (Korea, Republic of)

    2012-05-15

    The APR+ (Advanced Power Reactor plus) is a Gen- III+ pressurized water reactor (PWR) of which the standard design is currently being developed in Korea. This reactor adopts new design features which are believed to contribute not only to enhancement in nuclear safety but also to improvement in economic competitiveness. While the conventional nuclear power plants have utilized the active cooling systems, the APR+ adopts two types of passive safety features; an advanced fluidic device (FD+) and a passive auxiliary feedwater system (PAFS). The PAFS is one of the passive cooling systems of the APR+ which can replace an active system for auxiliary feedwater injection to a steam generator. A schematic diagram of the PAFS is shown in Fig. 1. It cools down the secondary system by heat transfer at horizontal heat exchangers in a PCCT (Passive Condensation Cooling Tank). High pressure steam flow from the steam generator is condensed in the horizontal heat exchanger, and the water in the PCCT pool is evaporated by a boiling heat transfer at the outside wall of the heat exchanger. With an aim of validating the cooling and operational performance of the PAFS, a separate effect test, PASCAL (PAFS Condensing heat removal Assessment Loop) is being performed at KAERI (Korea Atomic Energy Research Institute). In this study, Phenomena Identification and Ranking Table (PIRT) has been developed for identifying the major parameters affecting the thermal-hydraulic phenomena which originate from the adoption of the PAFS in the APR+. The PIRT process can be widely used to improve a safety analysis code for a new application and to establish experimental programs and to support the resolution of the licensing issues. The PIRT process used in this study follows the methodology previously applied in the APR1400 (Advanced Power Reactor 1400 MWe) PIRTs for large break loss of coolant accident (LBLOCA) and direct vessel injection (DVI) line break events

  17. Use of neutron activation analysis for the control of air pollution of Algiers; Utilisation de l'analyse par activation neutronique pour le controle de la pollution de l'air d'Alger

    Energy Technology Data Exchange (ETDEWEB)

    Belamri, M.; Benrachedi, K. [Universite M' hamed Bouguarra, Lab. de Technologie Alimentaire, Boumerdes (Algeria)

    2010-07-15

    The urban zone needs clean air to assure public health. To achieve this goal several filter samples were collected in different sites in Algiers city. Toxic elements such as: Na, Mg, Cl, Sc, Cr, Ti, V, Fe, Co, Cu, Zn, Se, Br, Ag, Sb, Ce, La, Hf, Ta and Hg have been measured in the filters using neutron activation analysis technique. Irradiation of filter samples and standards were carried out in Es-Salem reactor. The experimental procedure and the results are discussed. We noted during this work that the upper limit values for suspended dusts and the high concentrations for some toxic elements found are due to the weather conditions and intense road traffic around collecting sites. (authors)

  18. Food irradiation: An update

    International Nuclear Information System (INIS)

    Recent regulatory and commercial activity regarding food irradiation is highlighted. The effects of irradiation, used to kill insects and microorganisms which cause food spoilage, are discussed. Special attention is given to the current regulatory status of food irradiation in the USA; proposed FDA regulation regarding the use of irradiation; pending irradiation legislation in the US Congress; and industrial applications of irradiation

  19. Analysis of steam condensation in APR1400 IRWST for loss of coolant accident

    International Nuclear Information System (INIS)

    The In-Containment Refueling Water Storage Tank (IRWST) of APR1400 is installed at the bottom of containment building to promote the plant safety functions during an accident. This design feature brings about uncertainty factors which may necessitate conventional prediction of temperature and pressure of containment building improved or revised when an accident occurs. The hot steam which is released from RCS break enters the IRWST through four Pressure Relief Dampers (PRDs). It is expected to be condensed with water stored in IRWST, in which water is colder than incoming steam. The purpose of this study is to investigate the influence of IRWST and pressure relief damper on back pressure and temperature in APR1400 containment codes such as CONTEMPT-LT and GOTHIC. The comparison of codes showed that GOTHIC code be more appropriate for the prediction of containment pressure and temperature under the condition of steam condensation occurring in confined water pool. Especially, the GOTHIC has superior capability to treat multi-compartmentalized geometry This study developed one-compartment (single) model, two-compartment (separated) model, and three-dimension (3-D) model, respectively. Two compartment model separates the IRWST from the other containment compartments. In 3-D model, only the IRWST is nodalized with Cartesian modeling. The single model is developed for comparison with two-compartment model which can analyze PRD's influence. The separated model for predicting PRD's influence divides the space between containment and IRWST. 3-D model for IRWST was generated because it is not symmetric considering location of sparger, pump, and suction sump. Therefore, IRWST is simulated with not only detailed three-dimensional behavior but also independent flow paths for four PRDs. Many experimental studies for the direct-contact heat transfer in stratified steam water flows, cocurrent or countercurrent, have been performed (Segev et al., 1981; Lim et al., 1981; Kim and

  20. Apreçamento de opções de IDI usando o modelo CIR

    Directory of Open Access Journals (Sweden)

    José Santiago Fajardo Barbachan

    2003-06-01

    Full Text Available A opção de IDI da BM&F possui características peculiares que torna o seu apreçamento diferente das opções de taxa de juros mais comuns, como as de títulos de renda fixa. Este artigo desenvolve uma fórmula para apreçamento dessas opções de IDI, utilizando a precificação livre de arbitragem. O modelo utilizado considera apenas um fator estocástico: a taxa de juros livre de risco de curto prazo. A equação diferencial usada para modelar o comportamento da taxa de juros é a do modelo CIR (COX INGERSOLL & ROSS, 1985, que possui reversão à média e não permite a existência de taxas de juros nominais negativas. Também é feita uma estimação dos parâmetros do modelo proposto baseando-se em dados históricos, para então comparar o preço teórico da opção baseado nestes parâmetros com os preços de mercado e com o preço teórico considerando a modelagem de Vasicek (1977.The IDI option from the BM&F (Commodities and Futures Exchange has unusual characteristics, that make its pricing different from common interest rate options. This paper develops a closed form formula for the pricing of these IDI options, using an arbitrage-free pricing approach. The model used considers only one stochastic factor: the short-term risk-free interest rate. The differential equation used to model the behavior of the interest rate comes from the CIR (COX INGERSOLL & ROSS, 1985 model, which has mean reversion property and does not allow negative nominal interest rates. It is also done a parameter estimation of the proposed model based on historic data, and then compares the theoretical price of the option based on these parameters with the market price and with the theoretical price considering the Vasicek (1977 model.

  1. Numerical Analysis of Molten Corium Dispersion during Hypothetical High-Pressure Accidents in APR1400 Nuclear Power Plant

    International Nuclear Information System (INIS)

    During a hypothetical high-pressure accident in a nuclear power plant (NPP), molten corium can be ejected through a breach of a reactor pressure vessel (RPV) and dispersed by the following jet of a high pressure steam in the RPV. The dispersed corium is fragmented into smaller droplets in a reactor cavity of the NPP by the steam jet with very high velocity and is released into the upper compartment of the NPP by an overpressure in the cavity. The heat-carrying fragments of the corium transfer the thermal energy to the ambient air in the containment and react chemically with steam and generate hydrogen which may be burnt in the containment. The thermal loads from the ejected molten corium on the containment which is called direct containment heating (DCH) can threaten the integrity of the containment. New generation NPPs such as APR1400 and EPR have been designed in consideration of reducing the possibility of the containment failure from the DCH. In order for that, APR1400 has a convolute-type corium chamber connected to the reactor cavity. In the case of EPR, severe-accident dedicated depressurization valves are installed to preclude a high pressure melt ejection (HPME). DCH in a NPP containment is related to many physical phenomena such as multi-phase hydrodynamics, thermodynamics and chemical reaction. In the evaluation of the DCH load, the melt dispersion rates depending on the RPV pressure are the most important parameter. Mostly, DCH was evaluated by using lumped-analysis codes with some correlations obtained from experiments for the dispersion rates. The corium dispersion rates for many types of the NPP containments had been obtained by experiments in 90s. And some correlations from the experimental data were developed. As mentioned above, APR1400 has a corium chamber to reduce the corium dispersion rate. But there is no experimental data for the dispersion rate specific to the APR1400 cavity geometry. So its performance for capturing of the dispersed corium

  2. Food irradiation

    International Nuclear Information System (INIS)

    Various aspects of food treatment by cobalt 60 or caesium 137 gamma radiation are reviewed. One of the main applications of irradiation on foodstuffs lies in its ability to kill micro-organisms, lethal doses being all the lower as the organism concerned is more complex. The effect on parasites is also spectacular. Doses of 200 to 300 krad are recommended to destroy all parasites with no survival period and no resistance phenomenon has ever been observed. The action of gamma radiation on macromolecules was also investigated, the bactericide treatment giving rise to side effects by transformation of food components. Three examples were studied: starch, nucleic acids and a whole food, the egg. The organoleptic aspect of irradiation was examined for different treated foods, then the physical transformations of unpasteurized, heat-pasteurized and radio-pasteurized eggs were compared. The report ends with a brief analysis of the toxicity and conditions of application of the treatment

  3. Food irradiation

    International Nuclear Information System (INIS)

    Radiation processing of food is based on irradiation by gamma radiation from a 60Co source or X-ray with energy < 5 MeV or electron beam with energy < 10 MeV. This technique is now completely mastered. About 30 countries use this technique to extend the storage life of food but the total quantity processed is weak, only 30000 tons a year for France. Some countries like Morocco or Tunisia have launched technical programmes about the radiation processing of dates and vegetable oil. These programmes may lead to the creation of a quality label. A joint laboratory between CEA and the Aix-Marseille-3 university is working on the detection of food irradiation in order to fight the fraud. 3 techniques are being investigated: thermoluminescence, electronic paramagnetism resonance and a chemical method. (A.C.)

  4. Endolymphatic irradiation

    International Nuclear Information System (INIS)

    The authors analysed the clinical evolution and the result of renal transplantation some years after irradiation in 24 patients (group I) who received endolymphatic 131I as a pre-transplantation immunesuppresive measure. The control group (group II) consisted of 24 non-irradiated patients comparable to group I in age, sex, primary disease, type of donor and immunesuppressive therapy. Significant differences were observed between the two groups regarding such factors a incidence and reversibility of rejection crises in the first 60 post-transplantation days, loss of kidney due to rejection, and dosage of azathioprine. The authors conclude that this method, besides being harmless, has prolonged immunesuppressive action, its administration being advised for receptores of cadaver kidneys, mainly those who show positive cross-match against HLA antigens for painel. (Author)

  5. Numerical Analysis of Overpressure Transient during Cold Shutdown Operation for APR1400 Nuclear Power Plant

    International Nuclear Information System (INIS)

    ASME code describes specified requirements as allowable pressure for materials of RCPB for low temperature condition. RCPB should be protected during the condition as well because, if it fails, radioactive material can be released. ASME section III appendix G stipulates that maximum allowable pressure of reactor coolant system is 20% of hydrostatic test pressure which means the maximum allowable pressure below lowest service temperature. Generally we determine most severe mass-addition or energy-addition transients arisen by operator errors, malfunction of components or other causes for initiating events of LTOP (low temperature overpressure protection) analysis. According to safety analysis report for APR1400, most severe transient for mass addition begins from startup of one charging pump and four high pressure safety injection (HPSI) pumps at the same time and, on the other hand, most severe transient for energy addition begins from startup of one reactor coolant pump and, as a results of it, heat transfer from secondary side of SG filled with higher temperature water to primary side of SG. If RCS pressure increases and reaches a set pressure of LTOP relief valves, installed on suction pipe of shutdown cooling system (SCS), the valves perform the function of RCPB protection during cold shutdown status. PR1400 for overpressure transient under cold shutdown status. From the results of analysis of mass addition and energy addition, maximum RCS pressure is maintained lower than maximum allowable pressure for LTOP required in ASME code

  6. Numerical study on thermal stratification phenomenon in SCS branch pipe for APR1400

    International Nuclear Information System (INIS)

    The thermal stratification in the unisolable branch pipe for the Shutdown Cooling System (SCS) suction line for APR1400 has been studied. The vertical-horizontal branch pipe with an isolation valve at the end, and under Reactor System (RCS) operating condition is susceptible to the thermal stratification due to the stagnation flow around the isolation valve. The formation of the thermal stratification at the horizontal part of the branch line should be evaluated to determine the design consideration of thermal fatigue. Three dimensional transient analysis for the thermal stratification in a branch pipe is performed using the computational fluid dynamics code, FLUENT, to evaluate the velocity and temperature distribution. Parametric studies have been carried out to investigate the effect of the design and operating conditions. Parameters like the hot leg flow velocity, the outleakage through the isolation valve and the thermal insulation on piping wall are taken account. The analyses show that the temperature difference caused by the thermal stratification at the horizontal part of the unisolable branch pipe is not remarkable under normal operating conditions since the turbulent penetration length is developed deeply in the branch pipe due to the high velocity flow in the RCS hot leg. (author)

  7. A study on the mitigating capability of an auxiliary feedwater system during SBO for APR1400

    International Nuclear Information System (INIS)

    The objective of this paper is to establish an auxiliary feedwater (AFW) operational technical bases for the Korean Next Generation Reactor (APR1400) by modeling the plant, and by analyzing station blackout (SBO) using the MELCOR code. For the integrity of the reactor vessel and containment safety against severe accidents, it is essential to understand the severe accident sequences and to assess accident progression accurately using computer codes. Furthermore, it is important to attain the capability to analyze the advanced nuclear reactor design for the severe accident prevention and mitigation. Accident analyses are also undertaken to find out how effective AFW is mitigating in severe accident progresses. A nominal base case for SBO without AFW, time interval between feedwater stop and reactor vessel failure is 12,740 seconds. When AFW operates to mitigate the SBO accident progression 2, 4 and 8 hours after SBO starts, the reactor vessel failure is delayed for 20,415 seconds, 22,633 seconds and 26,508 seconds, respectively thus the operator has more time available for AC recovery and accident mitigation to prevent reactor vessel failure. (author)

  8. Numerical Analysis of Overpressure Transient during Cold Shutdown Operation for APR1400 Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Byung Soo; Kim, Yun Il; Jung, Ae Ju; Min, Bok Ki [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    ASME code describes specified requirements as allowable pressure for materials of RCPB for low temperature condition. RCPB should be protected during the condition as well because, if it fails, radioactive material can be released. ASME section III appendix G stipulates that maximum allowable pressure of reactor coolant system is 20% of hydrostatic test pressure which means the maximum allowable pressure below lowest service temperature. Generally we determine most severe mass-addition or energy-addition transients arisen by operator errors, malfunction of components or other causes for initiating events of LTOP (low temperature overpressure protection) analysis. According to safety analysis report for APR1400, most severe transient for mass addition begins from startup of one charging pump and four high pressure safety injection (HPSI) pumps at the same time and, on the other hand, most severe transient for energy addition begins from startup of one reactor coolant pump and, as a results of it, heat transfer from secondary side of SG filled with higher temperature water to primary side of SG. If RCS pressure increases and reaches a set pressure of LTOP relief valves, installed on suction pipe of shutdown cooling system (SCS), the valves perform the function of RCPB protection during cold shutdown status. PR1400 for overpressure transient under cold shutdown status. From the results of analysis of mass addition and energy addition, maximum RCS pressure is maintained lower than maximum allowable pressure for LTOP required in ASME code.

  9. General relativistic magnetohydrodynamic simulations of binary neutron star mergers with the APR4 equation of state

    Science.gov (United States)

    Endrizzi, A.; Ciolfi, R.; Giacomazzo, B.; Kastaun, W.; Kawamura, T.

    2016-08-01

    We present new results of fully general relativistic magnetohydrodynamic simulations of binary neutron star (BNS) mergers performed with the Whisky code. All the models use a piecewise polytropic approximation of the APR4 equation of state for cold matter, together with a ‘hybrid’ part to incorporate thermal effects during the evolution. We consider both equal and unequal-mass models, with total masses such that either a supramassive NS or a black hole is formed after merger. Each model is evolved with and without a magnetic field initially confined to the stellar interior. We present the different gravitational wave (GW) signals as well as a detailed description of the matter dynamics (magnetic field evolution, ejected mass, post-merger remnant/disk properties). Our simulations provide new insights into BNS mergers, the associated GW emission and the possible connection with the engine of short gamma-ray bursts (both in the ‘standard’ and in the ‘time-reversal’ scenarios) and other electromagnetic counterparts.

  10. General Relativistic Magnetohydrodynamic Simulations of Binary Neutron Star Mergers with the APR4 Equation of State

    CERN Document Server

    Endrizzi, Andrea; Giacomazzo, Bruno; Kastaun, Wolfgang; Kawamura, Takumu

    2016-01-01

    We present new results of fully general relativistic magnetohydrodynamic (GRMHD) simulations of binary neutron star (BNS) mergers performed with the Whisky code. All the models use a piecewise polytropic approximation of the APR4 equation of state (EOS) for cold matter, together with a "hybrid" part to incorporate thermal effects during the evolution. We consider both equal and unequal-mass models, with total masses such that either a supramassive NS or a black hole (BH) is formed after merger. Each model is evolved with and without a magnetic field initially confined to the stellar interior. We present the different gravitational wave (GW) signals as well as a detailed description of the matter dynamics (magnetic field evolution, ejected mass, post-merger remnant/disk properties). Our simulations provide new insights into BNS mergers, the associated GW emission and the possible connection with the engine of short gamma-ray bursts (both in the "standard" and in the "time-reversal" scenarios) and other electro...

  11. Thermal-hydraulic evaluation of passive containment cooling system of improved APR+ during LOCAs

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Byong Guk; No, Hee Cheon [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2014-05-15

    In performance of Passive Containment Cooling System (PCCS), sound operation of PCCS heat exchanger (HX) tubes is vital. To clarify their heat transfer function, various experiments are in progress, involving our group. Furthermore, in case of externally condensed HXs, careful evaluation of flow instability inside HX tubes are of prime importance. In PANDA integral tests targeting HXs of KERENA, a huge oscillation of flow inside tubes is observed. Flow instability is attributed to various reasons and classified into two types: static instability (ex. Ledinegg instability) and dynamic instability (ex. density wave oscillation). The former one is related to multiple stable flow rates at a given pressure drop under equilibrium condition while the latter one involves propagation time and feedback phenomena in transient condition. PCCS tubes correspond to the second type, dynamic instability. The detailed explanations are well documented. Our group suggested a PCCS design featuring an air holdup tank (AHT) for removing air near heat exchangers. Based on the design, the thermal hydraulic characteristics of PCCS are explored in this paper. Thermal hydraulic assessment of proposed PCCS is performed using a system code, MARS. Based on APR+, the required number of PCCS HX tubes are calculated with respect to AHT volume. We confirmed that larger AHT is preferred. Flow instability inside PCCS HX tubes are observed. Through sensitivity study, larger inlet orifice plate, return nozzle height, and tube angle are found to be most effective in stabilizing the flow.

  12. Numerical study of fluidic device in APR1400 using free surface model

    International Nuclear Information System (INIS)

    A fluidic device (FD) has been adopted in the safety injection tanks (SITs) of APR1400. A flow control mechanism of the FD was used to vary the flow regime in the vortex chamber corresponding to the SITs water level. The flow regime in the vortex chamber has a different pressure loss from low to high in accordance with the SITs water level. Nitrogen at the top of the SIT could be released owing to inertia of discharge flow when changing from a high flow rate to a low flow rate. This phenomenon is important to design improvement perspective because it can affect the performance of the FD. This paper shows a result of a preliminary numerical study to obtain the transient data related to air release in the flow turn down period using a two fluid free surface model provided from ANSYS CFX 13.0. In conclusion, there is no significant effect on the performance of the FD, though a small quantity of air is released during the flow turn down period

  13. Ārsta un farmaceita sadarbība pacientu aprūpē

    OpenAIRE

    Tione, Zane

    2016-01-01

    Sakārtota un pieejama veselības aprūpes sistēma valstī, var ievērojami uzlabot dzīves kvalitāti un nodrošināt valsts izaugsmi un konkurētspēju. Tomēr, kā zināms, svarīgs nosacījums šajā procesā ir arī pašu sistēmas dalībnieku iniciatīvai, viņu izrādītā vēlme uz sadarbību, vienotu mērķu sasniegšanai. Aktuāli ir noskaidrot kāda ir šī brīža situācija valstī, vai ārstiem un farmaceitiem ir vēlme šo komunikāciju uzlabot. Bakalaura darba mērķis ir noskaidrot vai pastāv ārstu un farmaceitu sadarbīb...

  14. Development of combined modularization technology for APR+ (Advanced Power Reactor) in Korea

    International Nuclear Information System (INIS)

    Full text: KHNP is currently operating 20 nuclear power plants and constructing 8 units in Korea. With the accumulated experience of operation and construction of NPPs over the past 50 years, KHNP tries to develop the original nuclear power reactor (APR+). The R and D project for 'combined modularization', which is a part of APR+ common core technology development, is being carried out and will be implemented by July 2010. This R and D project was initiated from the feasibility study on the modularization of structure and system facility for NPPs (2002). On the basis of the feasibility study result, The SC (Steel plate Concrete) structure technology development had been performed from 2005 to 2008, and the SC structure technology is under audit by the regulatory institution prior to the application for nuclear construction project. The research of combined modularization is an extension from the SC structure technology development. The research is divided into three phases. During first phase, by July 2010, the applicability of SC structure enlargement will be reviewed and conceptual design of combined/equipment modularization will be performed. In second phase, the basic design and construction feasibility evaluation of the screened combined/equipment modularization will be completed within July 2013. Afterward, in the final phase, optimized modularization technique will be realized through technical supplementation by Dec. 2015. Two main objectives will be achieved in the first phase study. The first one is to obtain design reliabilities for the SC structure by evaluating its applicability in auxiliary/compound building. The other one is to establish modularization requirements for design, procurement, manufacture and installation. To ensure these objectives, the flow sheet of technology development is greatly divided into 5 steps as follows. First step is to establish the screen criteria for adopting modularization. It's possible to catch the attitude of impact

  15. Sub compartment pressurization analysis for auxiliary building of APR1400DC

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Moon Oh; Lee, Hee Do [Atomic Creative Technology, Daejeon (Korea, Republic of)

    2012-10-15

    Generally, the sub compartment of PWR means a fully or partially enclosed volume that could house high-energy piping systems or restrict the flow of fluid in the event of a postulated pipe rupture. To meet the requirements of General Design Criteria (GDC) 4 and 50, Standard Review Plan (SRP) 6.2.1.2 states that the sub compartments shall be designed with sufficient margin to prevent the fracture of structure due to pressure differential across the walls of the sub- compartment and specifies the criteria related to the design and functional sub compartment nodalization schemes, vent flow path and vent flow behavior. Therefore the sub compartments structures within the containment and auxiliary building are designed to withstand the transient differential pressures loads, jet impingement forces, and pipe whip forces occurring due to a postulated pipe break. In this paper, the analyses of pressure transients after a postulated pipe rupture in sub compartments of APR1400DC auxiliary building is performed and the calculated peak differential pressures during the piping break transients for each sub compartment are less than structural design differential pressures.

  16. Evaluation on thermal-hydraulic characteristics for passive safety device of APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Seong Yeon; Lee, S. H.; Son, M. K. [Korea Association for Nuclear Technology, Taejon (Korea, Republic of); Jee, M. S.; Chung, M. H. [Chungnam National Univ., Taejon (Korea, Republic of)

    2001-07-15

    To establish evaluation and verification guideline for the APR1400, thermal-hydraulic characteristics for fuel rod bundle, reactor vessel and fluidic device is analyzed using FLUENT. Scope and major results of research are as follows : Thermal-hydraulic characteristics for nuclear fuel rod bundle: design data for nuclear fuel rod bundle and structure are surveyed, and 3 x 3 sub-channel model is adopted to investigate the fluid flow and heat transfer characteristics in fuel rod bundle. Computational results are compared with the heat transfer data measured by naphthalene sublimation method, and numerical analysis and evaluation are performed at various design conditions and flow conditions. Thermal-hydraulic characteristics for reactor vessel: reactor vessel design data are surveyed to develop numerical model. Porous media model is applied for fuel rod bundle, and full-scale, three dimensional simulation is performed at actual operating conditions. Distributions of velocity, pressure and temperature are discussed. Flow characteristics for fluidic device: three dimensional numerical model for fluidic device is developed, and numerical results are compared with experimental data obtained at KAERI in order to verify numerical simulation. In addition, variation of flow rate is investigated at various elapsed times after valve operating, and flow characteristics is analyzed at low and high flow rate conditions, respectively.

  17. Analysis of Condensation Phenomena in PAFS (Passive Auxiliary Feedwater System) Horizontal Heat Exchanger of APR+

    International Nuclear Information System (INIS)

    APR+ (Advanced Power Reactor Plus) is the next generation nuclear power plant in Korea. It adopts PAFS (Passive Auxiliary Feedwater System) on the secondary system. It can replace the conventional active system for auxiliary feedwater injection to the steam generator, and it enable to supply the coolant by a passive system. It cools down the secondary system by heat transfer at a horizontal U-tube in PCCT (Passive Condensate Cooling Tank). High pressure steam flow from the steam generator is condensed in the horizontal heat exchanger. The water in PCCT is maintained at an atmospheric pressure, so that boiling heat transfer at the outside wall of heat exchanger and natural convection occur in PCCT pool. The heat exchanger and PCCT is higher than steam generator, so condensate can be drained and injected to feedwater system without any active system. This study aims at design of the horizontal heat exchanger in PAFS. It should remove the heat generated in the steam generator. To satisfy this requirement, a system code analysis is conducted. The amount of condensation heat transfer is investigated by MARS (Multi-dimensional Analysis for Reactor Safety) code analysis

  18. Experimental program for validation of cooling and operational performance of the APR+ Passive auxiliary feedwater system

    International Nuclear Information System (INIS)

    PAFS (Passive Auxiliary Feedwater System) is one of the advanced passive safety systems adopted in the APR+ (Advanced Power Reactor plus), which is intended to completely replace the conventional active auxiliary feedwater system. PAFS cools down the steam generator's secondary side, and eventually removes the decay heat from the reactor core by introducing a natural driving force mechanism; i.e., condensing steam in nearly horizontal U-tubes submerged inside the passive condensation cooling tank (PCCT). With an aim of validating the cooling and operational performance of the PAFS, an experimental program is in progress at KAERI (Korea Atomic Energy Research Institute), which is composed of two kinds of tests; the separate effect test and the integral effect test. The separate effect test, PASCAL (PAFS Condensing Heat Removal Assessment Loop), is in progress to experimentally investigate the condensation heat transfer and natural convection phenomena in PAFS. The integral effect test is being performed to confirm the operational performance of the PAFS coupled with the other reactor coolant systems (RCS) using the thermal hydraulic integral effect test facility, ATLAS (Advanced Thermal hydraulic test Loop for Accident Simulation). This paper summarizes the up to date experimental results of the separate effect test and the integral effect test for PAFS from a cooling and operational performance point of view

  19. Preliminary Performance Analysis on APR+ PAFS Using RELAP5 and MARS Codes

    International Nuclear Information System (INIS)

    International nuclear industry has been adopting a passive safety system to enhance safety and reliability of nuclear power plant with advanced technology. Domestic industry has been also developing a specific advanced reactor, so-called advanced power reactor plus (APR+), with passive auxiliary feedwater system (PAFS). The PAFS was introduced to replace an active auxiliary feedwater system (AFWS) completely. The system function is to remove the residual heat in the primary system like the AFWS does when the main feedwater system is unavailable. PAFS consists of a passive condensate cooling tank (PCCT), a heat exchanger, valves, and pipes as shown in Fig. 1. When PAFS works, steam from steam generator is supplied and condensed into water in the heat exchange. And the water falls down by gravity and returns to the steam generator. This progress goes on repeatedly and it makes natural circulation possible in the system. The circulating flow removes continuously the primary residual heat without any active components. The performance of PAFS depends on various thermo-hydraulic (TH) phenomena occurred in the system. So understanding these phenomena is required to analyze its performance with TH code such as RELAP5 or MARS which is a regulatory audit code. Licensee in the domestic industry has been conducting the performance analysis of the PAFS with RELAP5. So the analysis of MARS model with the same input was carried out and difference between two codes was compared in this study

  20. A Framework to Measure Operator's Workload in Main Control Room of APR1400

    International Nuclear Information System (INIS)

    Though the work of operators has been changed a great deal, due to a lack of appropriate guidelines on the role allocation or communication method of operators, the problem of a lopsided workload for each operator has been raised. Thus, it is necessary to enhance the operation capability by developing the guidelines on the role definition and communication of operators in the advanced MCR of NPPs. To resolve this problem, however, a method of measuring the workload according to work execution of operators is necessary, but the applicable method is not available at this time. The objective of this research is to develop an analytical framework to evaluate the workload according to the work execution of power plant operators. A framework to measure the workload of crews in an advanced main control room has been suggested. In this research, we proposed a framework to measure and evaluate the workload of operators in an advanced MCR and the workload was measured through the simulator training experiment of the MCR of an APR1400. On the basis of these observations, it is necessary to reestablish the role and communication method of MCR operators suitable to the new operational environment and changed work and develops the appropriate operating guidelines

  1. Sensitivity Analysis of Ex-Vessel Steam Explosion usion TEXAS-V code for APR1400

    International Nuclear Information System (INIS)

    This study conducted the influence of melt velocity and melt diameter on the steam explosion calculation. There was strong influence of the jet diameter and velocity on the explosion. If there is the maximum pressure at the walls, the steam explosion loads can be too high to resist on the cavity wall. In the future study, TEXAS-V code will be used to evaluate the impact of various uncertainties to provide a conservative envelope for the steam explosion. In severe accidents, the corium can come into contact with coolant either when it flows to the bottom of the reactor vessel and encounters the reactor coolant, or when it breaches the reactor vessel and flows into the reactor containment. A steam explosion could then weaken the containment structures, such as the reactor vessel or the concrete walls of the containment building. The purpose of this study is to calculate using TEXAS-V code for ex-vessel steam explosion for a flooded reactor cavity of APR1400. TEXAS-V code to analyze and predict the ex-vessel steam explosion for a reactor scale is used

  2. Preliminary Performance Analysis on APR+ PAFS Using RELAP5 and MARS Codes

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kyung Jin; Hong, Soon Joon [FNC Tech., SNU, Seoul (Korea, Republic of); Park, Ju Yeop; Seul, Kwang Won [KINS, Daejeon (Korea, Republic of)

    2010-10-15

    International nuclear industry has been adopting a passive safety system to enhance safety and reliability of nuclear power plant with advanced technology. Domestic industry has been also developing a specific advanced reactor, so-called advanced power reactor plus (APR+), with passive auxiliary feedwater system (PAFS). The PAFS was introduced to replace an active auxiliary feedwater system (AFWS) completely. The system function is to remove the residual heat in the primary system like the AFWS does when the main feedwater system is unavailable. PAFS consists of a passive condensate cooling tank (PCCT), a heat exchanger, valves, and pipes as shown in Fig. 1. When PAFS works, steam from steam generator is supplied and condensed into water in the heat exchange. And the water falls down by gravity and returns to the steam generator. This progress goes on repeatedly and it makes natural circulation possible in the system. The circulating flow removes continuously the primary residual heat without any active components. The performance of PAFS depends on various thermo-hydraulic (TH) phenomena occurred in the system. So understanding these phenomena is required to analyze its performance with TH code such as RELAP5 or MARS which is a regulatory audit code. Licensee in the domestic industry has been conducting the performance analysis of the PAFS with RELAP5. So the analysis of MARS model with the same input was carried out and difference between two codes was compared in this study

  3. Analysis of Condensation Phenomena in PAFS (Passive Auxiliary Feedwater System) Horizontal Heat Exchanger of APR+

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Byoung Uhn; Yun, Byong Jo; Bae, Sung Won; Choi, Ki Yong; Song, Chul Hwa [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Cheon, Jong [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2009-10-15

    APR+ (Advanced Power Reactor Plus) is the next generation nuclear power plant in Korea. It adopts PAFS (Passive Auxiliary Feedwater System) on the secondary system. It can replace the conventional active system for auxiliary feedwater injection to the steam generator, and it enable to supply the coolant by a passive system. It cools down the secondary system by heat transfer at a horizontal U-tube in PCCT (Passive Condensate Cooling Tank). High pressure steam flow from the steam generator is condensed in the horizontal heat exchanger. The water in PCCT is maintained at an atmospheric pressure, so that boiling heat transfer at the outside wall of heat exchanger and natural convection occur in PCCT pool. The heat exchanger and PCCT is higher than steam generator, so condensate can be drained and injected to feedwater system without any active system. This study aims at design of the horizontal heat exchanger in PAFS. It should remove the heat generated in the steam generator. To satisfy this requirement, a system code analysis is conducted. The amount of condensation heat transfer is investigated by MARS (Multi-dimensional Analysis for Reactor Safety) code analysis.

  4. Organizacijos aprūpinimo darbuotojais veiklų gerinimas gamybinės įmonės pavyzdžiu

    OpenAIRE

    Varnaitė, Evelina

    2008-01-01

    Darbas sudarytas iš trijų dalių. Pirmoje dalyje analizuojama Lietuvos ir užsienio mokslininkų suformuluota organizacijos aprūpinimo darbuotojais veiklų samprata, turinys, metodai, subjektai bei veiksniai, įtakojantys šias veiklas. Antrojoje dalyje pateikiami ir analizuojami tyrimo metu surinkti duomenys apie gamybinėje įmonėje atliekamas aprūpinimo darbuotojais veiklas. Analizė leido padaryti išvadą, kad įmonėje atliekamos aprūpinimo darbuotojais veiklos turi trūkumų. Todėl trečioje dalyje yr...

  5. Organizacijos aprūpinimu personalu veiklų tobulinimas ŽŪB „Nematekas“ pavyzdžiu

    OpenAIRE

    Matelytė, Giedrė

    2013-01-01

    Baigiamojo darbo tikslas – atlikti ŽŪB „Nematekas“ aprūpinimo personalu veiklų analizę ir pateikti projektinius sprendimus darbuotojų planavimo, verbavimo, atrankos ir adaptavimo procesams. Baigiamajame darbe atlikta personalo veiklų sampratos teorinė analizė. Atliekama personalo valdymo informacinio aprūpinimo veiklų, organizacijos aprūpinimo darbuotojais ir darbuotojų efektyvaus panaudojimo ir išlaikymo veiklų analizė. Analitinė darbo dalyje naudojami keturi tyrimo metodai: mokslinės litera...

  6. Single port-assisted fully laparoscopic abdominoperineal resection (APR) with immediate V-RAM flap reconstruction of the perineal defect.

    LENUS (Irish Health Repository)

    Ali, Sayid

    2012-09-01

    Abdominoperineal resection (APR) of anorectal cancers after neoadjuvant chemoradiotherapy may incur significant perineal morbidity. While vertical rectus abdominis muscle (V-RAM) flaps can fill the pelvic resection space with health tissue, their use has previously been described predominantly in association with laparotomy. Here, we describe a means of combination laparoscopic APR with V-RAM flap reconstruction that allows structural preservation of the entire abdominal wall throughout the oncological resection and of the deep parietal layers after V-RAM donation. Furthermore, a single port access device used at the end colostomy site allows a second senior surgeon assist with an additional two working instruments for the purpose of improved pelvic tissue retraction, especially useful in obese patients.

  7. Food irradiation

    International Nuclear Information System (INIS)

    The first part of this data is relative to the study of chemical modifications induced by gamma radiations (60Co, 137Cs) on macromolecules of food and their contaminates with the help of two examples: starch and nucleic acids. Then the second part shows what are the consequences of irradiation on food and their preservation; we make distinction between useful effects (for instance germination inhibition of tubercules, destruction of insects or micro-organisms) and the results which are contingently bad for nutritional, technological and above all toxicologic aspects. The last part is relative to a short restatement of the problems inherent in the industrialization of this treatment

  8. Scoping Test on the Effects of Boron and Buffer in the Mockup PLUS7 Fuel Assembly of the APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Jeong Kwan; Kwon, Sun Guk; Kim, Jae Won; Lee, Jae Yong [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    Test results of the repeatability and the boron/buffer effects are presented, and compared with the acceptance basis for the LTCC of the APR1400. To address GSI-191 of the APR1400, we have performed a series of FA tests using a mockup PLUS7. The test results of repeatability performed at limiting conditions meet the acceptance basis compared with the reference results (SK34-61∼64) within 7% difference. Boron and buffer in the fluid lowered pressure drop across the entire FA compared with the condition without them. The test results of boron and buffer effects meet the acceptance head loss (91.8 kPa) of the APR1400 with a sufficient margin. To address U. S. Nuclear Regulatory Commission (NRC) Generic Safety Issue (GSI)-191, we have performed a series of fuel assembly (FA) head loss tests. The goal of this test is to confirm that there is sufficient available head when the debris reaches the core inlets of the APR1400 during a loss-of-coolant accident (LOCA), and that the long-term core cooling (LTCC) is not impeded. To move forward with the resolution of GSI-191 in-vessel effects, we have performed a scoping test on the effects of boron and buffer at ambient temperature. In test SK34-205, repeatability of the tests was confirmed at the limiting conditions. In a scoping test SK34-245, boron and Tri-Sodium Phosphate (TSP) buffer were added prior to the debris addition.

  9. Developing Optimal Procedure of Emergency Outside Cooling Water Injection for APR1400 Extended SBO Scenario Using MARS Code

    International Nuclear Information System (INIS)

    In this study, we examined optimum operator actions to mitigate extended SBO using MARS code. Particularly, this paper focuses on analyzing outside core cooling water injection scenario, and aimed to develop optimal extended SBO procedure. Supplying outside emergency cooling water is the key feature of flexible strategy in extended SBO situation. An optimum strategy to maintain core cooling is developed for typical extended SBO. MARS APR1400 best estimate model was used to find optimal procedure. Also RCP seal leakage effect was considered importantly. Recent Fukushima accident shows the importance of mitigation capability against extended SBO scenarios. In Korea, all nuclear power plants incorporated various measures against Fukushima-like events. For APR1400 NPP, outside connectors are installed to inject cooling water using fire trucks or portable pumps. Using these connectors, outside cooling water can be provided to reactor, steam generators (SG), containment spray system, and spent fuel pool. In U. S., similar approach is chosen to provide a diverse and flexible means to prevent fuel damage (core and SFP) in external event conditions resulting in extended loss of AC power and loss of ultimate heat sink. Hence, hardware necessary to cope with extended SBO is already available for APR1400. However, considering the complex and stressful condition encountered by operators during extended SBO, it is important to develop guidelines/procedures to best cope with the event

  10. Evaluation of the APR+ Passive Auxiliary Feedwater System Performance during Main Feedwater Line Break Accident using MARS-KS

    International Nuclear Information System (INIS)

    Ever since the Nuclear Power Plant (NPP) started commercial operation, advanced NPPs have been developed to enhance performance and safety as well as the economics of the plant. As a part of a regulatory safety research of the advanced nuclear reactors, MARS-KS regulatory safety analysis code has been selected to evaluate the performance of the Passive Auxiliary Feedwater System (PAFS) during Main Feedwater Line Break (MFLB) accident of the APR+ (Advanced Power Reactor+) which is under development by Korea Hydro and Nuclear Power (KHNP). The results of the APR+ MFLB analysis and the performance of the PAFS are presented herein. MATS-KS MFLB analysis shows that the MARS-KS code well simulates dynamic thermal hydraulic behavior of the MFLB and maximum RCS pressure satisfies the acceptance criteria of 120% design RCS pressure for the MFLB accident. APR+ PAFS effectively removes the core decay heat by the natural circulation during the MFLB accidents, however, comprehensive performance of the PAFS should be evaluated against the design basis of 8 hours core heat removal until the conditions for the initiation of the Shutdown Cooling System (350 .deg. F and 400 psia) are met

  11. Evaluation of the APR+ Passive Auxiliary Feedwater System Performance during Main Feedwater Line Break Accident using MARS-KS

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Minjeong; Ralph, Marigomena; Sim, S. K. [Environment and Energy Technology, Inc., Daejeon (Korea, Republic of); Bang, Youngseok [KINS, Daejeon (Korea, Republic of)

    2013-05-15

    Ever since the Nuclear Power Plant (NPP) started commercial operation, advanced NPPs have been developed to enhance performance and safety as well as the economics of the plant. As a part of a regulatory safety research of the advanced nuclear reactors, MARS-KS regulatory safety analysis code has been selected to evaluate the performance of the Passive Auxiliary Feedwater System (PAFS) during Main Feedwater Line Break (MFLB) accident of the APR+ (Advanced Power Reactor+) which is under development by Korea Hydro and Nuclear Power (KHNP). The results of the APR+ MFLB analysis and the performance of the PAFS are presented herein. MATS-KS MFLB analysis shows that the MARS-KS code well simulates dynamic thermal hydraulic behavior of the MFLB and maximum RCS pressure satisfies the acceptance criteria of 120% design RCS pressure for the MFLB accident. APR+ PAFS effectively removes the core decay heat by the natural circulation during the MFLB accidents, however, comprehensive performance of the PAFS should be evaluated against the design basis of 8 hours core heat removal until the conditions for the initiation of the Shutdown Cooling System (350 .deg. F and 400 psia) are met.

  12. Thyroid cancer following exposure to ionising radiation; Cancer de la thyroide apres exposition aux rayonnements ionisants

    Energy Technology Data Exchange (ETDEWEB)

    Schlumberger, M. [Institut de cancerologie Gustave-Roussy, 114, rue edouard-Vaillant, 94805 Villejuif cedex (France); Universite Paris Sud 11, 114, rue edouard-Vaillant, 94805 Villejuif cedex (France); Chevillard, S.; Ory, K. [Commissariat a l' energie atomique et aux energies alternatives, route du Panorama, 92265 Fontenay-aux-Roses cedex (France); Dupuy, C. [Institut de cancerologie Gustave-Roussy, 114, rue edouard-Vaillant, 94805 Villejuif cedex (France); Universite Paris Sud 11, 114, rue edouard-Vaillant, 94805 Villejuif cedex (France); UMR 8200 CNRS, 114, rue edouard-Vaillant, 94805 Villejuif cedex (France); Le Guen, B. [Division production nucleaire, direction production ingenierie, EDF, Tete-Pleyel, 1, place Pleyel, 93282 Saint-Denis cedex (France); De Vathaire, F. [Institut de cancerologie Gustave-Roussy, 114, rue edouard-Vaillant, 94805 Villejuif cedex (France); Universite Paris Sud 11, 114, rue edouard-Vaillant, 94805 Villejuif cedex (France); equipe d' epidemiologie des radiations, centre d' etudes en sante des populations, UMR 1018 Inserm, 114, rue edouard-Vaillant, 94805 Villejuif cedex (France)

    2011-08-15

    Exposure to ionising radiations during childhood increases the risk of thyroid cancer. Similar risk factors have been found after external radiation exposure or internal contamination with radioactive iodine isotopes. In case of contamination with radio-iodines, administration of potassium iodide can prevent thyroid irradiation. (authors)

  13. Drop size measurements and entrainment in APR1400 during LBLOCA reflood phase

    International Nuclear Information System (INIS)

    A study has been performed to investigate droplet size in the nuclear reactor of APR1400 during LBLOCA reflood phase and to develop droplet entrainment and deposition models for SPACE (Safety and Performance CodE) which is a safety analysis tool for PWR being developed in Korea. A freezing technique for measuring the size of droplets was developed to obtain the droplet size distribution in horizontal annular flow in a pipe with a 37.1 mm diameter. Droplets are frozen by using an extremely low temperature nitrogen gas with liquid film extraction. They are then photographed with a microscope and a CCD camera and measured by means of an image process. The results are compared with various experimental data. The droplet sizes measured by the freezing technique are comparable with those measured by other methods at a high superficial air velocity (of 50 m/s). However, because of the film extraction problem, the droplet sizes measured at a low superficial air velocity of less than 40 m/s are higher than those measured by other methods. A present method suggested for predicting the Sauter mean diameter is based on the maximum droplet size correlation for the experimental data, with and without liquid film extraction. The average droplet size is remarkably smaller downstream of the liquid film extractor because large droplets from the liquid film are excluded. In order to understand and to predict a heat transfer between superheated steam and droplets properly during reflood phase of LBLOCA, it is very important to measure broken droplet sizes by spacer grids. A study, therefore, has been performed to investigate droplet size in rod bundles with spacer grids and to develop a spacer grid droplet breakup model for safety analysis codes. Experiments were conducted with liquid droplets (SMD of 300∼700 μm) and various spacer grids at superficial air velocity of 10 m/s and 20 m/s based on FLECHT SEASET. The test channel and the grids were heated to 150 .deg. C to prevent

  14. Review on the NEI Methodology of Debris Transport Analysis in Sump Blockage Issue for APR1400

    International Nuclear Information System (INIS)

    Since USNRC (United State Nuclear Regulatory Committee) initially addressed post-accident sump performance under Unresolved Safety Issue USI A-43, sump blockage issue has gone through GSI-191, Regulation Guide 1.82, Rev. 3 (RG. 1.82 Rev.3), and generic Letter 2004-02 for PWRs (Pressurized Water Reactors). As a response of these USNRC's activities, NEI 04-07 was issued in order to evaluate the post-accident performance of a plant's recirculation sump. The baseline methodology of NEI 04-07 is composed of break selection, debris generation, latent debris, debris transport, and head loss. In analytical refinement of NEI 04-07, computational fluid dynamic (CFD) is suggested for the evaluation of debris transport in emergency core cooling (ECC) recirculation mode as guided by RG. 1.82 Rev.3. In Korea nuclear industry also keeps step with international activities of this safety issue, with Kori 1 plant as a pioneering edge. Korean nuclear industry has been also pursuing development of an advanced PWR of APR1400, which incorporates several improved safety features. One of the key features, considering sump blockage issue, is the adoption of IRWST (In-containment Refueling Water Storage Tank). This device, as the acronym implies, changes the emergency core cooling water injection pattern. This fact makes us to review the applicability of NEI 04-07's methodology. In this paper we discuss the applicability of NEI 04- 07's methodology, and more over, new methodology is proposed. And finally the preliminary debris transport is analyzed

  15. Steady state flow evaluations for passive auxiliary feedwater system of APR

    International Nuclear Information System (INIS)

    This paper briefly introduces a methodology to evaluate steady state flow of APR+ Passive Auxiliary Feedwater System (PAFS). The PAFS is being developed as a safety grade passive system to completely replace the existing active Auxiliary Feedwater System (AFWS). Natural circulation cooling can be generally classified into the single-phase, two-phase, and boiling-condensation modes. The PAF is designed to be operated in a boiling-condensation natural circulation mode. The steady-state flow rate should be equal to the steady-state boiling/condensation rate determined by the steady-state energy and momentum balances in the PAFS. The determined steady-state flow rate can be used in the design optimization for the natural circulation loop of the PAFS through the steady-state momentum balance. Since the retarding force, which is to be balanced by the driving force in the natural circulation system design depends on the reliable evaluation of the success of a natural circulation system design depends on the reliable evaluation of the pressure loss coefficients. In PAFS, the core decay heat is released by natural circulation flow between the S G secondary side and the Passive Condensation Heat Exchanger (PCHX) that is immersed in the Passive Condensation Cooling Tank (PCCT). The PCCT is located on the top of Auxiliary building The driving force is determined by the difference between the S/G (heat Source) secondary water level and condensation liquid (heat sink) level. It will overcome retarding force at flowrate in the system, which is determined by vaporization and condensation of the steam which is generated at the S/G by the latent heat in system. In this study, the theoretical method to estimate the steady state flow rate in boiling-condensation natural circulation system is developed and compared with test results

  16. Integral experiment and RELAP5 analysis for DVI line break SBLOCA in APR1400

    International Nuclear Information System (INIS)

    The thermal-hydraulic phenomena of Direct Vessel Injection (DVI) line Small-Break Loss-of-Coolant Accident (SBLOCA) in the pressurized water reactor, APR1400, were investigated. To understand the thermal-hydraulic phenomena during the SBLOCA transient, the reduced-height and reduced-pressure integral test loop, SNUF (Seoul National University Facility), was constructed according to the energy scaling methodology. The methodology conserves the mass inventory and energy of the system in the same time scale as the prototype. From the RELAP5 analysis, the energy scaling methodology was confirmed to show the reasonable transient when ideally scaled-down SNUF model was compared to the prototype model. In order to overcome the limitation of power in actual SNUF, the modified-power curve was utilized without simulating the forced flow by pump, so that those corrections did not affect the major phenomena during transient. Geometric distortion of actual SNUF also did not strongly disturb the thermal-hydraulic behaviors, especially occurrence of the downcomer seal clearing. In the experiments according to the conditions determined by energy scaling methodology, the phenomenon of downcomer seal clearing had a dominant role in decrease of the system pressure and increase of the coolant level of core. It occurred when the steam injected from cold legs penetrated the coolant in upper downcomer toward the broken DVI line. The experimental results was used to validate the calculation capability of RELAP5, especially for the downcomer seal clearing phenomenon, and to estimate the scale-up capability of RELAP5 code according to the scaling methodology. (authors)

  17. Analysis of severe accident progression for in-vessel corium retention estimation in the APR 1400

    International Nuclear Information System (INIS)

    The scope and content of this technical report is to evaluate high-pressure transients of total Loss of Feed Water (LOFW) to the steam generators and Station Blackout (SBO), and low-pressure transients of Loss of Coolant Accident (LOCA) without Safety Injection (SI) using the SCDAP/RELAP5/MOD3.3 computer code from transient initiation to reactor vessel failure in the APR 1400. The SCDAP/RELAP5/MOD3.3 results have shown that the pressurizer surge line had failed before reactor vessel failure, which results in a rapid decrease of RCS pressure in the high-pressure sequences of the LOFW and the SBO transients. The LOFW with intentional RCS depressurization using the safety depressurization system prevents failure of the pressurizer surge line and results in actuation of the safety injection tanks. A large mass of the melted and relocated core material in the bottom of core region at approximately 6 hours was relocated to the lower plenum of the reactor vessel in the 2-inch and the 3-inch SBLOCAs, which results in the reactor vessel failure by creep. In the SBLOCA sequence without the safety injection, the actuation of the SITs can be possible for the operator to have time of 4-5 hours in the action of the severe accident mitigation strategy to prevent reactor vessel failure. In all sequences, approximately 50-90 % of the core material was melted and relocated to the lower plenum of the reactor vessel at the time of reactor vessel failure and approximately 30-60 % of the fuel rod cladding was oxidized

  18. Experiment and RELAP5 analysis for the downcomer boiling of APR1400 under LBLOCA

    International Nuclear Information System (INIS)

    Experiment has been carried out to investigate the boiling phenomena in the downcomer and RELAP5/MOD3.2 has been assessed with the present experimental data. The heated wall with a thickness of 8.2 cm and a height of 27 cm is used, which is made of the same material as the prototype (APR1400) with chrome coating against rusting. From the experiment, we visually observed strong liquid recirculation and vapor jetting near the heated wall due to the axial migration of voids only in the thin layer of the heated wall but little bubble migration to the bulk region. The size of the thin layer is about 4 cm, which is used for the determination of the radial nodal size in the radial double-node schemes. The RELAP5 calculations using three different nodal schemes are compared with experimental data in aspects of water level, void fraction, wall temperatures and phase velocities. The radial single-node scheme produces no liquid recirculation, resulting in the sudden level drop due to a sudden increase in void fraction. The double-nodal scheme with the top-bottom radial connections yields the strong circulation, eliminating the sudden level drop. As a result, the scheme produces better results than the radial single-nodal scheme and the double-nodal scheme with all radial connections. Based on the information from the measurement of local liquid velocity profile and visual observation, the drift velocity model is developed to apply into the downcomer with a large gap and a vertical heated wall. The proposed drift velocity model has been implemented into RELAP5 and verified with the experimental results. (author)

  19. Cold-Leg Small Break LOCA Analysis of APR1400 Plant Using a SPACE/sEM Code

    International Nuclear Information System (INIS)

    The Small Break Loss-of-Coolant Accident (SBLOCA) evaluation methodology (EM) for APR1400, called sEM, is now being developed using SPACE code. SPACE/sEM is to set up a conservative evaluation methodology in accordance with appendix K of 10 CFR 50. Major required and acceptable features of the evaluation models are described as below. - Fission product decay : 1.2 times of ANS97 decay curve - Critical flow model : Henry-Fauske Moody two phase critical flow model - Metal-Water reaction model : Baker-Just equation - Critical Heat Flux (CHF) : B and W, Barnett and Modified Barnett correlation - Post-CHF : Groeneveld 5.7 film boiling correlation A series of test matrix is established to validate SPACE/sEM code in terms of major SBLOCA phenomena, e.g. core level swelling and boiling, core heat transfer, critical flow, loop seal clearance and their integrated effects. The separated effect tests (SETs) and integrated effect tests (IETs) are successfully performed and these results shows that SPACE/sEM code has a conservatism comparing with experimental data. Finally, plant calculations of SBLOCA for APR1400 are conducted as described below. - Break location sensitivity : DVI line, hot-leg, cold-leg, pump suction leg. - Break size spectrum : 0.4ft2∼0.02ft2(DVI) 0.5ft2∼0.02ft2(hot-leg, cold-leg, pump suction leg) This paper deals with break size spectrum analysis of cold-leg break accidents. Based on the calculation results, emergency core cooling system (ECCS) performances of APR1400 and typical SBLOCA phenomena can be evaluated. Cold-leg SBLOCA analysis for APR1400 is performed using SPACE/sEM code under harsh environment condition. SPACE/sEM code shows the typical SBLOCA behaviors and it is reasonably predicted. Although SPACE/sEM code has conservative models and correlations based on appendix K of 10 CFR 50, PCT does not exceed the requirement (1477 K). It is concluded that ECCS in APR1400 has a sufficient performance in cold-leg SBLOCA

  20. A study of the behaviour of irradiated or unirradiated grafts in the camera aquosa of irradiated and unirradiated animals; Etude du comportement d'un greffon irradie ou non, transplante dans la chambre anterieure de l'oeil d'un animal irradie ou non

    Energy Technology Data Exchange (ETDEWEB)

    Djalali-Behzad, G. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1969-06-01

    Following grafts of new born mice spinal ganglia in the 'camera aquosa' of adult mice, the authors tried hematopoietic tissue grafts in the same conditions. The growth of iso-logous and hetero-logous bone marrow in the 'camera aquosa' showed that this tissue, even after exposure to supralethal doses, was capable of survival and growth. A counter-experiment with non irradiated bone marrow grafts in the 'camera aquosa' of rats delivered 700 rads led to the conclusion that the environment, intoxicated by exposure, acted on the graft so that after vascularization it became unable to grow. (author) [French] Apres avoir greffe des ganglions rachidiens de souriceaux nouveaux-nes dans la chambre anterieure de l'oeil de souris adultes, l'auteur a tente de greffer du tissu hematopoietique de la meme facon. La proliferation de la moelle osseuse isologue et heterologue, dans la chambre anterieure de l'oeil, lui a permis de mettre en evidence une certaine capacite de survie et de proliferation de ce tissu irradie meme a dose supraletale. Par une contre-experimentation, c'est-a-dire par la greffe de moelle non irradiee dans la chambre anterieure de rats irradies a 700 rads, il conclut que le milieu ambiant, intoxique par l'irradiation, agit sur le greffon de telle sorte que ce dernier, apres s'etre vascularise, devient depourvu de son aptitude de proliferation. (auteur)

  1. Development of an amphibious robot for visual inspection of APR1400 Npp IRWST strainer

    International Nuclear Information System (INIS)

    An amphibious inspection robot system (hereafter AIROS) is being developed to visually inspect the in-containment refueling storage water tank (hereafter IRWST) strainer in APR1400 instead of a human diver. Four IRWST strainers are located in the IRWST, which is filled with boric acid water. Each strainer has 108 sub-assembly strainer fin modules that should be inspected with the VT-3 method according to Reg. guide 1.82 and the operation manual. AIROS has 6 thrusters for submarine voyage and 4 legs for walking on the top of the strainer. An inverse kinematic algorithm was implemented in the robot controller for exact walking on the top of the IRWST strainer. The IRWST strainer has several top cross braces that are extruded on the top of the strainer, which can be obstacles of walking on the strainer, to maintain the frame of the strainer. Therefore, a robot leg should arrive at the position beside the top cross brace. For this reason, we used an image processing technique to find the top cross brace in the sole camera image. The sole camera image is processed to find the existence of the top cross brace using the cross edge detection algorithm in real time. A 5-DOF robot arm that has multiple camera modules for simultaneous inspection of both sides can penetrate narrow gaps. For intuitive presentation of inspection results and for management of inspection data, inspection images are stored in the control PC with camera angles and positions to synthesize and merge the images. The synthesized images are then mapped in a 3D CAD model of the IRWST strainer with the location information. An IRWST strainer mock-up was fabricated to teach the robot arm scanning and gaiting. It is important to arrive at the designated position for inserting the robot arm into all of the gaps. Exact position control without anchor under the water is not easy. Therefore, we designed the multi leg robot for the role of anchoring and positioning. Quadruped robot design of installing sole

  2. Development of an amphibious robot for visual inspection of APR1400 Npp IRWST strainer

    Energy Technology Data Exchange (ETDEWEB)

    Jang, You Hyun; Kim, Jong Seog [Korea Hydro Nuclear Power Central Research Institute, Daejeon (Korea, Republic of)

    2014-06-15

    An amphibious inspection robot system (hereafter AIROS) is being developed to visually inspect the in-containment refueling storage water tank (hereafter IRWST) strainer in APR1400 instead of a human diver. Four IRWST strainers are located in the IRWST, which is filled with boric acid water. Each strainer has 108 sub-assembly strainer fin modules that should be inspected with the VT-3 method according to Reg. guide 1.82 and the operation manual. AIROS has 6 thrusters for submarine voyage and 4 legs for walking on the top of the strainer. An inverse kinematic algorithm was implemented in the robot controller for exact walking on the top of the IRWST strainer. The IRWST strainer has several top cross braces that are extruded on the top of the strainer, which can be obstacles of walking on the strainer, to maintain the frame of the strainer. Therefore, a robot leg should arrive at the position beside the top cross brace. For this reason, we used an image processing technique to find the top cross brace in the sole camera image. The sole camera image is processed to find the existence of the top cross brace using the cross edge detection algorithm in real time. A 5-DOF robot arm that has multiple camera modules for simultaneous inspection of both sides can penetrate narrow gaps. For intuitive presentation of inspection results and for management of inspection data, inspection images are stored in the control PC with camera angles and positions to synthesize and merge the images. The synthesized images are then mapped in a 3D CAD model of the IRWST strainer with the location information. An IRWST strainer mock-up was fabricated to teach the robot arm scanning and gaiting. It is important to arrive at the designated position for inserting the robot arm into all of the gaps. Exact position control without anchor under the water is not easy. Therefore, we designed the multi leg robot for the role of anchoring and positioning. Quadruped robot design of installing sole

  3. Analysis of MSGTR events for APR1400 by means of best estimate thermal-hydraulic system code

    International Nuclear Information System (INIS)

    A multiple steam generator tube rupture (MSGTR) event has never occurred in the history of commercial nuclear reactor operation while single steam generator tube rupture (SGTR) event is reported to occur every two years. As there is no history of MSGTR event, the understandings of transients and consequences of this event are not so much. In this study, a postulated MSGTR event in advanced power reactor 1400 (APR1400) is analyzed using thermal-hydraulic system code. The APR 1400 is a two-loop, 1000 MWe, PWR supposed to be built in 2009. MARS1.4 is used in this study. The present study aims to understand the effects of rupture location in heat transfer tubes and selection of affected steam generator following a MSGTR event. The effects of five tube rupture locations are compared with each other. The comparison shows that the response of APR1400 is to allow shortest time for operator action following a tubes rupture in the vicinity of hot-leg side tube sheet and to allow longest time following a tube ruptures at the tube top. The MSSV lift time for rupture at tube-top is evaluated as 24.5% larger than that for rupture at hot-leg side tube sheet. Also, the MSSV lift time for four cases are compared in order to examine how long operator response time is allowed depending on which steam generator is affected. The comparison shows that the cases for both of two steam generators are affected allow longer time for operator action compared with the cases that a single steam generator is affected. Further more, the tube ruptures in the steam generator where a pressurizer is linked leads to the shortest operator response time

  4. Regulation of enterobactin iron transport in Escherichia coli: characterization of ent::Mu d(Apr lac) operon fusions.

    OpenAIRE

    Fleming, T P; Nahlik, M S; McIntosh, M A

    1983-01-01

    The vector Mu d(Apr lac) was utilized to construct operon fusions in the Escherichia coli enterobactin (ent) biosynthetic and transport genes. Enzyme assays indicated a 5- to 15-fold increase in the expression of beta-galactosidase when the fusion strains were grown under iron-deficient conditions. The polarity effects seen by Mu d insertions into entA, entC, and entE were consistent with a single operon, entA(CGB)E. The direction of transcription from iron-regulated promoters was determined ...

  5. Pastato aprūpinimas šiluma šilumos siurbliu su šiluminiu poliumi

    OpenAIRE

    Žostautas, Mauricijus

    2012-01-01

    Baigiamajame magistro darbe nagrinėjamas pastato, aprūpinimas šiluma šilumos siurbliu su šiluminiais poliais. Yra apžvelgtos esamos giliosios bei sekliosios geoterminės energijos panaudojimo panaudojimo galimybės Lietuvoje. Aprašytos prielaidos ir supaprastinimai šiluminių polių skaičiavimui, aprašytos skaičiavimo metodikos. Atlikti šiluminių polių skaičiavimai, naudojantis penkiomis metodikomis. Aprašytas pasirinktas pastatas, apskaičiuoti atitvarų šiluminiai rodikliai, nustatyta pastatui re...

  6. Kvartalo/objekto aprūpinimo šilumine energija variantų analizė

    OpenAIRE

    Pladas, Karolis

    2014-01-01

    Magistro baigiamajame darbe aptariamas Lietuvos ir Europos Sąjungos šalių energetikos sektorius. Apžvelgiamos direktyvos, strategijos, plėtros planai bei teisės aktai skirti energetikos plėtojimui šalyje. Tiriamuoju objektu pasirenkama Trakų Vokės katilinė, kuri aprūpina šiluma kvartalą degindama gamtines dujas vandens šildymo katiluose. Šiame darbe yra nagrinėjamos penkios alternatyvos: kogeneratorius ir dujiniai katilai, kogeneratorius su akumuliacine talpa ir dujiniais katilais, kogenerato...

  7. Multi-analytical characterisation of D’Aprés Cormon by José Veloso Salgado

    Energy Technology Data Exchange (ETDEWEB)

    Cardeira, A.M. [Faculdade de Belas-Artes da Universidade de Lisboa, Largo da Academia Nacional de Belas-Artes, 1249-058 Lisboa (Portugal); Centro de Física Atómica da Universidade de Lisboa, Av. Professor Gama Pinto 2, 1649-003 Lisboa (Portugal); Longelin, S. [Centro de Física Atómica da Universidade de Lisboa, Av. Professor Gama Pinto 2, 1649-003 Lisboa (Portugal); Costa, S.; Candeias, A. [Laboratório José de Figueiredo, Direcção Geral do Património Cultural, Rua das Janelas Verdes 37, 1249-018 Lisboa (Portugal); Laboratório HERCULES e Centro de Química de Évora, Universidade de Évora, Largo Marquês de Marialva 8, 7000 Évora (Portugal); Carvalho, M.L. [Centro de Física Atómica da Universidade de Lisboa, Av. Professor Gama Pinto 2, 1649-003 Lisboa (Portugal); Manso, M., E-mail: marta974@cii.fc.ul.pt [Centro de Física Atómica da Universidade de Lisboa, Av. Professor Gama Pinto 2, 1649-003 Lisboa (Portugal)

    2014-07-15

    This case study reveals the analytical characterisation carried out on ‘D’Aprés Cormon’ (1891) by Veloso Salgado, a copy of ‘Caïn’ (1880) by Fernando Cormon, belonging nowadays to Musée d’Orsay. Infrared Reflectography made in situ revealed underdrawing grid that was used to transpose the original painting to a smaller scale, pictorial style, execution method and retouched/restored areas. In situ EDXRF analysis together with Raman microscopy allowed the identification of gypsum, lead white, titanium white, yellow ochre, vermilion, ultramarine and lamp black. These results provide valuable information about the Salgado’s palette and his production technique.

  8. Multi-analytical characterisation of D’Aprés Cormon by José Veloso Salgado

    International Nuclear Information System (INIS)

    This case study reveals the analytical characterisation carried out on ‘D’Aprés Cormon’ (1891) by Veloso Salgado, a copy of ‘Caïn’ (1880) by Fernando Cormon, belonging nowadays to Musée d’Orsay. Infrared Reflectography made in situ revealed underdrawing grid that was used to transpose the original painting to a smaller scale, pictorial style, execution method and retouched/restored areas. In situ EDXRF analysis together with Raman microscopy allowed the identification of gypsum, lead white, titanium white, yellow ochre, vermilion, ultramarine and lamp black. These results provide valuable information about the Salgado’s palette and his production technique

  9. Is food irradiation harmful

    International Nuclear Information System (INIS)

    The paper reports on a seminar on 'The irradiation of food', held in London, 1987, and organised by the Royal Society and the Association of British Science Writers. A description is given of the food irradiation techniques. Problems with food irradiation are discussed with respect to the nutritional value of food, killing of microorganisms, survival of fungi following treatment, mutation of irradiated bacteria, and chemical changes produced in the food. Monitoring and controls of food that has been irradiated is discussed. A personal opinion of irradiated food by the author is given, including a verdict on irradiated food. (UK)

  10. Detection of irradiated liquor

    International Nuclear Information System (INIS)

    D-2,3-butanediol is formed by irradiation processes in irradiated liquors. This radiolytic product is not formed in unirradiated liquors and its presence can therefore be used to identify whether a liquor has been irradiated or not. The relation meso/dl∼1 for 2,3-butanediol and the amount present in irradiated liquors may therefore be used as an indication of the dose used in the irradiation. (author)

  11. Thermal-Hydraulic Integral Effect Test Result on the Steam Generator Tube Rupture Accident in the APR1400

    International Nuclear Information System (INIS)

    A postulated SGTR (Steam Generator Tube Rupture) event of the APR1400 was experimentally investigated with the thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation). It is generally known that the leak flow rate from the primary to the secondary side is the most important factor affecting the overall thermalhydraulic behaviors such as the depressurization rate of the RCS system, the water level increase and pressurization rate of the secondary system, and the consequent MSSV opening time, etc. As one of the most limiting SGTR accidents, a leak flow equivalent to a double-ended rupture of single and five U-tubes was simulated in this study. The main objectives of these tests were not only to provide physical insight into the system response of the APR1400 reactor during a transient situation of the SGTR but also to present integral effect test data for the validation of the SPACE (Safety and Performance Analysis Computer Code), which is now under development by the Korean nuclear industry

  12. A Bayesian inversion for slip distribution of 1 Apr 2007 Mw8.1 Solomon Islands Earthquake

    Science.gov (United States)

    Chen, T.; Luo, H.

    2013-12-01

    On 1 Apr 2007 the megathrust Mw8.1 Solomon Islands earthquake occurred in the southeast pacific along the New Britain subduction zone. 102 vertical displacement measurements over the southeastern end of the rupture zone from two field surveys after this event provide a unique constraint for slip distribution inversion. In conventional inversion method (such as bounded variable least squares) the smoothing parameter that determines the relative weight placed on fitting the data versus smoothing the slip distribution is often subjectively selected at the bend of the trade-off curve. Here a fully probabilistic inversion method[Fukuda,2008] is applied to estimate distributed slip and smoothing parameter objectively. The joint posterior probability density function of distributed slip and the smoothing parameter is formulated under a Bayesian framework and sampled with Markov chain Monte Carlo method. We estimate the spatial distribution of dip slip associated with the 1 Apr 2007 Solomon Islands earthquake with this method. Early results show a shallower dip angle than previous study and highly variable dip slip both along-strike and down-dip.

  13. Feed and Bleed Operation Analysis during Total Loss of Feedwater Accident for Supporting the PSA of APR+

    International Nuclear Information System (INIS)

    For estimating the safety of APR+ design, the probabilistic safety assessment (PSA) is performed. This paper discusses the minimum success criteria for successful feed and bleed procedure verified and decided when the secondary cooling is failed during Total loss of feedwater (TLOFW) accident. For verifying whether the equipment conditions proposed is enough to manage the transient event without core damage, the analysis is performed by RELAP5/MOD 3.3 code. During TLOFW event, the operator's action time is allowed for 80 minutes and the uncovered core could maintain the stable state for a long time, about a half or one hour by the positive effects given by the fast coolant circulation by RCP pump operation. In simulations considering test scenarios, the minimum required equipment for successful F and B managing during TLOFW without LOOP is verified that it is that F and B procedure could be performed successfully as if the operator would open at least one out of four POSRV within 80 minutes after secondary cooling failure for the RCS depressurization. These analysis results can be used for contribute more realistic and accurate performance of a APR+ PSA

  14. Evaluation of Steam and Gas-flow for APR1400 IRWST using GOTHIC 6.1b

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Mun Soo; Lee, Suk Ho; Kim, Han Gon [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2009-05-15

    The In-Containment Refueling Water Storage Tank (IRWST) of APR1400 is installed at the bottom of the containment building to promote the plant safety functions during an accident. This design feature brings about uncertainty factors that may necessitate improvement or revision of the conventional prediction of temperature and pressure of the containment building in the event of an accident. The hot steam that is released from a RCS break enters the IRWST through four Pressure Relief Dampers (PRDs). The steam is expected to be condensed with water stored in the IRWST, in which water is colder than the incoming steam. The purpose of this study is to investigate the influence of IRWST and PRDs on back pressure and temperature in APR1400 containment by utilizing a containment code: GOTHIC 6.1b (Generation of Thermal-Hydraulic Information for Containments). For this purpose, a multi-compartment and detailed three-dimensional model was developed to predict the steam and gas flow-rate in IRWST.

  15. Unit Risk Quotient (RQ) and Relative Significance of Radionuclide on Flora and Fauna to the EU-APR Optimization

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Keunsung [KHNP-CRI, Daejeon (Korea, Republic of); Kim, Sukhoon [FNC Technology Co., Ltd., Yongin (Korea, Republic of); Lee, Chonghui [KEPCO E and C, Yongin (Korea, Republic of)

    2015-05-15

    As part of the project for acquiring the certification from EUR organization, in accordance with Articles 4.8 and 5.5 specified in Section 2.20 of EUR Volume 2, the effects of ionizing radiation from the standard design of EU-APR on biota and ecosystems during operation and decommissioning phases shall be assessed. This assessment must be carried out according to the ERICA (i.e. Environmental Risk from Ionizing Contaminants: Assessment and management) integrated approach. This paper describes the evaluation results for unit risk quotient and relative significance by radionuclide derived from performing Tier 1 assessment on flora and fauna for the EU-APR design using ERICA Tool. As specified previously, Pa-231 and Th-228 are the most significant for the terrestrial and for the marine/freshwater ecosystems, respectively. And, in terms of environmental risk, those radionuclides having the most impact on flora and fauna are relatively more significant than isotope having the least impact by about 7 to 10 orders of magnitude.

  16. Irradiation of goods

    International Nuclear Information System (INIS)

    The necessary dose and the dosage limits to be observed depend on the kind of product and the purpose of irradiation. Product density and density distribution, product dimensions, but also packaging, transport and storage conditions are specific parameters influencing the conditions of irradiation. The kind of irradiation plant - electron accelerator or gamma plant - , its capacity, transport system and geometric arrangement of the radiation field are factors influencing the irradiation conditions as well. This is exemplified by the irradiation of 3 different products, onions, deep-frozen chicken and high-protein feed. Feasibilities and limits of the irradiation technology are demonstrated. (orig.)

  17. [Preparation and Identification of High Immunogenic A/PR/8/34 Maternal Strain HA Protein for Influenza Virus Classical Reassortment].

    Science.gov (United States)

    Tang, Jing; Xin, Li; Guo, Junfeng; Zhu, Wenfei; Zhang, Heyuan; Lang, Shaohui; Wang, Dayan; Shu, Yuelong

    2016-03-01

    Preparation of maternal strain A/PR/8/34 HA antiserum for influenza virus classical reassortment. A/PR/8/34 virus was digested by bromelain after inactivation and purification. 5%-20% sucrose continuous density gradient centrifugation method was used to purify HA protein. SIRD method was used to select the target protein. SDS-PAGE method was used to identified HA protein. High Immunogenic A/PR/8/34 HA protein was successfully prepared and HI titer reached 10240. High purity HA antiserum was identified by SIRD method. The key reagent in the classical reassortment of influenza virus was prepared, and the complete set of technical methods were explored, which laid the foundation for the independent research and development of seasonal influenza vaccine strains of China. PMID:27396155

  18. Evaluation of Effect of N{sub 2} Gas on the Cooling Capability of Passive Auxiliary Feedwater System (PAFS) in APR+

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Yun Je; Kang, Kyong Ho; Yun, Byong Jo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    In Korea, Advanced Power Reactor Plus (APR+) has being developed by adding passive safety features to Advanced Power Reactor 1400MWe (APR1400). Passive Auxiliary Feedwater System (PAFS) is one of passive system adopted in the APR+ to replace the conventional active auxiliary feedwater system. Because PAFS removes decay heat from the reactor core, it is required to verify the performance of PAFS in postulated accidents cases. In addition, an effect of noncondensable gas on the heat removal capability of PAFS should be evaluated since the non-condensable gas may deteriorate a condensation heat transfer through the condensation heat exchanger in PAFS. In this study, the effect of N{sub 2} gas was evaluated using MARS

  19. Neutron and thermal hydraulic analyses of irradiated fuel plates for Molybdenum-99 production

    International Nuclear Information System (INIS)

    Neutron and thermal hydraulic analyses of the LEU targets irradiated in a research reactor for 99Mo production were performed to investigate the heat production during irradiation, decay heat after irradiation, and the cooling capacity with various cooling conditions. The heat production on the targets during irradiation was evaluated by McCARD. The decay heat after irradiation was estimated by ORIGEN-APR and compared against ANSI-79. The cooling capacity of forced convection during irradiation and the cooling capacity of natural convection after irradiation were evaluated with time. The coolant and cladding wall temperatures and thermal margins (i. e. minimum Onset of Nucleate Boiling (ONB) temperature margin and minimum Critical Heat Flux (CHF) ratio) were evaluated with a consideration of a total power peaking factor and engineering hot channel factors. While targets were under the water, the cladding wall temperature maintained below ONB temperature. While targets were exposed to the air in hot cell for further 99Mo production process, the cladding wall temperature maintained below 75% of solidus temperature

  20. The subtilisin-like protease AprV2 is required for virulence and uses a novel disulphide-tethered exosite to bind substrates.

    Directory of Open Access Journals (Sweden)

    Ruth M Kennan

    Full Text Available Many bacterial pathogens produce extracellular proteases that degrade the extracellular matrix of the host and therefore are involved in disease pathogenesis. Dichelobacter nodosus is the causative agent of ovine footrot, a highly contagious disease that is characterized by the separation of the hoof from the underlying tissue. D. nodosus secretes three subtilisin-like proteases whose analysis forms the basis of diagnostic tests that differentiate between virulent and benign strains and have been postulated to play a role in virulence. We have constructed protease mutants of D. nodosus; their analysis in a sheep virulence model revealed that one of these enzymes, AprV2, was required for virulence. These studies challenge the previous hypothesis that the elastase activity of AprV2 is important for disease progression, since aprV2 mutants were virulent when complemented with aprB2, which encodes a variant that has impaired elastase activity. We have determined the crystal structures of both AprV2 and AprB2 and characterized the biological activity of these enzymes. These data reveal that an unusual extended disulphide-tethered loop functions as an exosite, mediating effective enzyme-substrate interactions. The disulphide bond and Tyr92, which was located at the exposed end of the loop, were functionally important. Bioinformatic analyses suggested that other pathogenic bacteria may have proteases that utilize a similar mechanism. In conclusion, we have used an integrated multidisciplinary combination of bacterial genetics, whole animal virulence trials in the original host, biochemical studies, and comprehensive analysis of crystal structures to provide the first definitive evidence that the extracellular secreted proteases produced by D. nodosus are required for virulence and to elucidate the molecular mechanism by which these proteases bind to their natural substrates. We postulate that this exosite mechanism may be used by proteases produced by

  1. Contribution to the determination of the neutronic parameters uncertainties of a compact heterogeneous core: the material testing Jules Horowitz reactor; Contribution a l'etude des incertitudes des parametres neutroniques d'un coeur compact et heterogene: le reacteur d'irradiation Jules Horowitz

    Energy Technology Data Exchange (ETDEWEB)

    Di Salvo, J

    2002-07-01

    The design studies of the future Material Testing Reactor Jules Horowitz require the development of an adapted neutronic calculation route. To guarantee good accuracy and save time cost, some approximations with deterministic modelling (APOLLO2 / CRONOS2) are needed. As no relevant integral experiments are yet available to ensure the accuracy of the calculation, the results need to be validated by a rigorous methodical approach, which is based on comparison against numerical benchmarks (Monte Carlo TRIPOLI4 code). In order to complete the validation results, sensitivity coefficients of main neutronic parameters to nuclear data are very useful to get an estimate of the final uncertainty on the calculation. Unfortunately, most of covariance information is missing in the recent evaluated files such as JEF-2.2. To generate missing covariance matrices, a method based on the comparison of different independent evaluations is used in this study. Special attention is paid to the determination of sensitivity coefficients, using perturbation methods and direct calculations. This study points out the importance of the non-diagonal elements of the covariance matrices as well as the neutron capture cross section uncertainty of the 27Al in the thermal range. In complement to uncertainty studies, it will be still necessary to obtain integral experimental validation of the Jules Horowitz Reactor neutronic parameters calculations. (author)

  2. Monoclinically distorted perovskites, A2ZnTiO6 (A=Pr, Gd): Rietveld refinement, and dielectric studies

    International Nuclear Information System (INIS)

    Double perovskite related oxide A2ZnTiO6A=Pr, Gd were synthesized by the solid state reaction method at 1523 K. The structure and microstructure of the compounds were studied by X-ray, SAED and FESEM. Rietveld refinement of the powder X-ray analysis shows that the compounds crystallizes in monoclinic space group P21/n (a+b−b−) with unit cell parameter √2ap×√2ap×2ap (a=5.5026(1) Å, b=5.6305(1) Å, c=7.8149(1) Å, β=90.02(1)° for Pr2ZnTiO6 and a=5.3621(1) Å, b=5.6565(2) Å, c=7.6779(2) Å and β=90.264(2)° for Gd2ZnTiO6. Electron diffraction study confirms P21/n symmetry of the oxides. The monoclinic distortion is larger in Gd2ZnTiO6 than Pr2ZnTiO6 which is associated with the tolerance factor and the tilting angle of ZnO6 and TiO6 octahedra (ϕ=13.64° for Pr2ZnTiO6 and 16.51° for Gd2ZnTiO6). The compounds are highly ordered. The charge and size difference between B site cations are the driving force for the ordering of the B′O6 and B″O6 octahedra. Pr2ZnTiO6 shows a dielectric constant of 27 and dielectric loss of 0.003 while Gd2ZnTiO6 has a dielectric constant of 17 and dielectric loss of 0.005 measured at 1 MHz. - Graphical abstract: Synthesis of new double perovskite dielectric material with very low dielectric loss. - Highlights: • Synthesis of new monoclinically distorted double perovskite (Pr2ZnTiO6). • Synthesis of monoclinically distorted double perovskite (Gd2ZnTiO6). • Selected area electron diffraction study of A2ZnTiO6 (A=Pr, Gd). • Study of dielectric properties of A2ZnTiO6 (A=Pr, Gd)

  3. Prospective study of treatment techniques to minimize the volume of pelvic small bowel with reduction of acute and late effects associated with pelvic irradiation

    International Nuclear Information System (INIS)

    The volume, distribution, and mobility of opacified pelvic small bowel (PSB) were determined by fluoroscopy and orthogonal radiographs in 150 consecutive patients undergoing pelvic irradiation. Various techniques including uteropexy, omental transposition, bladder distention, inclining the patient, and anterior abdominal wall compression in the supine and prone treatment position were studied for their effect on the volume and location of small bowel within the pelvis. Abdominal wall compression in the prone position combined with bladder distention was selected for further investigation because of its simplicity, reproducibility, patient comfort, and ability to displace the small bowel. Factors correlating with the volume of pelvic small bowel (PSB) included prior pelvic surgery, pelvic irradiation (XRT), and body mass index. After pelvic surgery, especially following abdominoperineal resection (APR), there was a greater volume of PSB which was also less mobile. The severity of acute gastrointestinal effects positively correlated with the volume of irradiated small bowel. Overall, 67% of patients experienced little or no diarrhea, 30% developed mild diarrhea, and no patient required treatment interruption. Late gastrointestinal effects correlated with the prior pelvic surgery and with the volume of small bowel receiving greater than 45 Gy. Small bowel obstruction was not observed in 75 patients who had no previous pelvic surgery. However, following pelvic surgery excluding APR, 2/50 patients and following APR, 3/25 patients developed small bowel obstruction

  4. Strong synergy with APR-246 and DNA-damaging drugs in primary cancer cells from patients with TP53 mutant High-Grade Serous ovarian cancer

    OpenAIRE

    Fransson, Åsa; Glaessgen, Daria; Alfredsson, Jessica; Wiman, Klas G.; Bajalica-Lagercrantz, Svetlana; Mohell, Nina

    2016-01-01

    Background Mutation in the tumor suppressor gene TP53 is an early event in the development of high-grade serous (HGS) ovarian cancer and is identified in more than 96 % of HGS cancer patients. APR-246 (PRIMA-1MET) is the first clinical-stage compound that reactivates mutant p53 protein by refolding it to wild type conformation, thus inducing apoptosis. APR-246 has been tested as monotherapy in a Phase I/IIa clinical study in hematological malignancies and prostate cancer with promising result...

  5. Food irradiation in China

    International Nuclear Information System (INIS)

    In this paper, the author discussed the recent situation of food irradiation in China, its history, facilities, clearance, commercialization, and with emphasis on market testing and public acceptance of irradiated food. (author)

  6. Economics of food irradiation

    International Nuclear Information System (INIS)

    Economic aspects of food irradiation and direct economic benefits accruing from the application of food irradiation are discussed. A formula is presented to estimate the net economic benefit due to radiation processing of food. (M.G.B .)

  7. JMTR irradiation handbook

    International Nuclear Information System (INIS)

    A wide variety of nuclear irradiation and post-irradiation experiments are available using the JMTR (Japan Materials Testing Reactor, 50 MW) and the multi-cell hot laboratory associated with the JMTR. In this Handbook, an application manual for conducting irradiation and post-irradiation experiments using those facilities is provided. The Handbook is primarily designed to aid the experimenter and to serve as a reference for communications between the experimenter and the Division of JMTR Project. (author)

  8. JMTR irradiation handbook

    International Nuclear Information System (INIS)

    A wide variety of nuclear irradiation and post-irradiation experiments are available using the Japan Materials Testing Reactor, 50 MW (JMTR) and the multi-cell hot laboratory associated with the JMTR. In this Handbook, an application manual for conducting irradiation and post-irradiation experiments using those facilities is provided. The Handbook is primarily designed to aid the experimenter and to serve as a reference for communications between the experimenter and the Department of JMTR Project. (author)

  9. Containers in food irradiation

    International Nuclear Information System (INIS)

    The preservation of food by irradiation is promising technology which increases industrial application. Packaging of irradiated foods is an integral part of the process. Judicious selection of the package material for successful trade is essential. In this paper is presented a brief review of important aspects of packaging in food irradiation

  10. Evolution a court terme des formes du phosphore d'un sol ferrallitique apres apports d'une boue urbaine

    OpenAIRE

    Brossard, M.; Mench, Michel; CLAIRON, Maurice; Laurent, J.Y.

    1991-01-01

    Une boue urbaine a été incorporée aux doses de 10 et 100 t (MS)●ha-1 dans l’horizon 0-20 cm d’un sol ferrallitique de Guadeloupe. L’expérimentation est conduite en microparcelles de plein champ pendant 500 j. Après prélèvement des échantillons de sol, les mottes de boue non fragmentées de taille supérieure à 5 mm sont triées manuellement. Les formes du phosphore du sol analysées sont les suivantes : phosphore total (Pt), organique (Po), minéral (Pm), extrait par un mélange bicarbonate-f...

  11. O après-coup e a reconsolidação da memória

    Directory of Open Access Journals (Sweden)

    Graziele Luiza Barizon Scopel Gerbasi

    2015-04-01

    Full Text Available Em diferentes áreas do conhecimento é reconhecido que a memória está sujeita a transformações ao longo do tempo. Partindo desse pressuposto, o objetivo do presente estudo é apresentar uma discussão compreendendo a ideia de que nossas recordações são suscetíveis a transformações e a concepção de après-coup. Há o delineamento de algumas ideias acerca da temporalidade em Psicanálise e do mecanismo de reconsolidação da memória segundo as Neurociências. Utilizando-se tais conceitos, evidenciou-se a viabilidade de se pensar uma interlocução entre a Psicanálise e as Neurociências.

  12. Fernand Braudel : Civilisation matérielle, Economie et Capitalisme trente ans après

    OpenAIRE

    Garner, Guillaume

    2013-01-01

    Trente ans après la publication par Fernand Braudel de sa trilogie Civilisation matérielle, Économie et Capitalisme XVe-XVIIIe siècle, l’IFHA (Guillaume Garner) et le Global and European Studies Institute de l’Université de Leipzig (Matthias Middell) se sont associés pour organiser une journée d’études franco-allemande, qui s’est tenue à Leipzig le 2 octobre 2009, dont le but était moins de discuter de la pertinence des conclusions formulées par F. Braudel que d’évaluer, sur le plan des probl...

  13. 返工设备——APR-5000-XLS阵列封装返工系统

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    Metcal公司2001年推出阵列封装返工系统,确立了可重复性、精度和温度控制的新标准。该公司最近推出的APR-5000-XLS阵列封装返工系统,再次确立了精确、有成本效益的、最大范围元件类型的返工基准,可处理BGA,CSP,LGA(Land Grid Array),Micro SMD,MLF(Micro-Lead Frame),BCC(Bumped Chip Component)多种封装。

  14. 返工设备——APR-5000-XLS阵列封装返工系统

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    APR-5000-XLS阵列封装返工系统可处理BGA,CSP,LGA(Land Grid Array),Micro SMD,MLF(Micro—Lead Frame),BCC(Bumped Chip Component)多种封装。其可处理的板尺寸达610mm×610mm(24.5″×24.5″),厚度达6.35mm(0.25″)。双程、全空气底部预热,能处理大小不同规格的PCB板。采用5个热电偶输入和闭环RTD温度控制,

  15. O après-coup e a reconsolidação da memória

    OpenAIRE

    Graziele Luiza Barizon Scopel Gerbasi; Paulo José da Costa

    2015-01-01

    Em diferentes áreas do conhecimento é reconhecido que a memória está sujeita a transformações ao longo do tempo. Partindo desse pressuposto, o objetivo do presente estudo é apresentar uma discussão compreendendo a ideia de que nossas recordações são suscetíveis a transformações e a concepção de après-coup. Há o delineamento de algumas ideias acerca da temporalidade em Psicanálise e do mecanismo de reconsolidação da memória segundo as Neurociências. Utilizando-se tais conceitos, evidenciou-se ...

  16. Performance and scenario evaluation of PAFS through the LOFW accident in APR1400 by using MARS code

    International Nuclear Information System (INIS)

    In order to enhance the safety feature of the APR1400 through the passive ways, the passive auxiliary feedwater system(PAFS) is under preliminary consideration by KAERI. For the successful adaptation of PAFS, accident scenario evaluation of PWR plant that is assumed to have the PAFS system should be performed. Condensing heat exchanger assemblies are installed at the exterior boundary of the containment building per one steam generator. The performance of the heat exchanger is designed to remove the decay heat of the fuel completely. In normal operation condition, PAFS system is not connected with the steam and feed lines. A Total Loss of Feed Water(TLOFW) accident is selected for the performance and scenario evaluation after the severity check. The PAFS connection valves are open at the signal of 25% level trip of steam generator. With the single failure assumption of PAFS open valve, the scenario propagations are calculated by using MARS code

  17. Performance and scenario evaluation of PAFS through the LOFW accident in APR1400 by using MARS code

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Sung Won; Bae, Byoung Uhn; Yun, Byong Jo [Korea Atomic Energy Institute, Daejeon (Korea, Republic of)

    2009-07-01

    In order to enhance the safety feature of the APR1400 through the passive ways, the passive auxiliary feedwater system(PAFS) is under preliminary consideration by KAERI. For the successful adaptation of PAFS, accident scenario evaluation of PWR plant that is assumed to have the PAFS system should be performed. Condensing heat exchanger assemblies are installed at the exterior boundary of the containment building per one steam generator. The performance of the heat exchanger is designed to remove the decay heat of the fuel completely. In normal operation condition, PAFS system is not connected with the steam and feed lines. A Total Loss of Feed Water(TLOFW) accident is selected for the performance and scenario evaluation after the severity check. The PAFS connection valves are open at the signal of 25% level trip of steam generator. With the single failure assumption of PAFS open valve, the scenario propagations are calculated by using MARS code.

  18. Conceptual design of passive containment cooling system with air holdup tanks in the concrete containment of improved APR+

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Byong Guk; NO, Hee Cheon, E-mail: hcno@kaist.ac.kr

    2014-02-15

    Highlights: • Conceptual design of passive containment cooling system (PCCS) based on APR+ is proposed. • Decay heat removal rate is to be maximized by introducing air holdup tanks (AHT). • Only air is transported into the AHT decreasing air mass fraction near HXs inside containment and increasing heat transfer rates. • Large AHT volume gives significantly higher heat removal rate. • External HXs have merits over in-tube HXs for long term cooling. - Abstract: The accident of the Fukushima nuclear power plant emphasized passive systems against prolonged station blackout. This paper aims at conceptual design of passive containment cooling system (PCCS) based on APR+, an advanced PWR developed in Korea with passive auxiliary feedwater system (PAFS). In the design, decay heat removal rate is to be maximized by introducing air holdup tanks (AHT). The AHT is an isolated space disposed above IRWST and is connected to the containment free space by vent lines through IRWST water and PAFS heat exchangers (HXs), where steam generated by decay heat is condensed. Since a lot of steam is condensed through in-tube HXs and IRWST water, air is mainly transported into the AHT decreasing air mass fraction near HXs inside containment and increasing heat transfer rates. Several design options (AHT volume, flow distribution in vent lines, HX types) are evaluated via scoping analysis. The scoping analysis had proved that AHT (>10% containment volume) decreased the required number of PCCS HXs to be installed less than a half, failure of valves caused marginal increase in HXs to be installed, and external HXs had merits over in-tube HXs for long term cooling.

  19. Design of condensation heat exchanger for the PAFS (Passive Auxiliary Feedwater System) of APR+ (Advanced Power Reactor Plus)

    International Nuclear Information System (INIS)

    Highlights: ► Condensation heat exchanger for the PAFS (Passive Auxiliary Feedwater System) was designed. ► The requirement of the heat removal rate and the prevention of water hammer phenomena were considered. ► The proposed design of the heat exchanger satisfied the requirement of the passive heat removal system. - Abstract: The APR+ (Advanced Power Reactor Plus), a next generation nuclear power plant in Korea, has adopted the PAFS (Passive Auxiliary Feedwater System) on the secondary system of the steam generator (SG) as an advanced safety feature. It is intended to replace the conventional auxiliary feedwater system, which consists of active components for the SG in a passive way. It removes decay heat from the reactor core by cooling down the secondary system of the SG using a condensation heat exchanger installed in the PCCT (Passive Condensation Cooling Tank). The objective of this study is to design a condensation heat exchanger for the PAFS and to evaluate the cooling performance for the proposed design using the thermal hydraulic system analysis code, MARS (Multi-dimensional Analysis for Reactor Safety). Requirements such as the heat removal capacity and the prevention of water hammer were preferentially considered to determine the design parameters of the heat exchanger tube. The MARS code analysis result showed that the proposed design of the PAFS heat exchanger is able to cool down the required amount of decay heat. The distribution of a liquid volume fraction and flow regime predicted by the MARS code shows that the proposed design of the heat exchanger excludes the water hammer inside the tube. Estimation of a two-phase flow pressure drop indicates that the pressure drop inside the tube is negligible compared to the total pressure drop in the PAFS. From the MARS code analysis, it is concluded that the proposed design of the condensation heat exchanger in the PAFS satisfies the overall criteria for the performance of the passive heat removal

  20. Canadian Food Irradiation Facilities

    International Nuclear Information System (INIS)

    Atomic Energy of Canada Limited (AECL) began work on the irradiation of potatoes in 1956, using spent fuel rods as the radiation source. In 1958 the first Gammacell 220, a self-contained irradiator, was designed and manufactured by AECL, and cobalt-60 was then used exclusively in the food irradiation programme. In 1960 the first food and drug clearance was obtained for potatoes. The next stage was to demonstrate to the potato industry that cobalt-60 was a safe, simple and reliable tool, and that irradiation would inhibit sprouting under field conditions. A mobile irradiator was designed and produced by AECL in 1961 to carry out this pilot-plant programme. The irradiator was mounted on a fully-equipped road trailer and spent the 1961/1962 season irradiating one million pounds of potatoes at various points in Eastern Canada. In 1965 the first commercial food irradiator was designed and built by AECL for Newfield Products, Ltd. Whilst the potato programme was under way, AECL initiated co-operative programmes with Canadian food research laboratories, using additional Gammacells. In 1960, AECL constructed an irradiation facility in a shielded room at its own plant in Ottawa for the irradiation of larger objects, such as sides of pork and stems of bananas. During 1963 the mobile irradiator, already a most useful tool, was made more versatile when its source strength was increased and it was equipped with a product cooling system and van air conditioning. Following these modifications, the unit was employed in California for the irradiation of a wide spectrum of fruits at the United States Department of Agriculture Station in Fresno. The Gammacell, mobile irradiator, shielded-room facility, the commercial food irradiator and some of the main food programmes are described in detail. There is an increasing amount of interest in irradiation by the food industry, and prospects are encouraging for future installations. (author)

  1. Welding irradiated stainless steel

    International Nuclear Information System (INIS)

    Conventional welding processes produced severe underbead cracking in irradiated stainless steel containing 1 to 33 appm helium from n,a reactions. A shallow penetration overlay technique was successfully demonstrated for welding irradiated stainless steel. The technique was applied to irradiated 304 stainless steel that contained 10 appm helium. Surface cracking, present in conventional welds made on the same steel at the same and lower helium concentrations, was eliminated. Underbead cracking was minimal compared to conventional welding methods. However, cracking in the irradiated material was greater than in tritium charged and aged material at the same helium concentrations. The overlay technique provides a potential method for repair or modification of irradiated reactor materials

  2. APR-246 (PRIMA-1(MET)) strongly synergizes with AZD2281 (olaparib) induced PARP inhibition to induce apoptosis in non-small cell lung cancer cell lines.

    Science.gov (United States)

    Deben, Christophe; Lardon, Filip; Wouters, An; Op de Beeck, Ken; Van den Bossche, Jolien; Jacobs, Julie; Van Der Steen, Nele; Peeters, Marc; Rolfo, Christian; Deschoolmeester, Vanessa; Pauwels, Patrick

    2016-06-01

    APR-246 (PRIMA-1(Met)) is able to bind mutant p53 and restore its normal conformation and function. The compound has also been shown to increase intracellular ROS levels. Importantly, the poly-[ADP-ribose] polymerase-1 (PARP-1) enzyme plays an important role in the repair of ROS-induced DNA damage. We hypothesize that by blocking this repair with the PARP-inhibitor AZD2281 (olaparib), DNA damage would accumulate in the cell leading to massive apoptosis. We observed that APR-246 synergistically enhanced the cytotoxic response of olaparib in TP53 mutant non-small cell lung cancer cell lines, resulting in a strong apoptotic response. In the presence of wild type p53 a G2/M cell cycle block was predominantly observed. NOXA expression levels were significantly increased in a TP53 mutant background, and remained unchanged in the wild type cell line. The combined treatment of APR-246 and olaparib induced cell death that was associated with increased ROS production, accumulation of DNA damage and translocation of p53 to the mitochondria. Out data suggest a promising targeted combination strategy in which the response to olaparib is synergistically enhanced by the addition of APR-246, especially in a TP53 mutant background. PMID:26975633

  3. Irradiation effects on polycaprolactone

    International Nuclear Information System (INIS)

    The structure and some physical properties of γ-irradiated polycaprolactone (PCL), a semi-crystalline linear saturated polyester, were studied as function of the irradiation dose level. The critical dose level for gel formation is 26 Mrad and above this irradiation dose the number of scission events is similar to the number of crosslinking events. G.p.c. results show that the initial rather narrow molecular weight distribution gradually widens with increasing dose in the pre-gelation region. A significant difference between first and second d.s.c. scans of irradiated PCL is shown and explained. Scission and crosslinking reactions associated with the irradiation process occur preferentially in the non-ordered regions. Small irradiation doses, 2 to 5 Mrad, are shown to have a dramatic effect on the tensile elongation at break by converting ductile PCL samples into brittle materials. (author)

  4. Identification of irradiated chicken

    International Nuclear Information System (INIS)

    Frozen chicken and chicken parts were irradiated at a dose of 5 kGy with Co-60. The irradiated chicken and chicken parts were identified by determination of three radiation-induced hydrocarbons from the lipid fraction. Isolation was carried out by high-vacuum distillation with a cold-finger apparatus. The detection of the hydrocarbons was possible in all irradiated samples by gaschromatography/mass spectrometry. (orig.)

  5. A systematic core design method for reduction of critical boron concentration in APR 1400 with gadolinia-bearing assembly

    International Nuclear Information System (INIS)

    Highlights: • A systematic core design method reduces CBC of APR 1400. • The core design method solves a non-linear programming problem. • The solution is a set of new Gd-bearing fuel assembly design. • LP loading new Gd-bearing fuel assembly designs achieves target CBCs. • Lower L/H ratio shows longer hold-down effect than higher L/H ratio. - Abstract: A systematic core design method is developed to design Gd-bearing fuel assembly having two types of Gd rods, low-wt%-Gd rod and high-wt%-Gd rod. The purpose of the method is to lower the critical boron concentration (CBC) of a preliminary core loading pattern, and consequently to achieve more negative or less positive moderator temperature coefficient (MTC). The proposed core design method is a process of solving a non-linear programming problem stated with a system of equations. In this method, both the ratio of the number of low-wt%-Gd rod to the number of high-wt%-Gd rod (r) and the assembly average Gd wt% (w) are the solution variables of the system of equations. The target function is the amount of soluble boron concentration reduction, ΔCBC, which is correlated with the reactivity change, ΔkFA, per Gd-bearing fuel assembly by a quadratic reactivity equation. The coefficients of the quadratic equations are calculated prior to the determination of Gd-bearing fuel assembly pattern, using the least square method. The constraints required to determine (r, w) are physically realizable Gd rods pattern, Δki close to ΔkFA derived from ΔCBC, etc. An objective function, min[f(∑i(ΔkFA-Δki))], enables a final loading pattern to reach a target CBC. This design methodology is applied to APR 1400. Total six cases with various target CBCs are investigated to validate the proposed method. CASMO-3/MASTER calculations with new design assemblies produce lower CBCs at BOC than target CBCs keeping maximum pin power below the safety limit, and thus show more negative MTC

  6. Gamma irradiation devices

    International Nuclear Information System (INIS)

    The main parameters and the preparation procedures of the gamma radiation sources frequently applied for irradiation purposes are discussed. In addition to 60Co and 137Cs sources also the nuclear power plants offer further opportunities: spent fuel elements and products of certain (n,γ) reactions can serve as irradiation sources. Laboratory scale equipments, pilot plant facilities for batch or continuous operation, continuous industrial irradiators and special multipurpose, mobile and panorama type facilities are reviewed including those in Canada, USA, India, the Soviet Union, Hungary, UK, Japan and Australia. For irradiator design the source geometry dependence of the spatial distribution of dose rates can be calculated. (V.N.)

  7. Irradiation of food

    International Nuclear Information System (INIS)

    A committee has on instructions from the swedish government made an inquiry into the possible effects on health and working environment from irradition of food. In this report, a review is presented on the known positiv and negative effects of food irradiation Costs, availabilty, shelf life and quality of irradiated food are also discussed. According to the report, the production of radiolysis products during irradiation is not easily evaluated. The health risks from irradiation of spices are estimated to be lower than the risks associated with the ethenoxid treatment presently used. (L.E.)

  8. Food irradiation. An alternative

    International Nuclear Information System (INIS)

    In order to start a food irradiation program, one needs to perform some tests, such as: local handling problems, consumer acceptance and government licenses. At this point the cost of a special food irradiator can be considered a too high investment. It is proposed that for the irradiation of a few tons of several food items, a commercial irradiator for medical products sterilization be employed. With the use of an ''experimental loop'' and some special positions inside the irradiation chamber, it is possible to irradiate even potatoes and onions, at doses ranging from 100 Gy to 200 Gy. The quantities, depending on the source activity, can be around 300 kg per hour. For doses near 10 kGy, the normal procedure used for sterilization of medical products can be employed, while changing the cycle on the machine. In the case of an experimental loop within a JS-7400 (AECC) irradiator at a dose rate of 20 Gy per minute, around 200 kg of potatoes per hour can be irradiated. The experimental positions inside the chamber have a dose rate of 60 Gy per hour, and the batch capacity is 250 kg, so that 250 kg can be irradiated each 1,5 hour

  9. Decreased influenza virus pathogenesis by infection with germicidal UV-irradiated airborne virus

    International Nuclear Information System (INIS)

    Respiratory infections are acquired by the inhalation of airborne microorganisms. To evaluate the effect of germicidal UV-irradiation on airborne contagion, infectious clouds of influenza A/PR8/34 virus were generated and exposed to known intensities of UV. Thereafter, the airborne virus was used to infect mice wherein the pathogenesis of the viral pneumonia was evaluated. Increasing doses of UV inactivated infectious airborne virus in a dose-dependent manner and reduced the mortality rates as compared to an infectious cloud of untreated virus. When a sublethal cloud of infectious virus was used, UV-irradiation modified the viral infection, as quantified by pulmonary virus titers, from a severe pneumonitis to a milder form of the disease. (author)

  10. Pagure {sup 60}Co panoramic irradiation facility; Pagure irradiateur panoramique au {sup 60}Co

    Energy Technology Data Exchange (ETDEWEB)

    Puig, J.R.; Laizier, J.; Lorin, M.; Laroche, R. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-07-01

    After a description of the various parts of 'PAGURE', a 10 KCi panoramic irradiation facility, and of the operations data, a critic scrutiny is given. From the experience of five years operations, working of the facility can be thought of very satisfying. From the point of view of standardization of irradiation facilities, PAGURE can be taken, in its range, as a standard design. (authors) [French] Apres avoir decrit les differents elements constitutifs de 1'irradiateur panoramique de 10 KCi 'PAGURE' et precise les donnees d'exploitation, on en fait l'examen critique. A la lumiere de cinq annees d'utilisation, le fonctionnement de 1'irradiateur apparait extremement satisfaisant. Dans une perspective de standardisation des appareils, on peut, dans sa gamme, le considerer comme une realisation type. (auteurs)

  11. Extracorporeal irradiation of calves blood. Effects on: the lymphocytes, the blood-platelet function, seric proteins, and fibrinogen; Irradiation extracorporelle du sang de veau effets sur: les lymphocytes, la fonction plaquettaire, les proteines seriques et le fibrinogene

    Energy Technology Data Exchange (ETDEWEB)

    Hollard, D.; Suscillon, M.; Benabid, Y.; Concord, E.; Ivanoff, M.; Laurent, M.; Rambaud, F. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1969-07-01

    The present paper reports the results obtained after extracorporeal irradiation of circulating blood of calves. Animals are divided in 3 groups as follows: - control animals: blood circulation without irradiation; - calves which received 40000 rads during 24 hours of continuous irradiation; - calves which received the same dose, during a period of 5 days (5 hours every day). The more interesting results are: - the early lymphopenia which persists for 7 or 8 weeks and may be in relationship with the change of immunoglobulins; - a constant hyperfibrinemia (12 g/l) never reported, as far as we know, by authors using I.E.C. Several hypothesis are advanced to explain this phenomenon. (authors) [French] Ce travail presente l'ensemble des resultats hematologiques obtenus apres irradiation extracorporelle du sang de veaux repartis en 3 series: - veaux temoins: circulation du sang sans irradiation - veaux soumis a une irradiation continue dose globale integree de 40000 rads en 24 heures; - veaux ayant recu la meme dose globale en irradiation fractionnee repartie sur 5 jours (5 heures par jour). Les resultats les plus marquants sont d'une part une lymphopenie precoce se prolongeant durant 7 a 8 semaines et qui pourrait etre reliee aux modifications observees sur les immunoglobulines. D'autre part une hyperfibrinemie (12 g/l) constante, apparemment jamais signalee par d'autres auteurs utilisant l'I.E.C. Plusieurs hypotheses explicatives de ce phenomene sont exposees et sont a l'etude. (auteurs)

  12. Facts about food irradiation: Chemical changes in irradiated foods

    International Nuclear Information System (INIS)

    This fact sheet addresses the safety of irradiated food. The irradiation process produces very little chemical change in food, and laboratory experiments have shown no harmful effects in animals fed with irradiated milk powder. 3 refs

  13. Mobile irradiation robot - computer modelling of the irradiation process

    International Nuclear Information System (INIS)

    For irradiation of cultural objects, which are damaged by wood-destroying insects or fungi, with the automatized irradiation robot, the computer code MOBROB1 for irradiation planning was developed and is presented. (author)

  14. Some examples of a differential calorimeter use for low temperature thermal effects measurement; Quelques exemples d'utilisation d'un calorimetre differentiel a puissance compensee pour des mesures d'anomalies thermiques a basses temperatures

    Energy Technology Data Exchange (ETDEWEB)

    Bochirol, L; Bonjour, E

    1967-07-01

    The principle of a differential calorimeter is briefly described. The apparatus allows a direct and continuous determination of the differential heat-capacity between a sample and a reference, in the range 20 to 600 deg. K approximately. Some examples concerning measurements at low temperatures of reversible or non reversible thermal effects are given. They show the possibilities of the apparatus and are connected with: - detection and measurements of thermal effects associated to structural transformations in elastomers at low temperatures, - measurements of Wigner energy released after neutron irradiations at 77 deg. K for: recrystallized pyro-graphites; high purity iron, aluminium. [French] On decrit brievement le principe d'un calorimetre differentiel qui permet la determination directe et continue de la difference de chaleur specifique apparente entre un echantillon et une reference, dans une gamme de temperatures s'etendant de 20 a 600 deg. K environ. On donne quelques exemples de mesure a basses temperatures d'effets thermiques reversibles ou non reversibles. Ils montrent les possibilites de l'appareillage et concernent: - la detection et la mesure d'effets thermiques associes a des transformations structurales dans des elastomeres a basse temperature, - la mesure du degagement d'energie Wigner apres des irradiations neutroniques a 77 deg. K dans: des pyrographites recristallises; du fer de haute purete et de l'aluminium. (auteurs)

  15. APR-246/PRIMA-1(MET) rescues epidermal differentiation in skin keratinocytes derived from EEC syndrome patients with p63 mutations.

    Science.gov (United States)

    Shen, Jinfeng; van den Bogaard, Ellen H; Kouwenhoven, Evelyn N; Bykov, Vladimir J N; Rinne, Tuula; Zhang, Qiang; Tjabringa, Geuranne S; Gilissen, Christian; van Heeringen, Simon J; Schalkwijk, Joost; van Bokhoven, Hans; Wiman, Klas G; Zhou, Huiqing

    2013-02-01

    p53 and p63 share extensive sequence and structure homology. p53 is frequently mutated in cancer, whereas mutations in p63 cause developmental disorders manifested in ectodermal dysplasia, limb defects, and orofacial clefting. We have established primary adult skin keratinocytes from ectrodactyly, ectodermal dysplasia, and cleft lip/palate (EEC) syndrome patients with p63 mutations as an in vitro human model to study the disease mechanism in the skin of EEC patients. We show that these patient keratinocytes cultured either in submerged 2D cultures or in 3D skin equivalents have impaired epidermal differentiation and stratification. Treatment of these patient keratinocytes with the mutant p53-targeting compound APR-246/PRIMA-1(MET) (p53 reactivation and induction of massive apoptosis) that has been successfully tested in a phase I/II clinical trial in cancer patients partially but consistently rescued morphological features and gene expression during epidermal stratification in both 2D and 3D models. This rescue coincides with restoration of p63 target-gene expression. Our data show that EEC patient keratinocytes with p63 mutations can be used for characterization of the abnormal molecular circuitry in patient skin and may open possibilities for the design of novel pharmacological treatment strategies for patients with mutant p63-associated developmental abnormalities. PMID:23355676

  16. A study on issues and solutions about logic functions applied to computerized procedure system in APR1400

    International Nuclear Information System (INIS)

    Plant procedures are instructions to guide operators in monitoring, decision making, and controlling nuclear power plants(NPPs). While plant procedures historically have been paper-based, computerized-based procedures are being developed to overcome the drawbacks of paper-based procedures. The CPS is used to integrate the operational instructions, plan process information and computerized operator support functions in advanced main control room (MCR) of APR1400. The logic functions applied to CPS are three categories: Procedure Entry Condition (PEC), Continuously Applied Step (CAS) re-execution condition, instruction evaluation. This automation using logic function can reduce operator 2019's burden about monitoring, decision making, controlling NPPs but this automation can also lower situation awareness and operator in the loop. These automation issues caused by logic function shall be closed to apply computerized procedure. This paper introduces issues drawn by system designer, plant operators, and human factors engineers. To close these introduced issues, this paper suggests solutions from system design, procedure writer's guideline, and operator training. This paper introduces issues drawn by system designer, plant operators, and human factors engineers. To close these introduced issues, this paper suggests solutions from system design, procedure writer's guideline, and operator training

  17. The fifteenth period report on the cooperative utilization of the AVF cyclotron at Osaka University RCNP (Dec 1982 - Apr 1983)

    International Nuclear Information System (INIS)

    The AVF cyclotron at the RCNP (Research Center for Nuclear Physics) of Osaka University has been cooperatively used by various researchers of Japanese universities or colleges. This collective report covers papers concerning various studies performed at the AVF during Dec 1982 to Apr 1983. Some of the titles of these papers are as follows : Elastic scattering of 56 MeV polarized deuterons from 12C and 40Ca ; Pionic three-nucleon capture reactions ; Measurement on branching ratios of short-lived beta emitter 23Mg and its hyperfine interactions ; Half-life and branching ratios of short-lived beta emitter 13O ; 7Li excitation of the giant resonances in 208Pb ; Measurements of spin polarization of residual nuclei after light particle emission in heavy ion reactions ; Target dependence of the sequential alpha decay through the narrow resonances of 20Ne ; Analyzing power of neutron continuum spectra for the 93Nb (p,nx) reaction and a simple one step OWBA analysis ; Energy dependence of the reaction mechanism for the 3He and alpha induced reactions ; Medium energy gamma rays following radiative capture of polarized protons on light nuclei. (Aoki, K.)

  18. A condensation heat transfer model for nearly horizontal tubes of the Passive Auxiliary Feedwater System in APR+

    International Nuclear Information System (INIS)

    A new condensation heat transfer model based on the flow regime in the nearly horizontal tube has been developed for the Passive Auxiliary Feed-water System (PAFS) of Korean Advanced Power Reactor Plus (APR+). This study focused on the stratified flow in horizontal tubes in which two different heat transfer mechanisms are involved. The void fraction was determined from the 1-D separated flow model (SFM) which incorporates closure relations for shear stress defined by single-phase based expressions and geometric relations for a concave interface using the eccentric circles. The wetted angle proposed by Hart's correlation (1989) was used to classify flow regimes into annular, stratified-wavy and stratified-smooth flow. The new film condensation heat transfer correlation based on Nusselt's integral analysis (1916) was proposed to predict the heat transfer coefficient affected by the vapor flow on the upper portion of tube in the stratified flow. Furthermore, the convective heat transfer correlation for single-phase heat transfer was used to predict the heat transfer coefficient for condensate flowing on the entire perimeter of annular flow and the bottom of the stratified flow. Both heat transfer correlations use Reynolds number based on the phasic actual velocities and geometric variables obtained from SFM. Finally, the new condensation heat transfer model package was evaluated against available experimental data for water and it showed good results. (author)

  19. General arrangement design optimization of emergency response facility (TSC, OSC) in Korea next generation reactor (APR-1400)

    International Nuclear Information System (INIS)

    The accident at the Three Mile Island (TMI) led to install some data processing and display equipment to assist control room personnel in rapidly evaluating the safety status. And also to place in the plant for providing operators with technical support and an emergency response center for radiological environmental assessments and determination of recommended public protective action during emergency. In practice, most of the countries possessing nuclear power plants including USA have partially or wholly adopted US NRC regulations and guidelines for Emergency Response Facility(ERF). Also the Korea nuclear power plants are implementing or operating ERF and SPDS after analyzing US NRC regulations and guideline since TMI accident. So this paper first been reviewed Korea Regulations, US NRC published codes and standards related to ERF (TSC/OSC). Finally this paper is described the design optimization of general arrangement in emergency response facility to improve emergency response capability in Korea Next Generation Reactor(APR-1400), which are best suitable for our domestic situation and also enhance the emergency response capability of ERF

  20. Irradiation damage in superconductors

    International Nuclear Information System (INIS)

    Most superconductors are quite sensitive to irradiation defects. Critical temperatures may be depressed, critical currents may be increased, by irradiation, but other behaviours may be encountered. In compounds, the sublattice in which defects are created is of significant importance. 24 refs

  1. Materials modified by irradiation

    International Nuclear Information System (INIS)

    Application of radiation in pharmaceutical sciences and cosmetology, polymer materials, food industry, environment, health camre products and packing production is described. Nanotechnology is described more detailed, because it is less known as irradiation using technology. Economic influence of the irradiation on the materials value addition is shown

  2. Materials modified by irradiation

    International Nuclear Information System (INIS)

    Application of radiation in pharmaceutical sciences and cosmetology, polymer materials, food industry, environment, health camre products and packing production is described. Nano-technology is described more detailed, because it is less known as irradiation using technology. Economic influence of the irradiation on the materials value addition is shown

  3. Food irradiation control

    International Nuclear Information System (INIS)

    A brief review is given of the control and monitoring of food irradiation with particular emphasis on the UK situation. After describing legal aspects, various applications of food irradiation in different countries are listed. Other topics discussed include code of practice for general control for both gamma radiation and electron beam facilities, dose specification, depth dose distribution and dosimetry. (U.K.)

  4. Food Irradiation in Japan

    International Nuclear Information System (INIS)

    Since 1967 research activities on food irradiation in Japan have been carried out under the National Food Irradiation Programme by the Japanese Atomic Energy Commission. The programme has been concentrated on the technological and economical feasibility and wholesomeness testings of seven irradiated food items of economic importance to the country, i.e. potatoes, onions, wheat, rice, “kamaboko” (fish-paste products), “Vienna” sausages and mandarin oranges. By now most studies, including wholesomeness testings of these irradiated food items, have been completed. In Japan, all foods or food additives for sale are regulated by the Food Sanitation Law enforced in 1947. Based on studies made by the national programme, irradiated potatoes were given “unconditional acceptance” for human consumption in 1972. At present, irradiated potatoes are the only food item which has so far been approved by the Minister of Health and Welfare. Unless the Minister of Health and Welfare has declared that items are not harmful to human health on obtaining comments from the Food Sanitation Investigation Council, no irradiated food can be processed or sold. In addition, the import of irradiated foodstuffs other than potatoes from foreign countries is prohibited by law.

  5. Phase stability under irradiation

    International Nuclear Information System (INIS)

    Experimental evidences of radiation induced instability are described then it is shown what theoretical approaches are relevant. Radiation induced segregation and precipitation in alloys irradiated at constant chemical composition, precipitate re-solution, order-disorder transition under irradiation and amorphization are examined

  6. Irradiation Creep in Graphite

    Energy Technology Data Exchange (ETDEWEB)

    Ubic, Rick; Butt, Darryl; Windes, William

    2014-03-13

    An understanding of the underlying mechanisms of irradiation creep in graphite material is required to correctly interpret experimental data, explain micromechanical modeling results, and predict whole-core behavior. This project will focus on experimental microscopic data to demonstrate the mechanism of irradiation creep. High-resolution transmission electron microscopy should be able to image both the dislocations in graphite and the irradiation-induced interstitial clusters that pin those dislocations. The team will first prepare and characterize nanoscale samples of virgin nuclear graphite in a transmission electron microscope. Additional samples will be irradiated to varying degrees at the Advanced Test Reactor (ATR) facility and similarly characterized. Researchers will record microstructures and crystal defects and suggest a mechanism for irradiation creep based on the results. In addition, the purchase of a tensile holder for a transmission electron microscope will allow, for the first time, in situ observation of creep behavior on the microstructure and crystallographic defects.

  7. Issues in food irradiation

    International Nuclear Information System (INIS)

    This discussion paper has two goals: first, to raise public awareness of food irradiation, an emerging technology in which Canada has the potential to build a new industry, mainly oriented to promising overseas markets; and second, to help build consensus among government and private sector decision makers about what has to be done to realize the domestic and export potential. The following pages discuss the potential of food irradiation; indicate how food is irradiated; outline the uses of food irradiation; examine questions of the safety of the equipment and both the safety and nutritional value of irradiated food; look at international commercial developments; assess the current and emerging domestic scene; and finally, draw some conclusions and offer suggestions for action

  8. Irradiation of goods

    International Nuclear Information System (INIS)

    Mechanical handling apparatus is adapted to handle goods, such as boxed fruit, during a process of irradiation, in palletized form. Palletized goods are loaded onto wheeled vehicles in a loading zone. Four vehicles are wheeled on a track into an irradiation zone via a door in a concrete shield. The vehicles are arranged in orthogonal relationship around a source of square section. Turntables are positioned at corners of the square shaped rail truck around the source selectively to turn the vehicles to align then with track sections. Mechanical manipulating devices are positioned in the track sections opposed to sides of the source. During irradiation, the vehicles and their palletized goods are cylically moved toward the source to offer first sides of the goods for irradiation and are retraced from the source and are pivoted through 900 to persent succeeding sides of the goods for irradiation

  9. Discussion on RELAP5 and RETRAN3D Modeling for Passive Condensate Cooling Tank of Passive Auxiliary Feedwater System in APR+

    International Nuclear Information System (INIS)

    Domestic nuclear industry has started the development of APR+ as a Korean specific reactor for the export strategy. In the development of APR+ a passive auxiliary feedwater system (PAFS) has been considered as a noticeable candidate of improved design. The outline of PAFS and passive condensate cooling tank (PCCT) containing horizontal heat exchanger is shown in Fig. 1. For the successful design of PAFS, performance analyses or safety analyses are prerequisite using best estimate thermal hydraulic codes such as RELAP5 or RETRAN3D. Because of the inherent features of RELAP5 or RETRAN3D, pool model and condensation in horizontal tube have not been well-setup nor widely studied. This paper discusses about the PCCT phenomena including steam condensation in horizontal tube and pool heat transfer, and RELAP5 and RETRAN3D modeling

  10. Facteurs influençant le retour au travail après transplantation chez 61 patients rénaux ou hépatiques

    OpenAIRE

    Praz-Christianaz S.-M.

    2014-01-01

    Enjeux La réussite d'une transplantation rénale ou hépatique intègre non seulement le succès de l'acte chirurgical et sa prise en charge médicale post-greffe, mais également pour le patient greffé l'assurance d'une nouvelle qualité de vie dont le retour au travail fait partie. Le retour au travail après greffe est cependant généralement peu étudié dans la littérature et peu discuté semble-t-il au niveau médical que ce soit avant ou après greffe, quand bien même d'un point de vue médico-socio-...

  11. Une première consultation après la crise de décembre 2007Les élections partielles du 11 juin 2008

    OpenAIRE

    Cussac, Anne

    2008-01-01

    Après les élections générales du 27 décembre 2007, les Kenyans, dans certaines circonscriptions électorales ont denouveau été appelés aux urnes le 11 juin 2008, pour élire cinq députés et une cinquantaine de représentantslocaux. Ces élections partielles, qui se déroulées dans les circonscriptions d’Ainamoi, Emuhaya, Embakasi1, Kilgoris etWajir North, ont constitué la toute première consultation après la formation du gouvernement de grande coalition entrele Party of National Unity (PNU) du Pré...

  12. Effects of relative irradiance on the leaf structure of Fagus sylvatica L. seedlings planted in the understory of a Pinus sylvestris L. stand after thinning

    OpenAIRE

    Aranda, Ismael; Bergasa, Luis; Gil, Luis; Pardos, José

    2001-01-01

    Effets, après éclaircie, de l'irradiation relative sur la structure de la feuille de semis de Fagus sylvatica L. plantés sous couvert d'un peuplement de Pinus sylvestris L. Des plants de hêtre ont été mis en place sous le couvert d'une plantation de Pin sylvestre localisée près d'une des populations de hêtre la plus méridionale, la hêtraie chênaie de Montejo de la Sierra. Quatre ans après, l'étage dominant a été partiellement réduit au cours d'une éclaircie des pins. La radiation solaire dans...

  13. Mu dX, a derivative of Mu d1 (lac Apr) which makes stable lacZ fusions at high temperature.

    OpenAIRE

    Baker, T A; Howe, M M; Gross, C A

    1983-01-01

    We describe defective Mu phage Mu dX (Mu d1 Bx::Tn9 [lac Apr Cmr]) which is useful for insertion mutagenesis and for construction of lac operon fusions in vivo. Mu dX retains the insertion properties of Mu d1 but produces temperature-resistant lysogens and transposes at a reduced frequency. A method is described to convert existing Mu d1 insertions to Mu dX.

  14. Onion irradiation - a case study

    International Nuclear Information System (INIS)

    Onion irradiation prevents sprouting associated with long term storage. Under the climatic conditions of Central Europe, only that part of onions should be irradiated which is needed to supply the domestic market during the months of May to July. Two types of irradiation plants, a bulk-irradiation and a multipurpose large-scale irradiation plant are used for onion irradiation. Technical data, throughput, cost-related parameters of onion irradiation are discussed. Onion irradiation for long term storage is beneficial to the national economy as well as to the business management. (author) 13 refs.; 11 tabs

  15. Antiviral activity of the plant extracts from Thuja orientalis, Aster spathulifolius, and Pinus thunbergii against influenza virus A/PR/8/34.

    Science.gov (United States)

    Won, Ji-Na; Lee, Seo-Yong; Song, Dae-sub; Poo, Haryoung

    2013-01-01

    Influenza viruses cause significant morbidity and mortality in humans through epidemics or pandemics. Currently, two classes of anti-influenza virus drugs, M2 ion-channel inhibitors (amantadin and rimantadine) and neuraminidase inhibitors (oseltamivir and zanamivir), have been used for the treatment of the influenza virus infection. Since the resistance to these drugs has been reported, the development of a new antiviral agent is necessary. In this study, we examined the antiviral efficacy of the plant extracts against the influenza A/PR/8/34 infection. In vitro, the antiviral activities of the plant extracts were investigated using the cell-based screening. Three plant extracts, Thuja orientalis, Aster spathulifolius, and Pinus thunbergii, were shown to induce a high cell viability rate after the infection with the influenza A/PR/8/34 virus. The antiviral activity of the plant extracts also increased as a function of the concentration of the extracts and these extracts significantly reduced the visible cytopathic effect caused by virus infections. Furthermore, the treatment with T. orientalis was shown to have a stronger inhibitory effect than that with A. spathulifolius or P. thunbergii. These results may suggest that T. orientalis has anti-influenza A/PR/8/34 activity. PMID:23314378

  16. Irradiation of fusion materials

    International Nuclear Information System (INIS)

    In collaboration with the EFDA (European Fusion Development Agreement), SCK-CEN irradiates several materials in the BR2 reactor at different temperatures and up to different doses to study their mechanical and physical properties during and after the irradiation. These materials are candidates for the construction of different parts of the ITER (International Thermonuclear Experimental Reactor) fusion reactor and of the long-term DEMO (DEMOnstration) reactor. The objectives of research at SCK-CEN in this area are: (1) to irradiate RAFM (Reduced Activity Ferritic Martensitic) steel joints and RAFM ODS (Oxide Dispersion Strengthening) at 300 degrees Celsius up to 2 dpa; (2) to irradiate RAFM steel and different FeCr alloys at 300 degrees C above 1.5 dpa; (3) to irradiate Beryllium and Tungsten specimen at 300 degress C up to 0.75 dpa; (4) to irradiate copper/stainless steel joints at 150 degrees C up to 0.1 dpa; (5) to perform in-situ creep-fatigue tests with CuCrZr specimens under neutron irradiation

  17. Food irradiation 2009

    International Nuclear Information System (INIS)

    Food irradiation principles; its main applications, advantages and limitations; wholesomeness, present activities at Ezeiza Atomic Centre; research coordinated by the International Atomic Energy Agency; capacity building; and some aspects on national and international regulations, standards and commercialization are briefly described. At present 56 countries authorize the consumption of varied irradiated foods; trade is performed in 32 countries, with about 200 irradiation facilities. Argentina pioneered nuclear energy knowledge and applications in Latin America, food irradiation included. A steady growth of food industrial volumes treated in two gamma facilities can be observed. Food industry and producers show interest towards new facilities construction. However, a 15 years standstill in incorporating new approvals in the Argentine Alimentary Code, in spite of consecutive request performed either by CNEA or some food industries restricts, a wider industrial implementation, which constitute a drawback to future regional commercialization in areas such as MERCOSUR, where Brazil since 2000 freely authorize food irradiation. Besides, important chances in international trade with developed countries will be missed, like the high fresh fruits and vegetables requirements United States has in counter-season, leading to convenient sale prices. The Argentine food irradiation facilities have been designed and built in the country. Argentina produces Cobalt-60. These capacities, unusual in the world and particularly in Latin America, should be protected and enhanced. Being the irradiation facilities scarce and concentrated nearby Buenos Aires city, the possibilities of commercial application and even research and development are strongly limited for most of the country regions. (author)

  18. Economics of Food Irradiation

    International Nuclear Information System (INIS)

    This paper reviews and evaluates current developments relating to the prospects for commercial food irradiation within the United States. The study, recognizes that one cannot generalize about the prospects for food irradiation either by process or product. Both technical and economic potentials vary widely for different food products subjected to the same or different types of treatment. Food irradiation processes and products are evaluated. Recent studies concerned with the economics of food irradiation are briefly reviewed and evaluated and findings and conclusions relating to economic potentials summarized. Industry reactions to a proposed pilot plant meat irradiator, sponsored by the U.S. Army and U.S. AEC and coordinated by the Department of Commerce, are discussed and factors which will determine the future direction, extent and commercial success of food preservation by ionizing irradiation are analysed. Developments in all these categories are essential for success, and if not achieved would be limiting factors. Nevertheless, the successful and profitable marketing of irradiated foods must finally be dependent upon customer acceptance and favourable cost versus benefit relations. Benefits will include lower costs and higher profits through spoilage reductions, extensions of shelf-life and shipping distances, market expansions, and quality Improvements. Ultimately, the economic success of this new technology must depend upon the clear demonstration that these benefits will exceed the additional processing costs by a margin sufficient to induce the necessary private investments and willingness to accept related risks in this new field. (author)

  19. Irradiation-Induced Nanostructures

    Energy Technology Data Exchange (ETDEWEB)

    Birtcher, R.C.; Ewing, R.C.; Matzke, Hj.; Meldrum, A.; Newcomer, P.P.; Wang, L.M.; Wang, S.X.; Weber, W.J.

    1999-08-09

    This paper summarizes the results of the studies of the irradiation-induced formation of nanostructures, where the injected interstitials from the source of irradiation are not major components of the nanophase. This phenomena has been observed by in situ transmission electron microscopy (TEM) in a number of intermetallic compounds and ceramics during high-energy electron or ion irradiations when the ions completely penetrate through the specimen. Beginning with single crystals, electron or ion irradiation in a certain temperature range may result in nanostructures composed of amorphous domains and nanocrystals with either the original composition and crystal structure or new nanophases formed by decomposition of the target material. The phenomenon has also been observed in natural materials which have suffered irradiation from the decay of constituent radioactive elements and in nuclear reactor fuels which have been irradiated by fission neutrons and other fission products. The mechanisms involved in the process of this nanophase formation are discussed in terms of the evolution of displacement cascades, radiation-induced defect accumulation, radiation-induced segregation and phase decomposition, as well as the competition between irradiation-induced amorphization and recrystallization.

  20. Development of a Phenomena Identification Ranking Table (PIRT) for a Station Black Out (SBO) Accident of the APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Kyoung Ho; Yun, Byong Jo; Sim, Suk Ku and others

    2013-10-15

    SBO is one of the most important DEC in that without any proper operator actions, a total loss of heat sink leads to core uncover, to core damage, and ultimately a core melt-down scenario under high pressure. Due to this safety importance, SBO is considered to be a base test item of the OECD-ATLAS project. In this study, Phenomena Identification Ranking Table (PIRT) has been developed for identifying the major parameters affecting the thermal-hydraulic phenomena in SBO transients. Development of PIRT for SBO transient is expected to contribute to making strategy for performing a thermal-hydraulic integral effect test with ATLAS which includes determination of proper test conditions and improvement of measurements. The PIRT process used in this study follows the methodology previously applied in the Passive Auxiliary Feedwater System (PAFS) of the APR+ (Advanced Power Reactor Plus). The PIRT has been developed for identifying the major parameters affecting the thermal-hydraulic phenomena during a SBO transient. The PSC was determined to be the core mixture level from the expert panel discussion. As for the major components of the nuclear power plant, the rank of the importance and the knowledge level were summarized for each of the three temporal phases. Taking into account the important phenomena from the PIRT result, it can be confirmed that ATLAS has a capability of simulating the major thermal-hydraulic phenomena during a SBO transient as realistically as possible. The present PIRT is expected to contribute to making strategy for performing a thermal-hydraulic integral effect test with ATLAS in the framework of the OECD-ATLAS project.

  1. Irradiation in action

    International Nuclear Information System (INIS)

    The extent to which food irradiation takes place and the regulations governing the process in America, Brazil, Chile, and European countries is reported. The development and operation of a pilot plant built in Holland to test the application of the process to the sterilization of medical supplies and certain foods and the setting up and operation, by Gammester, of a special food irradiation plant in 1982, is described. In this plant 36 foods, mainly dry ingredients such as spices, dried vegetables, egg powder and blood proteins are irradiated. Research looks promising for the future. The implementation of international legal acceptance and more public information is stressed. (U.K.)

  2. Alaskan Commodities Irradiation Project

    International Nuclear Information System (INIS)

    The ninety-ninth US Congress commissioned a six-state food irradiation research and development program to evaluate the commercial potential of this technology. Hawaii, Washington, Iowa, Oklahoma and Florida as well as Alaska have participated in the national program; various food products including fishery products, red meats, tropical and citrus fruits and vegetables have been studied. The purpose of the Alaskan study was to review and evaluate those factors related to the technical and economic feasibility of an irradiator in Alaska. This options analysis study will serve as a basis for determining the state's further involvement in the development of food irradiation technology. 40 refs., 50 figs., 53 tabs

  3. Facts about food irradiation: Irradiated foods and the consumer

    International Nuclear Information System (INIS)

    This fact sheet discusses market testing of irradiate food, consumer response to irradiated products has always been positive, and in some countries commercial quantities of some irradiated food items have been sold on a regular basis. Consumers have shown no reluctance to buy irradiated food products. 4 refs

  4. Texture et Anisotropie du comportement mécanique après laminage à chaud d'un alliage léger Aluminium Cuivre Lithium (2050) pour l'aéronautique

    OpenAIRE

    Contrepois, Quentin

    2010-01-01

    Ce travail vise à comprendre l’évolution de la texture cristallographique et l’anisotropie du comportement mécanique après laminage à chaud et traitements thermiques d’un Al-Cu-Li 2050 et d’un Al-Zn-Mg-Cu 7050, et expliquer leurs différences. La texture est analysée par EBSD et RX après des essais de compression plane à chaud et après des laminages à chaud industriels. L’anisotropie est étudiée sur des tôles fortes industrielles après différents détensionnements et dans différents états micro...

  5. Contribution to the study of internal friction in graphites; Contribution a l'etude du frottement interieur des graphites

    Energy Technology Data Exchange (ETDEWEB)

    Merlin, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-03-01

    A study has been made of the internal friction in different graphites between -180 C and +500 C using a torsion pendulum; the graphites had been previously treated thermo-mechanically, by neutron irradiation and subjected to partial annealings. It has been shown that there occurs: a hysteretic type dissipation of energy, connected with interactions between dislocations and other defects in the matrix; a dissipation having a partially hysteretic character which can be interpreted by a Granato-Luke type formalism and which is connected with the presence of an 'ultra-micro porosity'; a dissipation by a relaxation mechanism after a small dose of irradiation; this is attributed to the reorientation of bi-interstitials; a dissipation having the characteristics of a solid state transformation, this during an annealing after irradiation. It is attributed to the reorganization of interstitial defects. Some information has thus been obtained concerning graphites, in particular: their behaviour at low mechanical stresses, the nature of irradiation defects and their behaviour during annealing, the structural changes occurring during graphitization, the relationship between internal friction and macroscopic mechanical properties. (author) [French] L'etude du coefficient de frottement interieur au moyen d'un pendule de torsion entre -180 C et +500 C a ete realisee pour differents graphites apres des traitements thermo-mecaniques, des irradiations neutroniques et des guerisons partielles. Il a ete mis en evidence: une dissipation d'energie a caractere hysteretique, reliee aux interactions des dislocations avec les autres defauts de la matrice; une dissipation a caractere partiellement hysteretique, interpretable par un formalisme type Granato-Lucke et reliee a la presence d'une ''ultra-microporosite''; une dissipation par un mecanisme de relaxation, apres irradiation a faible dose, attribuee a la reorientation de di

  6. Packing for food irradiation

    International Nuclear Information System (INIS)

    Joint FAO/IAEA/WHO Expert Committee approved the use of radiation treatment of foods. Nowadays food packaging are mostly made of plastics, natural or synthetic, therefore effect of irradiation on these materials is crucial for packing engineering for food irradiation technology. By selecting the right polymer materials for food packaging it can be ensured that the critical elements of material and product performance are not compromised. When packaging materials are in contact with food at the time of irradiation that regulatory approvals sometimes apply. The review of the R-and-D and technical papers regarding material selection, testing and approval is presented in the report. The most information come from the USA where this subject is well elaborated, the International Atomic Energy Agency (IAEA) reports are reviewed as well. The report can be useful for scientists and food irradiation plants operators. (author)

  7. Food irradiation : ACA inquiry

    International Nuclear Information System (INIS)

    The executive summary of the report on food irradiation by the Australian Consumers' Association is presented. The key issues which emerged during the inquiry are summarised including safety controls, wholesomeness, the environment, consumer rights and economic considerations

  8. Sterilization by gamma irradiation

    International Nuclear Information System (INIS)

    Since 1980 the National Institute of Nuclear Research counts with an Industrial Gamma Irradiator, for the sterilization of raw materials and finished products. Through several means has been promoted the use of this technology as alternative to conventional methods of sterilization as well as steam treatment and ethylene oxide. As a result of the made promotion this irradiator has come to its saturation limit being the sterilization irradiation one of the main services that National Institute of Nuclear Research offers to producer enterprises of disposable materials of medical use also of raw materials for the elaboration of cosmetic products and pharmaceuticals as well as dehydrated foods. It is presented the trend to the sterilization service by irradiation showed by the compilation data in a survey made by potential customers. (Author)

  9. Economics of food irradiation.

    Science.gov (United States)

    Deitch, J

    1982-01-01

    This article examines the cost competitiveness of the food irradiation process. An analysis of the principal factors--the product, physical plant, irradiation source, and financing--that impact on cost is made. Equations are developed and used to calculate the size of the source for planned product throughput, efficiency factors, power requirements, and operating costs of sources, radionuclides, and accelerators. Methods of financing and capital investment are discussed. A series of tables show cost breakdowns of sources, buildings, equipment, and essential support facilities for both a cobalt-60 and a 10-MeV electron accelerator facility. Additional tables present irradiation costs as functions of a number of parameters--power input, source size, dose, and hours of annual operation. The use of the numbers in the tables are explained by examples of calculations of the irradiation costs for disinfestation of grains and radicidation of feed. PMID:6759046

  10. Food irradiation in perspective

    International Nuclear Information System (INIS)

    Food irradiation already has a long history of hopes and disappointments. Nowhere in the world it plays the role that it should have, including in the much needed prevention of foodborne diseases. Irradiated food sold well wherever consumers were given a chance to buy them. Differences between national regulations do not allow the international trade of irradiated foods. While in many countries food irradiation is still illegal, in most others it is regulated as a food additive and based on the knowledge of the sixties. Until 1980, wholesomeness was the big issue. Then the ''prerequisite'' became detection methods. Large amounts of money have been spent to design and validate tests which, in fact, aim at enforcing unjustified restrictions on the use of the process. In spite of all the difficulties, it is believed that the efforts of various UN organizations and a growing legitimate demand for food safety should in the end lead to recognition and acceptance. (Author)

  11. Food irradiation in perspective

    Science.gov (United States)

    Henon, Y. M.

    1995-02-01

    Food irradiation already has a long history of hopes and disappointments. Nowhere in the world it plays the role that it should have, including in the much needed prevention of foodborne diseases. Irradiated food sold well wherever consumers were given a chance to buy them. Differences between national regulations do not allow the international trade of irradiated foods. While in many countries food irradiation is still illegal, in most others it is regulated as a food additive and based on the knowledge of the sixties. Until 1980, wholesomeness was the big issue. Then the "prerequisite" became detection methods. Large amounts of money have been spent to design and validate tests which, in fact, aim at enforcing unjustified restrictions on the use of the process. In spite of all the difficulties, it is believed that the efforts of various UN organizations and a growing legitimate demand for food safety should in the end lead to recognition and acceptance.

  12. Innovations in irradiator design

    International Nuclear Information System (INIS)

    In the past few years industry has demanded certain changes in irradiator design to meet the needs of the medical manufacturers, and as well service the requirements of new applications for irradiation. The medical manufacturers have, in certain cases, been tending toward larger capacity machines with higher efficiencies to take advantage of economies of scale. Other parts of the industry have been demanding a truly ''Multipurpose'' facility which can process many varied types of products. Coupled with these machine changes there has been an increase in demand for more comprehensive logging of the irradiation process. This has spawned development of several styles of computer monitoring, control and logging systems. This paper will discuss these topics in more detail in order to give some insight into the ''state of the art'' within the irradiator design industry. (author)

  13. Dosimetry for food irradiation

    International Nuclear Information System (INIS)

    A Manual of Food Irradiation Dosimetry was published in 1977 under the auspices of the IAEA as Technical Reports Series No. 178. It was the first monograph of its kind and served as a reference in the field of radiation processing and in the development of standards. While the essential information about radiation dosimetry in this publication has not become obsolete, other publications on radiation dosimetry have become available which have provided useful information for incorporation in this updated version. There is already a Codex General Standard for Irradiated Foods and an associated Code of Practice for Operation of Irradiation Facilities used for Treatment of Food, issued in 1984 by the Codex Alimentarius Commission of the FAO/WHO Food Standard Programme. The Codex Standard contains provisions on irradiation facilities and process control which include, among other requirements, that control of the processes within facilities shall include the keeping of adequate records including quantitative dosimetry. Appendix A of the Standard provides an explanation of process control and dosimetric requirements in compliance with the Codex Standard. By 1999, over 40 countries had implemented national regulations or issued specific approval for certain irradiated food items/classes of food based on the principles of the Codex Standard and its Code of Practice. Food irradiation is thus expanding, as over 30 countries are now actually applying this process for the treatment of one or more food products for commercial purposes. Irradiated foods are being marketed at retail level in several countries. With the increasing recognition and application of irradiation as a sanitary and phytosanitary treatment of food based on the provisions of the Agreement on the Application of Sanitary and Phytosanitary Measures of the World Trade Organization, international trade in irradiated food is expected to expand during the next decade. It is therefore essential that proper dosimetry

  14. Irradiation of chilled lamb

    International Nuclear Information System (INIS)

    Chilled, vacuum-packed New Zealand lamb loins have been irradiated at doses between 1-8 kGy. The report outlines the methods used and provides dosimetry details. An appendix summarises the results of a taste trial conducted on the irradiated meat by the Meat Industry Research Institute of New Zealand. This showed that, even at 1 kGy, detectable flavours were induced by the radiation treatment

  15. Food irradiation in Malaysia

    International Nuclear Information System (INIS)

    Food irradiation has recently been visited as a technology that can contribute to the solution of problems associated with food preservation of Malaysia's agriculture produce and products thereby improving the economic status of the rural sector. However, the history of food irradiation in Malaysia is very recent. Research carried out on food irradiation only began in 1974 as a result of the installation of a 60Co facility (initially 10,000 Ci) at the National University of Malaysia. Since its installation several studies have been carried out pertaining to the food irradiation. Presently its development has been slow. Research in this area has been confined to laboratory scale and purely academic. This limitation is due to a number of reasons, among others are: a) limited number of facilities; b) lack of expertise to conduct its research; c) other preservation methods can be improved with lower capital output. An important step towards its development was made when Malaysia actively participated in the RCA/IAEA food irradiation project, viz. the irradiation of pepper which was carried out at the National University of Malaysia in the 80's. As a result of this venture, research and development activities in food irradiation have been geared toward semi-plot scale with the view ot commercialization in the future. In 1982, a group of researchers was formed to conduct feasibility studies using irradiation techniques in trying to overcome several problems associated with our local paddy and rice. Another group is being organized by the National University of Malaysia to look into the problems associated with the preservation of frozen shrimps. (author)

  16. Fully portable blood irradiator

    International Nuclear Information System (INIS)

    A fully portable blood irradiator was developed using the beta emitter thulium-170 as the radiation source and vitreous carbon as the body of the irradiator, matrix for isotope encapsulation, and blood interface material. These units were placed in exteriorized arteriovenous shunts in goats, sheep, and dogs and the effects on circulating lymphocytes and on skin allograft retention times measured. The present work extends these studies by establishing baseline data for skin graft rejection times in untreated animals

  17. Proton irradiation of EMCCDs

    OpenAIRE

    Smith, DR; Ingley, R.; Holland, AD

    2006-01-01

    This paper describes the irradiation of 95 electron multiplication charge coupled devices (EMCCDs) at the Paul Scherrer Institut (PSI) in Switzerland, to investigate the effects of proton irradiation on the operational characteristics of CCDs featuring electron multiplication technology for space use. This work was carried out in support of the CCD development for the radial velocity spectrometer (RVS) instrument of the European Space Agency's cornerstone Gaia mission. Previous proton irradia...

  18. Irradiation Defects in Silicon Crystal

    Institute of Scientific and Technical Information of China (English)

    2003-01-01

    The application of irradiation in silicon crystal is introduced.The defects caused by irradiation are reviewed and some major ways of studying defects in irradiated silicon are summarized.Furthermore the problems in the investigation of irradiated silicon are discussed as well as its properties.

  19. Irradiated produce reaches Midwest market

    International Nuclear Information System (INIS)

    In March 1992, the Chicago-area store gave its shoppers a choice between purchasing irradiated and nonirradiated fruits. The irradiated fruits were treated at Vindicator Inc., the first U.S. food irradiation facility (starting up on January 10, 1992). The plant, located in Mulberry, Fla., then shipped the fruits in trucks to the store where they were displayed under a hand-lettered sign describing the irradiated fruits and showing the irradiation logo

  20. Irradiation of cane sugar spirit

    International Nuclear Information System (INIS)

    The present study deals with the effect of irradiation on the gas-chromatographic profile of irradiated cane sugar spirit irradiated in glass containers in the presence of oak chops with doses of 0-10 kGy. Volatile constituents were analyzed in a CG gas chromatographer with a flame ionization detector using a Megabore CG-745 column. The results are discussed considering the contribution of irradiation to the quality of the spirit and the contribution of the irradiated oak wood. (author)

  1. Consumer response to irradiated foods

    International Nuclear Information System (INIS)

    Apart from the safety and nutritional adequacy of irradiated foods, consumer acceptance would be a major factor in the successful commercialization of irradiation technology. One way to remove the misconceptions about irradiated foods is to serve the food items prepared from irradiated foods to consumers and gauge their response. To evaluate the public perception on irradiated foods, a survey was conducted in various scientific symposia and Bhabha Atomic Research Centre canteens covering a wide spectrum of consumers

  2. Longevity of irradiated burros

    International Nuclear Information System (INIS)

    During the course of external radiation exposures of burros to establish a dose-response curve for acute mortality after total irradiation, some of the animals at the three lowest exposures to gamma photons survived. These groups of 10, 9, and 10 burros were exposed to 320, 425, and 545 R, respectively. There were 10 unirradiated controls. In 1953, 20 burros were exposed to 375 R (gamma) in 25-R/week increments without acute mortality and were added to the life-span study. In 1957, 33 burros were exposed to mixed neutron-gamma radiation from nuclear weapons, and 14 controls were added. The total number of irradiated burros in the study was increased to 88 by the addition of 6 animals irradiated with 180 rads of neutron and gamma radiation (4:1) in a Godiva-type reactor in 1959. In this experiment two acute deaths occurred which were not included in the analysis. In the first 4 years after the single gamma exposures, there were deaths from pancytopenia and thrombocytopenia, obviously related to radiation-induced bone-marrow damage. After that period, however, deaths were from common equine diseases; no death has resulted from a malignant neoplasm. Of the original 112 burros, 15 survive (10 irradiated and 5 controls). Survival curves determined for unirradiated and neutron-gamma- and gamma-irradiated burros showed significant differences. The mean survival times were: controls, 28 years; gamma irradiation only, 26 years; and neutron-gamma irradiation, 23 years. 3 refs., 4 figs., 1 tab

  3. Evaluation of uncertainties of key neutron parameters of PWR-type reactors with slab fuel, application to neutronic conformity; Determination des incertitudes liees aux grandeurs neutroniques d'interet des reacteurs a eau pressurisee a plaques combustibles et application aux etudes de conformite

    Energy Technology Data Exchange (ETDEWEB)

    Bernard, D

    2001-12-01

    The aim of this thesis was to evaluate uncertainties of key neutron parameters of slab reactors. Uncertainties sources have many origins, technologic origin for parameters of fabrication and physical origin for nuclear data. First, each contribution of uncertainties is calculated and finally, a factor of uncertainties is associated to key slab parameter like reactivity, isotherm reactivity coefficient, control rod efficiency, power form factor before irradiation and life-time. This factors of uncertainties were computed by Generalized Perturbations Theory in case of step 0 and by directs calculations in case of irradiation problems. One of neutronic conformity applications was about fabrication and nuclear data targets precision adjustments. Statistic (uncertainties) and deterministic (deviations) approaches were studied. Then, neutronics key slab parameters uncertainties were reduced and so nuclear performances were optimized. (author)

  4. Gamma Irradiation does not Cause Carcinogenesis of Irradiated Herbs

    International Nuclear Information System (INIS)

    Full text: Microbial contamination of medicinal herbs can be effectively reduced by gamma irradiation. Since irradiation may cause carcinogenicity of the irradiated herbs, the objective of this research is to study the effect of gamma irradiation (10 and 25 kGy) from cobalt-60 on carcinogenicity. The herbs studied were Pueraria candollei Grah., Curcuma longa Linn. Zingiber montanum, Senna alexandrina P. Miller, Eurycoma Longifolia Jack, Gymnostema pentaphylum Makino, Ginkgo biloba, Houttuynia cordata T., Andrographis paniculata, Thunbergia laurifolia L., Garcinia atroviridis G., and Cinnamomum verum J.S.Presl. The results showed that gamma irradiation at the dose of 10 and 25 kGy did not cause carcinogenicity of the irradiated herbs

  5. ORNL irradiation creep facility

    International Nuclear Information System (INIS)

    A machine was developed at ORNL to measure the rates of elongation observed under irradiation in stressed materials. The source of radiation is a beam of 60 MeV alpha particles from the Oak Ridge Isochronous Cyclotron (ORIC). This choice allows experiments to be performed which simulate the effects of fast neutrons. A brief review of irradiation creep and experimental constraints associated with each measurement technique is given. Factors are presented which lead to the experimental choices made for the Irradiation Creep Facility (ICF). The ICF consists of a helium-filled chamber which houses a high-precision mechanical testing device. The specimen to be tested must be thermally stabilized with respect to the temperature fluctuations imposed by the particle beam which passes through the specimen. Electrical resistance of the specimen is the temperature control parameter chosen. Very high precision in length measurement and temperature control are required to detect the small elongation rates relevant to irradiation creep in the test periods available (approx. 1 day). The apparatus components and features required for the above are presented in some detail, along with the experimental procedures. The damage processes associated with light ions are discussed and displacement rates are calculated. Recent irradiation creep results are given, demonstrating the suitability of the apparatus for high resolution experiments. Also discussed is the suitability of the ICF for making high precision thermal creep measurements

  6. Post-irradiation diarrhea

    International Nuclear Information System (INIS)

    In radiotherapy of pelvic cancers, the X-ray dose to be delivered to the tumour is limited by the tolerance of healthy surrounding tissue. In recent years, a number of serious complications of irradiation of pelvic organs were encountered. Modern radiotherapy necessitates the acceptance of a calculated risk of complications in order to achieve a better cure rate. To calculate these risks, one has to know the radiation dose-effect relationship of normal tissues. Of the normal tissues most at risk when treating pelvic tumours only the bowel is studied. In the literature regarding post-irradiation bowel complications, severe and mild complications are often mixed. In the present investigation the author concentrated on the group of patients with relatively mild symptoms. He studied the incidence and course of post-irradiation diarrhea in 196 patients treated for carcinoma of the uterine cervix or endometrium. The aims of the present study were: 1) to determine the incidence, course and prognostic significance of post-irradiation diarrhea; 2) to assess the influence of radiotherapy factors; 3) to study the relation of bile acid metabolism to post-irradiation diarrhea; 4) to investigate whether local factors (reservoir function) were primarily responsible. (Auth.)

  7. ORNL irradiation creep facility

    Energy Technology Data Exchange (ETDEWEB)

    Reiley, T.C.; Auble, R.L.; Beckers, R.M.; Bloom, E.E.; Duncan, M.G.; Saltmarsh, M.J.; Shannon, R.H.

    1980-09-01

    A machine was developed at ORNL to measure the rates of elongation observed under irradiation in stressed materials. The source of radiation is a beam of 60 MeV alpha particles from the Oak Ridge Isochronous Cyclotron (ORIC). This choice allows experiments to be performed which simulate the effects of fast neutrons. A brief review of irradiation creep and experimental constraints associated with each measurement technique is given. Factors are presented which lead to the experimental choices made for the Irradiation Creep Facility (ICF). The ICF consists of a helium-filled chamber which houses a high-precision mechanical testing device. The specimen to be tested must be thermally stabilized with respect to the temperature fluctuations imposed by the particle beam which passes through the specimen. Electrical resistance of the specimen is the temperature control parameter chosen. Very high precision in length measurement and temperature control are required to detect the small elongation rates relevant to irradiation creep in the test periods available (approx. 1 day). The apparatus components and features required for the above are presented in some detail, along with the experimental procedures. The damage processes associated with light ions are discussed and displacement rates are calculated. Recent irradiation creep results are given, demonstrating the suitability of the apparatus for high resolution experiments. Also discussed is the suitability of the ICF for making high precision thermal creep measurements.

  8. Irradiation of grains and spices

    International Nuclear Information System (INIS)

    The efficacy of food irradiation to extend the storage life and improve the hygienic quality of rice, mungbean and spices was tested by direct involvement with related food industries. The test consisted of storage trials of irradiated rice under commercial conditions, market testing of irradiated food, and a trial irradiation of commercial products. A consumer acceptance test was conducted using a group of educated people from 3 universities. To prove the safety of food irradiation conducted under appropriately controlled conditions, additional data on vitamin B content and the physico-chemical properties of irradiated rice, as well as free radical activity in irradiated rice, mungbean and spices were collected during this study. The results indicated that rice packaged in polyethylene pouch and irradiated up to 1 kGy could be stored for more than 1 year without insect damage. The colour of irradiated rice was slightly darker than that of unirradiated control, but was still acceptable. The vitamin B content of rice irradiated with such a dose was not significantly changed. Many food companies have recognized the ability of food irradiation, but this technology is not well understood by the general public. An irradiation dose of 3 kGy can be recommended as maximum dose to decontaminate rice of certain bacteria. Free radicals produced in irradiated rice, mungbean and spice will disappear within 1 month following irradiation. (author). 10 refs, 2 figs, 10 tabs

  9. Dosimetry of neutron irradiations

    International Nuclear Information System (INIS)

    Biological dosimetry of neutron irradiation appears to be of great difficulty due to the multiparametric aspect of the relative biological effectiveness and the heterogeneity of the neutron dose distribution. Dosimetry by sodium 24 activation which can be performed by means of portable radiameters appears to be very useful for early triage within the 3 h following neutron irradiation, whereas hematological dosimetry by slope and level analysis of the lymphocyte drop cannot be used in this case. Chromosomic aberration analysis allows to evaluate the neutron dose heterogeneity by the frequency measurement of acentric fragments not originating from the formation of dicentrics or rings. Finally, recent experimental data on large primate models (baboons) have shown that some plasma hemostasia factors appear to be reliable biological indicators and noticeable markers of the prognosis of neutron irradiation

  10. The Birmingham Irradiation Facility

    International Nuclear Information System (INIS)

    At the end of 2012 the proton irradiation facility at the CERN PS will shut down for two years. With this in mind, we have been developing a new ATLAS scanning facility at the University of Birmingham Medical Physics cyclotron. With proton beams of energy approximately 30 MeV, fluences corresponding to those of the upgraded Large Hadron Collider (HL-LHC) can be reached conveniently. The facility can be used to irradiate silicon sensors, optical components and mechanical structures (e.g. carbon fibre sandwiches) for the LHC upgrade programme. Irradiations of silicon sensors can be carried out in a temperature controlled cold box that can be scanned through the beam. The facility is described in detail along with the first tests carried out with mini (1×1 cm2) silicon sensors

  11. Neutron irradiation of seeds

    International Nuclear Information System (INIS)

    Neutrons are a valuable type of ionizing radiation for seed irradiation and radiobiological studies and for inducing mutations in crop plants. In experiments where neutrons are used in research reactors for seed irradiation it is difficult to measure the dose accurately and therefore to establish significant comparisons between experimental results obtained in various reactors and between repeated experiments in the same reactor. A further obstacle lies in the nature and response of the seeds themselves and the variety of ways in which they are exposed in reactors. The International Atomic Energy Agency decided to initiate international efforts to improve and standardize methods of exposing seeds in research reactors and of measuring and reporting the neutron dose. For this purpose, an International Neutron Seed Irradiation Programme has been established. The present report aims to give a brief but comprehensive picture of the work so far done in this programme. Refs, figs and tabs

  12. The Birmingham Irradiation Facility

    CERN Document Server

    Dervan, P; Hodgson, P; Marin-Reyes, H; Wilson, J

    2013-01-01

    At the end of 2012 the proton irradiation facility at the CERN PS [1] will shut down for two years. With this in mind, we have been developing a new ATLAS scanning facility at the University of Birmingham Medical Physics cyclotron. With proton beams of energy approximately 30 MeV, fluences corresponding to those of the upgraded Large Hadron Collider (HL-LHC) can be reached conveniently. The facility can be used to irradiate silicon sensors, optical components and mechanical structures (e.g. carbon fibre sandwiches) for the LHC upgrade programme. Irradiations of silicon sensors can be carried out in a temperature controlled cold box that can be scanned through the beam. The facility is described in detail along with the first tests carried out with mini (1 x 1 cm^2 ) silicon sensors.

  13. Irradiation induced kyphosis

    International Nuclear Information System (INIS)

    Eighty-one patients with Wilms tumor treated by irradiation and chemotherapy were studied. Despite the fact that multiple portals for irradiation were used, each crossing the midline, the amount of irradiation delivered to different parts of the vertebral body varied and it was this variation in delivered dose which produced axial skeletal deformities in 70% of the patients. Of the 57 patients with these deformities, 32 had scoliosis, 22 kyphoscoliosis and 3 patients pure kyphosis; 12 patients had a kyphotic deformity of over 25 degrees, 7 patients requiring surgical correction. A high incidence of pseudarthrosis following posterior fusion has led to the preference of a 2-stage procedure, anterior interbody fusion followed by a posterior fusion with Harrington rods after 2 weeks of correction in halo femoral traction

  14. Irradiation induced kyphosis

    Energy Technology Data Exchange (ETDEWEB)

    Riseborough, E.J.

    1977-10-01

    Eighty-one patients with Wilms tumor treated by irradiation and chemotherapy were studied. Despite the fact that multiple portals for irradiation were used, each crossing the midline, the amount of irradiation delivered to different parts of the vertebral body varied and it was this variation in delivered dose which produced axial skeletal deformities in 70% of the patients. Of the 57 patients with these deformities, 32 had scoliosis, 22 kyphoscoliosis and 3 patients pure kyphosis; 12 patients had a kyphotic deformity of over 25 degrees, 7 patients requiring surgical correction. A high incidence of pseudarthrosis following posterior fusion has led to the preference of a 2-stage procedure, anterior interbody fusion followed by a posterior fusion with Harrington rods after 2 weeks of correction in halo femoral traction.

  15. Food irradiation - general aspects

    International Nuclear Information System (INIS)

    This paper describes research and development experience in food irradiation followed by commercial utilisation of multi-purpose plants. The main design objectives should be high efficiency and uniform dose. Particular care must be given to dosimetry and the use of plastic dosimeters is described. Capital outlay for a 1 MCi Cobalt 60 irradiator is estimated to be 2.5 million dollars giving a unit processing cost of 0.566 dollars/ft3 of throughput for 8000 hour/year use at a dose of 25 kGy. (2.5 Mrad). The sale of irradiated food for human consumption in Britain is not yet permitted but it is expected that enabling legislation will be introduced towards the end of 1985

  16. PRIMA-1Met/APR-246 induces apoptosis and tumor growth delay in small cell lung cancer expressing mutant p53

    DEFF Research Database (Denmark)

    Zandi, Roza; Selivanova, Galina; Christensen, Camilla Laulund;

    2011-01-01

    Small cell lung cancer (SCLC) is a highly malignant disease with poor prognosis, necessitating the need to develop new and efficient treatment modalities. PRIMA-1(Met) (p53-dependent reactivation of massive apoptosis), also known as APR-246, is a small molecule, which restores tumor suppressor...... function to mutant p53 and induces cancer cell death in various cancer types. Since p53 is mutated in more than 90% of SCLC, we investigated the ability of PRIMA-1(Met) to induce apoptosis and inhibit tumor growth in SCLC with different p53 mutations....

  17. Food irradiation and the chemist

    International Nuclear Information System (INIS)

    Food Irradiation and the Chemist reviews the chemical challenges facing the food industry regarding food irradiation, especially in the key area of detection methodology. The book looks at the most promising techniques currently available for the detection of irradiated foods and discusses their suitability to different food groups. It also covers the latest work on the effect of irradiation on polymer additives, potential taint from irradiated food contact plastics, the effects of irradiation on micro-organisms and their biochemistry, and much more... (author)

  18. Effects of irradiation

    International Nuclear Information System (INIS)

    The midday depression of CO2 assimilation in leaves of two cultivars of hazelnut. Effect of UV-B radiation on decay kinetics of long-term delayed luminiscence of green algae Scenedesmus quadricuda. Effects of irradiance on biomass allocation and needle photosynthetic capacity in silver fir seedlings originating from different localities. Chlorophyll fluorescence of UV-B irradiated bean leaves subjected to chilling in light. Preliminary studies on susceptibility of selected varieties of oats to high UV-B radiation dose. Influence of light conditions on oxidative stress in maize callus

  19. Irradiation of dehydrated vegetables

    International Nuclear Information System (INIS)

    The reason for radurization was to decreased the microbial count of dehydrated vegetables. The average absorbed irradiation dose range between 2kGy and 15kGy. The product catagories include a) Green vegetables b) White vegetables c) Powders of a) and b). The microbiological aspects were: Declining curves for the different products of T.P.C., Coliforms, E. Coli, Stap. areus, Yeast + Mold at different doses. The organoleptical aspects were: change in taste, flavour, texture, colour and moisture. The aim is the marketing of irradiated dehydrated vegetables national and international basis

  20. Irradiated cocoa beans

    International Nuclear Information System (INIS)

    Groups of 40 male and 40 female CD rats were fed powdered rodent diet containing 25% (w/w) of either non-irradiated, irradiated or fumigated cocoa beans. The diets were supplemented with certain essential dietary constituents designed to satisfy normal nutritional requirements. An additional 40 male and 40 female rats received basal rodent diet alone (ground) and acted as an untreated control. After 70 days of treatment, 15 male and 15 female rats from each group were used to assess reproductive function of the F0 animals and growth and development of the F1 offspring up to weaning; the remaining animals were killed after 91 days of treatment. (orig.)

  1. Materials response to irradiation

    International Nuclear Information System (INIS)

    Radiation-induced changes in the mechanical properties of metals, e.g. due to the embrittlement necessitate irradiation experiments with HTR-specific neutron spectra. These experiments help to determine materials behaviour and establish basic data for design and safety testing, especially with a view to the high fluence and temperature loads on absorber cans. The experiments are carried out up to maximum operational fluence (>= 1022nsub(th)/cm2). Results so far have shown the importance of the materials structure for assurance of sufficient residual ductility after irradiation. Secondary experiments, e.g. on He implantation and radiation response of the absorber material B4C, are mentioned. (orig.)

  2. Food irradiation processing

    International Nuclear Information System (INIS)

    An international symposium on food irradiation processing dealing with issues which affect the commercial introduction of the food irradiation process was held in Vienna in 1985. The symposium, which attracted close to 300 participants, was planned to interest not only scientists and food technologists, but also representatives of government agencies, the food industry, trade associations and consumer organizations. The symposium included a discussion of the technological and economic feasibility of applying ionizing energy for the preservation of food, and focused on the specific needs of developing countries. Separate abstracts were prepared for the various presentations at this meeting

  3. Serum magnesium and irradiation

    International Nuclear Information System (INIS)

    Serum magnesium determinations were obtained on 10 dogs and 11 patients undergoing fractionated irradiation to the pelvis and lower abdomen. Five of the dogs received oral prednisone during irradiation. There was no significant change in magnesium concentration in either the control dogs or the patients, but there was a significant increase in stool frequency in both the dogs and patients. A significant increase in magnesium concentration was noted in the dogs receiving prednisone. It is concluded that radiation-induced diarrhea is not caused by reduced serum magnesium concentration

  4. Canadian Irradiation Centre

    International Nuclear Information System (INIS)

    The Canadian Irradiation Centre is a non-profit cooperative project between Atomic Energy of Canada Limited, Radiochemical Company and Universite du Quebec, Institut Armand-Frappier, Centre for Applied Research in Food Science. The Centre's objectives are to develop, demonstrate and promote Canada's radiation processing technology and its applications by conducting applied research; training technical, professional and scientific personnel; educating industry and government; demonstrating operational and scientific procedures; developing processing procedures and standards, and performing product and market acceptance trials. This pamphlet outlines the history of radoation technology and the services offered by the Canadian Irradiation Centre

  5. Facts about food irradiation: Nutritional quality of irradiated foods

    International Nuclear Information System (INIS)

    This fact sheet briefly considers the nutritional value of irradiated foods. Micronutrients, especially vitamins, are sensitive to any food processing method, but irradiation does not cause any special nutritional problems in food. 4 refs

  6. Consumer opinions in Argentina on food irradiation: irradiated onions

    International Nuclear Information System (INIS)

    Two surveys were carried out in Buenos Aires of consumer attitudes towards irradiated onions [no data given]. The first investigated the general level of consumer knowledge concerning food irradiation, whilst the second (which covered consumers who had actually bought irradiated onions) examined reasons for purchase and consumer satisfaction. Results reveal that more than 90% of consumers surveyed had a very limited knowledge of food irradiation

  7. Economics of gamma irradiation processing

    International Nuclear Information System (INIS)

    The gamma-ray irradiation business started at the Takasaki Laboratory of Japan Atomic Energy Research Institute. The irradiation facilities were constructed thereafter at various sites. The facilities must accept various types of irradiation, and must be constructed as multi-purpose facilities. The cost of irradiation consists of the cost of gamma sources, construction expense, personnel expense, management expense, and bank interest. Most of the expenses are considered to be fixed expense, and the amount of irradiation treatment decides the original costs of work. The relation between the irradiation dose and the construction expense shows the larger facility is more economical. The increase of amount of treatment reduces the original cost. The utilization efficiency becomes important when the amount of treatment and the source intensity exceed some values. The principal subjects of gamma-ray irradiation business are the sterilization of medical tools and foods for aseptic animals, the improvement of quality of plastic goods, and the irradiation of foods. Among them, the most important subject is the sterilization of medical tools. The cost of gamma irradiation per m3 in still more expensive than that by ethylene oxide gas sterilization. However, the demand of gamma-ray irradiation is increasing. For the improvement of quality of plastic goods, electron irradiation is more favourable than the gamma irradiation. In near future, the economical balance of gamma irradiation can be achieved. (Kato, T.)

  8. Food irradiation and consumer values

    International Nuclear Information System (INIS)

    A mail survey technique was used to determine if value hierarchy, locus of control, innovativeness, and demographic parameters could distinguish between subjects expressing different levels of concern and willingness to buy irradiated food. Concern toward irradiated food was lower than concern for other food safety issues, probably because many expressed uncertainty regarding irradiation. Those ranking the value “an ecologically balanced world” expressed the greatest irradiation concern. Factors which could predict high irradiation concern were being highly concerned about the use of chemical sprays on food, completing more formal education and being female; those believing that life was controlled by luck were less concerned. Irradiation concern was a principal factor determining willingness to buy irradiated foods. Innovative consumers were more likely to try irradiated foods than noninnovative. Implications for consumer education are presented

  9. Regulatory aspect of food irradiation

    International Nuclear Information System (INIS)

    Interest in the process of food irradiation is reviewed once again internationally. Although food irradiation has been thoroughly investigated, global acceptance is still lacking. Factors which impede the progress of the technology are discussed here. (author)

  10. Phytosanitary Applications of Irradiation

    International Nuclear Information System (INIS)

    Phytosanitary treatments are used to disinfest agricultural commodities of quarantine pests so that the commodities can be shipped out of quarantined areas. Ionizing irradiation is a promising phytosanitary treatment that is increasing in use worldwide. Almost 19 000 metric tons of sweet potatoes and several fruits plus a small amount of curry leaf are irradiated each year in 6 countries, including the United States, to control a number of plant quarantine pests. Advantages over other treatments include tolerance by most fresh commodities, ability to treat in the final packaging and in pallet loads, and absence of pesticide residues. Disadvantages include lack of acceptance by the organic food industries and logistical bottlenecks resulting from current limited availability of the technology. A regulatory disadvantage is lack of an independent verification of treatment efficacy because pests may be found alive during commodity inspection, although they will not complete development or reproduce. For phytosanitary treatments besides irradiation, the pests die shortly after the treatment is concluded. This disadvantage does not hamper its use by industry, but rather makes the treatment more difficult to develop and regulate. Challenges to increase the use of phytosanitary irradiation (PI) are cost, because commercial use has not yet reached an optimum economy of scale, lack of facilities, because of their cost and current inability to feasibly locate them in packing facilities, lack of approved treatments for some quarantine pests, and concern about the process by key decision makers, such as packers, shippers, and retailers. Methods for overcoming these challenges are discussed. (author)

  11. Irradiation of spices

    International Nuclear Information System (INIS)

    The problem faced by spice producing countries and by the food industry using these spices as ingredients are facing the problem of their high contamination with pathogenic and non pathogenic microorganisms, which create public health and product-deterioration problems. After discussing the conventional methods of decontamination, which result either in organoleptic losses (heat and extracts) or in toxic residues (fumigants), the advantages of the irradiation treatment are presented. This procedure is direct, simple to administer and control, and highly efficient. Doses of 3-7 kGy have been proven to reduce the microbial load to satisfactory levels, without affecting the organoleptic characteristics, whereas the surviving microflora is more sensitive to the subsequent food processing treatments. Irradiation can be administered in the commercial packages, which leads to considerable energy and personnel savings, while preventing subsequent recontamination. The increasing demand for high microbial quality in spices makes it easier for the food industry to afford the irradiation treatment costs. The wholesomeness of irradiated spices has been demonstrated by a group of experts of WHO, FAO and IAEA, and the treatment has been promulgated by Codex Alimentarius and been cleared by a number of national health authorities, including the U.S. F.D.A. The number of clearances is steadily increasing and so is the commercial use

  12. Solar Irradiance Variability

    CERN Document Server

    Solanki, Sami K

    2012-01-01

    The Sun has long been considered a constant star, to the extent that its total irradiance was termed the solar constant. It required radiometers in space to detect the small variations in solar irradiance on timescales of the solar rotation and the solar cycle. A part of the difficulty is that there are no other constant natural daytime sources to which the Sun's brightness can be compared. The discovery of solar irradiance variability rekindled a long-running discussion on how strongly the Sun affects our climate. A non-negligible influence is suggested by correlation studies between solar variability and climate indicators. The mechanism for solar irradiance variations that fits the observations best is that magnetic features at the solar surface, i.e. sunspots, faculae and the magnetic network, are responsible for almost all variations (although on short timescales convection and p-mode oscillations also contribute). In spite of significant progress important questions are still open. Thus there is a debat...

  13. Irradiation effects on zircaloy

    International Nuclear Information System (INIS)

    In a water cooled reactor, the neutron effect on zirconium base alloys which are used in the core, is a twofold one: - indirect effect, by means of modifications to the alloy environment; - direct effect occurence of irradiation defects in the material. The indirect effect results in an increase of the water corrosion, as a consequence of the water radiolysis and in stress-corrosion, due to fission products such as iodine, cesium, cadmium... The paper will describe the consequence of these phenomena and the means used to remedy their harmfull effects. The occurence of irradiation defects has three consequence: - Material strenghening: the yield and ultimate stresses are increased by 45 and 35% respectively for the cold worked and stress-relieved zircaloy while the uniform elongation, rather low before irradiation, practically does not decrease (fluence 5.1021 n/cm2). Yield and ultimate stresses of annealed zircaloy are increased by about 150% while uniform elongation decreases from 8 to 1% in the same conditions. - Material growing it is a change in dimensions in the absence of any applied stress. It depends on the cristallography texture, metallurgical state of the material and irradiation temperature. - Material creeping: in the normal working conditions of a reactor, it is the main source of deformation. It depends on temperature, stress, neutron flux and metallurgical state of the material

  14. Wholesomeness of irradiated food

    Energy Technology Data Exchange (ETDEWEB)

    Raica, Nicholas; McDowell, Marion E.; Darby, William J.

    1963-01-15

    The wholesomeness of irradiated foods was evaluated in mice, rats, dogs, and monkeys over a 2-year period, or 4 generations. Data are presented on the effects of a diet containing radiation-processed foods on growth, reproduction, hematology, histopathology, carcinogenicity, and life span. (86 references) (C.H.)

  15. Photochromism in irradiated diamond

    International Nuclear Information System (INIS)

    Photochromism exhibited at low temperatures in the absorption line at 1.521 eV in electron-irradiated type IIb diamond is described and understood in terms of a simple model. Energy and temperature dependences of the photoconversion process are discussed briefly. (author)

  16. Profitability of irradiation plants

    International Nuclear Information System (INIS)

    In any industrial process it is seek an attractive profit from the contractor and the social points of view. The use of the irradiation technology in foods allows keep their hygienically, which aid to food supply without risks for health, an increment of new markets and a losses reduction. In other products -cosmetics or disposable for medical use- which are sterilized by irradiation, this process allows their secure use by the consumers. The investment cost of an irradiation plant depends mainly of the plant size and the radioactive material reload that principally is Cobalt 60, these two parameters are in function of the type of products for irradiation and the selected doses. In this work it is presented the economic calculus and the financial costs for different products and capacities of plants. In general terms is determined an adequate utility that indicates that this process is profitable. According to the economic and commercial conditions in the country were considered two types of credits for the financing of this projects. One utilizing International credit resources and other with national sources. (Author)

  17. Update on meat irradiation

    International Nuclear Information System (INIS)

    The irradiation of meat and poultry in the United States is intended to eliminate pathogenic bacteria from raw product, preferably after packaging to prevent recontamination. Irradiation will also increase the shelf life of raw meat and poultry products approximately two to three times the normal shelf life. Current clearances in the United States are for poultry (fresh or frozen) at doses from 1.5 to 3.0 kGy and for fresh pork at doses from 0.3 to 1.0 kGy. A petition for the clearance of all red meat was submitted to the Food and Drug Administration (FDA) in July 1994. The petition is for clearances of fresh meat at doses from 1.5 to 4.5 kGy and for frozen meat at ∼2.5 to 7.5 kGy. Clearance for red meat is expected before the end of 1997. There are 28 countries that have food irradiation clearances, of which 18 countries have clearances for meat or poultry. However, there are no uniform categories or approved doses for meat and poultry among the countries that could hamper international trade of irradiated meat and poultry

  18. Radiation irradiation test method

    International Nuclear Information System (INIS)

    The present invention provides a method of irradiating radiation (rays) to a test piece by using an actual powder of nuclear fuel material. Namely, the test piece is sealed in an inner and outer double-walled bag of a radiation-permeable polymer film to form an irradiation specimen. The irradiation specimen is placed at a predetermined position of a glove box for a predetermined period of time, and necessary irradiation is performed. The outer bag is cut out, and the test piece in the inner bag not deposited with radioactive material is obtained. This is transported out of the glove box by using a bag-out method. The test piece sealed in the inner bag can be taken out by cutting out the inner bag in an operation hood capable of preventing scattering of radioactive materials. The bag-out method mentioned herein is a method of taking out radioactive materials or materials contaminated by the radioactive materials in the glove box after sealing them in a vinyl chloride bag by welding. (I.S.)

  19. Pituitary irradiation program

    International Nuclear Information System (INIS)

    The alpha particle pituitary irradiation program continues to be a major research project at Donner Pavilion. A study to determine the incidence of hyperprolactinemia in a large series of acromegalic subjects was undertaken. The relationships between plasma levels of growth hormone and prolactin, sellar volume, duration of acromegaly, and age at time of evaluation were investigated

  20. Irradiated uranium reprocessing

    International Nuclear Information System (INIS)

    Task concerned with reprocessing of irradiated uranium covered the following activities: implementing the method and constructing the cell for uranium dissolving; implementing the procedure for extraction of uranium, plutonium and fission products from radioactive uranium solutions; studying the possibilities for using inorganic ion exchangers and adsorbers for separation of U, Pu and fission products

  1. NSUF Irradiated Materials Library

    Energy Technology Data Exchange (ETDEWEB)

    Cole, James Irvin [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    The Nuclear Science User Facilities has been in the process of establishing an innovative Irradiated Materials Library concept for maximizing the value of previous and on-going materials and nuclear fuels irradiation test campaigns, including utilization of real-world components retrieved from current and decommissioned reactors. When the ATR national scientific user facility was established in 2007 one of the goals of the program was to establish a library of irradiated samples for users to access and conduct research through competitively reviewed proposal process. As part of the initial effort, staff at the user facility identified legacy materials from previous programs that are still being stored in laboratories and hot-cell facilities at the INL. In addition other materials of interest were identified that are being stored outside the INL that the current owners have volunteered to enter into the library. Finally, over the course of the last several years, the ATR NSUF has irradiated more than 3500 specimens as part of NSUF competitively awarded research projects. The Logistics of managing this large inventory of highly radioactive poses unique challenges. This document will describe materials in the library, outline the policy for accessing these materials and put forth a strategy for making new additions to the library as well as establishing guidelines for minimum pedigree needed to be included in the library to limit the amount of material stored indefinitely without identified value.

  2. Physical properties of beryllium oxide - Irradiation effects; Proprietes physiques et caracteristiques mecaniques de l'oxyde de beryllium fritte - Effet de l'irradiation et guerison

    Energy Technology Data Exchange (ETDEWEB)

    Elston, J.; Caillat, R. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    This work has been carried out in view of determining several physical properties of hot-pressed beryllium oxide under various conditions and the change of these properties after irradiation. Special attention has been paid on to the measurement of the thermal conductivity coefficient and thermal diffusivity coefficient. Several designs for the measurement of the thermal conductivity coefficient have been achieved. They permit its determination between 50 and 300 deg. C, between 400 and 800 deg. C. Some measurements have been made above 1000 deg. C. In order to measure the thermal diffusivity coefficient, we heat a perfectly flat surface of a sample in such a way that the heat flux is modulated (amplitude and frequency being adjustable). The thermal diffusivity coefficient is deduced from the variations of temperature observed on several spots. Tensile strength; compressive strength; expansion coefficient; sound velocity and crystal parameters have been also measured. Some of the measurements have been carried out after neutron irradiation. Some data have been obtained on the change of the properties of beryllium oxide depending on the integrated neutron flux. (author)Fren. [French] L'objet de cette etude est la determination de plusieurs proprietes physiques de l'oxyde de beryllium fritte sous charge dans differentes conditions et l'evolution de ces proprietes apres irradiation. Une attention particuliere a ete portee sur la mesure de la conductibilite et de la diffusivite thermiques. Differents montages ont ete realises pour mesurer la conductibilite thermique. Ils permettent la determination entre 50 et 300 deg. C, entre 400 et 800 deg. C; quelques mesures ont ete faites au-dessus de 1000 deg. C. Pour la mesure du coefficient de diffusivite thermique, on realise une attaque thermique, de frequence et d'amplitude reglables d'une face parfaitement plane d'un echantillon d'oxyde de beryllium. Les variations de temperature sont

  3. Process for irradiation of polyethylene

    International Nuclear Information System (INIS)

    Irradiation of polyethylene affects its processabiltiy in the fabrication of products and affects the properties of products already fabricated. The present invention relates to a process for the irradiation of polyethylene, and especially to a process for the irradiation of homopolymers of ethylene and copolymers of ethylene and higher α-olefins, in the form of granules, with low levels of electron or gamma irradiation in the presence of an atomsphere of steam

  4. Peut-on réaliser une analgésie péridurale après un blood patch récent?

    Science.gov (United States)

    Chkoura, Khalid; Kechna, Hicham; Loutid, Jaouad; Ouzad, Omar; Hachimi, Moulay Ahmed; Hannafi, Sidi Mohamed

    2015-01-01

    Le blood patch constitue le traitement de référence du syndrome post ponction lombaire. Son efficacité a été démontrée par plusieurs essais randomisés comparant le BPE aux mesures conservatrices et au placebo. Il consiste en l'injection d'une quantité de sang autologue dans l'espace péridurale afin d'obturer la brèche dure-mérienne. La réalisation d'une analgésie péridurale après antécédent de blood patch est possible, malgré la persistance de questions sur les délais de retour à la normal de l'espace péridurale. Nous rapportons un cas où une analgésie péridurale a été réalisée avec succès trois semaines après un blood patch. PMID:26600909

  5. Economics of Food Irradiation

    International Nuclear Information System (INIS)

    To-day very reliable irradiation equipment is available, and for an industrialist it is largely an economic consideration whether he should go in for an otherwise acceptable irradiation processing. In Denmark an industrial concern has now found it economically justifiable to establish a multi-purpose industrial plant, equipped with an American linac, and this facility will be able to process food.l To date, few plants in the world have recorded actual cost experiences for industrial food processing, but cost figures from other fields may serve as a guide. In practical calculations it is convenient to divide the work into certain typical groups, e.g. facilities for ''bulk'', ''medium'', ''thin'', and ''multi-purpose'', but food products may come under any of these headings. Costs of irradiation depend on product properties, type of plant, annual and monthly quantities, doses, control standards, special requirements for re-packing or other additional handling, etc. Definite figures for a particular case must be based on an exact calculation, but for a preliminary judgement many general price-range indications are available to the industrialist, and for a variety of purposes it is already evident that irradiation processing is economically sound. Apart from plant economy it is advisable for the industrialist to study some general commercial problems also, such as consumer preference and marketing structure, for the commodity in question. This can often best be done by marketing a pilot production of some quantity, before final decisions are taken regarding major investments in highly-specialized equipment. For some products market testing has already been done with good results by existing research or production facilities, and indeed actual commercial marketing has been reported. In conclusion, many food irradiation processes seem to be promising from an economic point of view. (author)

  6. Food irradiation technology

    International Nuclear Information System (INIS)

    Trade in food and agricultural products is important to all countries, the economies of many developing countries would be significantly improved if they were able to export more food and agricultural products. Unfortunately, many products can not be traded because they are infested with, or hosts to, harmful pests, contaminated with microorganisms, or spoil quickly. Foods contaminated with microorganisms cause economic losses, widespread illness and death. Several technologies and products have been developed to resolve problems in trading food and to improve food safety, but none can provide all the solutions. Irradiation is an effective technology to resolve technical problems in trade of many food and agricultural products, either as a stand- alone technology or in combination with others. As a disinfestation treatment it allows different levels of quarantine security to be targeted and it is one of few methods to control internal pests. The ability of irradiation virtually to eliminate key pathogenic organisms from meat, poultry, and spices is an important public health advantage. In addition to controlling pests and eliminating harmful bacteria, irradiation also extends the storage life of many foods. In the laboratories of Turkish Atomic Energy Authority, many research projects were completed on the effects of gamma irradiation to the storage life of chicken meat, anchovy, Turkish fermented sausage, dried and fresh fruits and vegetables and also research projects were conducted on the effects of gamma irradiation on microorganisms (Salmonella, Campylo-bacteria, E.coli and S.aureus in white and red meat) and parasites (food-borne, trichostrongylus spp. and Nematodes spp.)

  7. Onion irradiation - a case study

    International Nuclear Information System (INIS)

    The irradiation of onions (Allium cepa L.) serves to prevent sprouting associated with long-term storage or transport and storage of onions in climatic conditions which stimulate sprouting. JECFI the Joint Expert Committee for Food Irradiation of FAO/IAEA/WHO, recommended the application of an irradiation dose of up to 150 Gy for sprout inhibition with onions. (author)

  8. Market trials of irradiated chicken

    International Nuclear Information System (INIS)

    The potential market for irradiated chicken breasts was investigated using a mail survey and a retail trial. Results from the mail survey suggested a significantly higher level of acceptability of irradiated chicken than did the retail trial. A subsequent market experiment involving actual purchases showed levels of acceptability similar to that of the mail survey when similar information about food irradiation was provided

  9. Study and development of a method allowing the identification of actinides inside nuclear waste packages, by active neutron or photon interrogation and delayed gamma-ray spectrometry; Etude et developpement d'une technique de dosage des actinides dans les colis de dechets radioactifs par interrogation photonique ou neutronique active et spectrometrie des gamma retardes

    Energy Technology Data Exchange (ETDEWEB)

    Carrel, F

    2007-10-15

    An accurate estimation of the alpha-activity of a nuclear waste package is necessary to select the best mode of storage. The main purpose of this work is to develop a non-destructive active method, based on the fission process and allowing the identification of actinides ({sup 235}U, {sup 238}U, {sup 239}Pu). These three elements are the main alpha emitters contained inside a package. Our technique is based on the detection of delayed gammas emitted by fission products. These latter are created by irradiation with the help of a neutron or photon beam. Performances of this method have been investigated after an Active Photon or Neutron Interrogation (INA or IPA). Three main objectives were fixed in the framework of this thesis. First, we measured many yields of photofission products to compensate the lack of data in the literature. Then, we studied experimental performances of this method to identify a given actinide ({sup 239}Pu in fission, {sup 235}U in photofission) present in an irradiated mixture. Finally, we assessed the application of this technique on different mock-up packages for both types of interrogation (118 l mock-up package containing EVA in fission, 220 l mock-up package with a wall of concrete in photofission). (author)

  10. Post-irradiation effects in polyethylenes irradiated under various atmospheres

    International Nuclear Information System (INIS)

    If a large amount of polymer free radicals remain trapped after irradiation of polymers, the post-irradiation effects may result in a significant alteration of physical properties during long-term shelf storage and use. In the case of polyethylenes (PEs) some failures are attributed to the post-irradiation oxidative degradation initiated by the reaction of residual free radicals (mainly trapped in crystal phase) with oxygen. Oxidation products such as carbonyl groups act as deep traps and introduce changes in carrier mobility and significant deterioration in the PEs electrical insulating properties. The post-irradiation behaviour of three different PEs, low density polyethylene (LDPE), linear low density polyethylene (LLDPE) and high density polyethylene (HDPE) was studied; previously, the post-irradiation behaviour of the PEs was investigated after the irradiation in air (Suljovrujic, 2010). In this paper, in order to investigate the influence of different irradiation media on the post-irradiation behaviour, the samples were irradiated in air and nitrogen gas, to an absorbed dose of 300 kGy. The annealing treatment of irradiated PEs, which can substantially reduce the concentration of free radicals, is used in this study, too. Dielectric relaxation behaviour is related to the difference in the initial structure of PEs (such as branching, crystallinity etc.), to the changes induced by irradiation in different media and to the post-irradiation changes induced by storage of the samples in air. Electron spin resonance (ESR), differential scanning calorimetry (DSC), infra-red (IR) spectroscopy and gel measurements were used to determine the changes in the free radical concentration, crystal fraction, oxidation and degree of network formation, respectively. - Highlights: • The post-irradiation behaviour of three different PEs, LDPE, LLDPE and HDPE, was studied. • In order to investigate influence of different irradiation media on post-irradiation behaviour, samples

  11. Storage of pork by irradiation

    International Nuclear Information System (INIS)

    In this paper the study of storage of pork, irradiated with Co-60 gamma rays, is recommended. The changes of the appearance and the main qualitative indexes of pork, irradiated with 1.5 M rad radiation and after two month's storage, were analysed. The evaluation of storage, transportation and nutritional acceptability of the two kinds of irradiated pork products was made. Systematic toxicological tests of rats and dogs, fed with irradiated pork, were given. The comparison of the economic facilitation of refrigerated pork and irradiated pork was made. (author)

  12. Safety aspects of irradiated foods

    International Nuclear Information System (INIS)

    The toxicological and microbiological safety of irradiated foods has been established after extensive research over a period of 30 years. No radioactivity can be induced in foods with the radioisotopes used to irradiate produce. The lethal effects of gamma irradiation on spoilage and pathogenic bacteria as well as insects and parasites, ensure a product of superior quality with regard to maintaining quality and hygiene. Feeding studies of unprecedented scope in the history of food research also proved the toxicological safety of irradiated foods. These findings are supported by recent short-term studies on toxicity and mutagenicity. The production and marketing of irradiated foods are therefore warranted and have indeed started worldwide

  13. Industrial application of food irradiation

    International Nuclear Information System (INIS)

    In the past three years the author has been irradiating foodstuffs with the Gammaster facility which was originally designed for the sterilization of medical equipment. A great diversity of products have been irradiated. In spite of some limitations of the facility, the process has proved to be very satisfactory. The technology for medical sterilization is directly applicable. At present, besides the sterilization of medical equipment, an average of twenty tonnes of foodstuffs, mainly spices, grains, herbs and fish products, are being irradiated every week. The Pilot Plant for Food Irradiation handles a similar quantity. The construction of the JS 7200, the JS 8500, and the JS 9000 irradiator is discussed. (Auth.)

  14. Commercial food irradiation in practice

    International Nuclear Information System (INIS)

    Dutch research showed great interest in the potential of food irradiation at an early stage. The positive research results and the potential applications for industry encouraged the Ministry of Agriculture and Fisheries to construct a Pilot Plant for Food Irradiation. In 1967 the Pilot Plant for Food Irradiation in Wageningen came into operation. The objectives of the plant were: research into applications of irradiation technology in the food industry and agricultural industry; testing irradiated products and test marketing; information transfer to the public. (author)

  15. Market Trials of Irradiated Spices

    International Nuclear Information System (INIS)

    Full text: The objectives of the experiment were to disseminate irradiated retail foods to the domestic publics and to test consumer acceptance on irradiated ground chilli and ground pepper. Market trials of irradiated ground chilli and ground pepper were carried out at 2 local markets and 4 in Bangkok and Nontaburi in 2005-2007. Before the start of the experiment, processing room, gamma irradiation room and labels of the products were approved by Food and Drug Administration, Thailand. 50 grams of irradiated products were packaged in plastic bags for the market trials. 688 and 738 bags of ground chilli and ground pepper were sold, respectively. Questionnaires distributed with the products were commented by 59 consumers and statistically analyzed by experimental data pass program. 88.1 and 91.4 percents of the consumers were satisfied with the quality and the price, respectively. 79.7% of the consumers chose to buy irradiated ground chilli and ground pepper because they believed that the quality of irradiated products were better than that of non-irradiated ones. 91.5% of the consumers would certainly buy irradiated chilli and pepper again. Through these market trials, it was found that all of the products were sold out and the majority of the consumers who returned the questionnaires was satisfied with the irradiated ground chilli and ground pepper and also had good attitude toward irradiated foods

  16. Biological Effects of Irradiated Fats

    International Nuclear Information System (INIS)

    Rats were fed with a diet containing 20% of irradiated oils. If the oils were irradiated with 2.5 Mrad, there was no indication of detrimental effects during the course of 80 weeks. Oils irradiated with 10 Mrad, however, caused an increase in lethality after a lag period of 9 to 12 months. Irradiation with 50 Mrad caused weight losses after 24 weeks, disturbed liver function, and hypoproteinaemia, with a relative increase in gamma globulins. No animal of this group exceeded a life-span of 75 weeks. Irradiation with 100 Mrad caused immediate toxic symptoms and a high lethality. There is no indication that peroxides are responsible for the toxicity of the irradiated oils. Because of the high content of dimeric products in the irradiated oils, it is assumed that dimerization of fatty acids is the cause of damage. (author)

  17. Vitamin A in irradiated foodstuffs

    International Nuclear Information System (INIS)

    Vitamin A losses induced by 10 MeV electrons in cream cheese, calf liver sausage, pig liver, whole egg powder and magarine continued to increase during storage for 4-8 weeks in presence of air. Thus, vitamin A loss in sausage irradiated with 5 Mrad was 22% on the day after irradiation, 61% after 4 weeks. Irradiation and storage at 00C instead of ambient temperature reduced these losses considerably. Exclusion of air (vacuum, nitrogen) or irradiation on dry ice (approx. -800C) were even more effective in preventing destruction of vitamin A. After 4 weeks of storage, cream cheese irradiated at 5 Mrad had lost 60% when irradiated and stored in air at ambient temperature, 20% in nitrogen atmosphere, 5% in vacuum package, and 5% when irradiated on dry ice and stored at ambient temperature. (orig.)

  18. Vitamin A in irradiated foodstuffs

    International Nuclear Information System (INIS)

    Vitamin A losses induced by 10 MeV electrons in cream cheese, calf liver sausage, pig liver, whole egg powder and margarine continued to increase during storage for 4-8 weeks in presence of air. Thus, vitamin A loss in sausage irradiated with 5 Mrad was 22% on the day after irradiation, 61% after 4 weeks. Irradiation and storage at 00C instead of at ambient temperature reduced these losses considerably. Exclusion of air (vacuum, nitrogen) or irradiation on dry ice (approx. -800C) were even more effective in preventing destruction of vitamin A. After 4 weeks of storage, cream cheese irradiated at 5 Mrad had lost 60% when irradiated and stored in air at ambient temperature, 20% in nitrogen atmosphere, 5% in vacuum package, and 5% when irradiated on dry ice and stored at ambient temperture. (orig.)

  19. Irradiated brown dwarfs

    CERN Document Server

    Casewell, S L; Lawrie, K A; Maxted, P F L; Dobbie, P D; Napiwotzki, R

    2014-01-01

    We have observed the post common envelope binary WD0137-349 in the near infrared $J$, $H$ and $K$ bands and have determined that the photometry varies on the system period (116 min). The amplitude of the variability increases with increasing wavelength, indicating that the brown dwarf in the system is likely being irradiated by its 16500 K white dwarf companion. The effect of the (primarily) UV irradiation on the brown dwarf atmosphere is unknown, but it is possible that stratospheric hazes are formed. It is also possible that the brown dwarf (an L-T transition object) itself is variable due to patchy cloud cover. Both these scenarios are discussed, and suggestions for further study are made.

  20. Thermoluminescence of irradiated foods

    International Nuclear Information System (INIS)

    This report describes developments and applications of the thermoluminescence (TL) analysis of mineral contaminants in foods. Procedures are presented to obtain minerals from most different products such as pepper, mangos, shrimps and mussels. The effect of light exposure during the storage of foods on the TL intensity of minerals is examined and corresponding conclusions for routine control are drawn. It is also shown that the normalization of TL intensities - the essential step to identify irradiated samples - can not only be achieved by γ, X or β rays but also by UV radiation. The results allow the conclusion that a clear identification of any food which has been irradiated with more than 1 kGy is possible if enough minerals can be isolated. (orig.)

  1. Identification of irradiated seafood

    International Nuclear Information System (INIS)

    Interest in the use of ionising radiation for the treatment and preservation of food is increasing throughout the world. Foods are treated with ionising radiation to decrease microbial and insect infestations, inhibit maturation and extend shelf-life. Ionising radiation can be used in place of, or in conjunction with, chemical treatment and other processes currently used to preserve foods. The treatment of food by ionising radiation is accepted for specific purposes in several countries, although in other countries the sale of irradiated food for human consumption is prohibited. It would be advantageous if a method was available to determine whether a commercial food has been treated with ionising radiation and is within regulatory limitations for permissible food types and maximum allowable absorbed dose. Because of differences in the composition of the food commodities that potentially could be treated by irradiation, several analytical procedures will probably have to be developed. (author)

  2. Safety of irradiated foods

    Energy Technology Data Exchange (ETDEWEB)

    Iwahara, Shigeo (Foods Medicines Safety Center (Japan)); Kobayashi, Kazuo

    1983-01-01

    The safety of 7 irradiated foods (potato, onion, rice, wheat, vienna sausage, fish paste and mandarine orange), in terms of 2-year long-term toxic effect, reproductive physiology and possible teratogenesis, was studied using 3 generations of rats, mice and monkeys. The genetic toxicity was studied by means of various mutagenicity tests. The details of the studies conducted by the authors to date and some overseas data were reported. The available data showed no toxic effect.

  3. Safety of irradiated foods

    International Nuclear Information System (INIS)

    The safety of 7 irradiated foods (potato, onion, rice, wheat, vienna sausage, fish paste and mandarine orange), in terms of 2-year long-term toxic effect, reproductive physiology and possible teratogenesis, was studied using 3 generations of rats, mice and monkeys. The genetic toxicity was studied by means of various mutagenicity tests. The details of the studies conducted by the authors to date and some overseas data were reported. The available data showed no toxic effect. (Chiba, N.)

  4. Analysis of irradiated materials

    International Nuclear Information System (INIS)

    Papers presented at the UKAEA Conference on Materials Analysis by Physical Techniques (1987) covered a wide range of techniques as applied to the analysis of irradiated materials. These varied from reactor component materials, materials associated with the Authority's radwaste disposal programme, fission products and products associated with the decommissioning of nuclear reactors. An invited paper giving a very comprehensive review of Laser Ablation Microprobe Mass Spectroscopy (LAMMS) was included in the programme. (author)

  5. Food Irradiation. Standing legislation

    International Nuclear Information System (INIS)

    The standing legislation in Mexico on food irradiation matter has its basis on the Constitutional Policy of the Mexican United States on the 4 Th. article by its refers to Secretary of Health, 27 Th. article to the Secretary of Energy and 123 Th. of the Secretary of Work and Social Security. The laws and regulations emanated of the proper Constitution establishing the general features which gives the normative frame to this activity. The general regulations of Radiological Safety expedited by the National Commission for Nuclear Safety and Safeguards to state the specifications which must be fulfill the industrial installations which utilizing ionizing radiations, between this line is founded, just as the requirements for the responsible of the radiological protection and the operation of these establishments. The project of Regulation of the General Health Law in matter of Sanitary Control of Benefits and Services, that in short time will be officialized, include a specific chapter on food irradiation which considers the International Organizations Recommendations and the pertaining harmonization stated for Latin America, which elaboration was in charge of specialized group where Mexico was participant. Additionally, the Secretary of Health has a Mexican Official Standard NOM-033-SSA1-1993 named 'Food irradiation; permissible doses in foods, raw materials and support additives' standing from the year 1995, where is established the associated requirements to the control registers, service constancies and dose limits for different groups of foods, moreover of the specific guidelines for its process. This standard will be adequate considering the updating Regulation of Benefits and Services and the limits established the Regulation for Latin America. The associated laws that cover in general terms it would be the requirements for food irradiation although such term is not manageable. (Author)

  6. Phytosanitary applications of irradiation

    International Nuclear Information System (INIS)

    Phytosanitary treatments are used to disinfest agricultural commodities of quarantine pests so that the commodities can be shipped out of quarantined areas. Ionizing irradiation is a promising phytosanitary treatment that is in- creasing in use worldwide. Almost 19000 metric tons of sweet potatoes and several fruits plus a small amount of curry leaf are irradiated each year in 6 countries, including the United States, to control a number of plant quarantine pests. Advantages over other treatments include tolerance by most fresh commodities, ability to treat in the final packaging and in pallet loads, and absence of pesticide residues. A regulatory disadvantage is lack of an independent verification of treatment efficacy because pests may be found alive during commodity inspection, although they will not complete development or reproduce. High-energy X-rays generated by electron beam are ideal for sterilizing large packages and pallet loads of food. The directional concentration and high penetration capability as well as excellent dose uniformity of X-rays allows disinfest efficiently. Application of irradiation phytosanitary in China still in its infancy. (authors)

  7. Genomic instability following irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Hacker-Klom, U.B.; Goehde, W. [Inst. fuer Strahlenbiologie, Muenster Univ. (Germany)

    2001-07-01

    Ionising irradiation may induce genomic instability. The broad spectrum of stress reactions in eukaryontic cells to irradiation complicates the discovery of cellular targets and pathways inducing genomic instability. Irradiation may initiate genomic instability by deletion of genes controlling stability, by induction of genes stimulating instability and/or by activating endogeneous cellular viruses. Alternatively or additionally it is discussed that the initiation of genomic instability may be a consequence of radiation or other agents independently of DNA damage implying non nuclear targets, e.g. signal cascades. As a further mechanism possibly involved our own results may suggest radiation-induced changes in chromatin structure. Once initiated the process of genomic instability probably is perpetuated by endogeneous processes necessary for proliferation. Genomic instability may be a cause or a consequence of the neoplastic phenotype. As a conclusion from the data available up to now a new interpretation of low level radiation effects for radiation protection and in radiotherapy appears useful. The detection of the molecular mechanisms of genomic instability will be important in this context and may contribute to a better understanding of phenomenons occurring at low doses <10 cSv which are not well understood up to now. (orig.)

  8. Genomic instability following irradiation

    International Nuclear Information System (INIS)

    Ionising irradiation may induce genomic instability. The broad spectrum of stress reactions in eukaryontic cells to irradiation complicates the discovery of cellular targets and pathways inducing genomic instability. Irradiation may initiate genomic instability by deletion of genes controlling stability, by induction of genes stimulating instability and/or by activating endogeneous cellular viruses. Alternatively or additionally it is discussed that the initiation of genomic instability may be a consequence of radiation or other agents independently of DNA damage implying non nuclear targets, e.g. signal cascades. As a further mechanism possibly involved our own results may suggest radiation-induced changes in chromatin structure. Once initiated the process of genomic instability probably is perpetuated by endogeneous processes necessary for proliferation. Genomic instability may be a cause or a consequence of the neoplastic phenotype. As a conclusion from the data available up to now a new interpretation of low level radiation effects for radiation protection and in radiotherapy appears useful. The detection of the molecular mechanisms of genomic instability will be important in this context and may contribute to a better understanding of phenomenons occurring at low doses <10 cSv which are not well understood up to now. (orig.)

  9. Control of food irradiation facilities and good irradiation practices

    International Nuclear Information System (INIS)

    Expansion of irradiation facilities employing commercial scale processes is evident in several countries. The list compiled by the Food Preservation Section of the Joint FAO/IAEA Division, Vienna (April 1988) showed that 34 counties have approved the use of irradiation process for more than 40 food commodities. In Asia and the Pacific Region, the main commercial application of irradiation process is still the sterilization of medical devices but applications to food processing are on the rise. To ensure the safety of irradiated foods, laws and regulations have to be promulgated to govern the facilities, the operations and the products. In most cases, there may be more than one governmental agency involved in regulatory control. The control activities include licensing/registration of a food irradiation premises as a food processing plant, registration of irradiated food in accordance with prescribed standards and regulating labelling practice as well as regularly conducting a comprehensive inspection of the facilities. The quality control programme must cover all aspects of treatment, handling, and distribution. It is emphasized that, as with all food technologies, effective quality control systems needs to be installed and adequately monitored at critical control points at the irradiation facility. Foods should be handled, stored, and transported according to GMP before, during, and after irradiation. Only foods meeting microbiological criteria and other quality standards should be accepted for irradiation. Besides, good irradiation practice (GIP) is also a fundamental principle of practice required specifically for food irradiation. With this recognition, the International Consultative Group on Food Irradiation (ICGFI) has elaborated a set of eight codes of GIP. The quality control system would also include proper packaging suitable for the product. Additional use of a logo to identify irradiated food should be permitted and may even become recognized as a symbol

  10. Cinétique de la troponine Ic et valeurs seuils pour le diagnostic d'infarctus du myocarde après chirurgie cardiaque sous circulation extracorporelle

    Science.gov (United States)

    Kallel, Samy; Jarraya, Anwar; Ellouze, Maged; Frikha, Imed; Karoui, Abbdelhamid

    2012-01-01

    Introduction L'objectif de ce travail était d’étudier la cinétique de la Troponine Ic (TnIc) après chirurgie cardiaque sous circulation extracorporelle (CEC) et établir des valeurs seuils de TnIc pour le diagnostic d'infarctus du myocarde (IDM) post opératoire. Il s'agissait d'une étude prospective type cohorte observationnelle. Méthodes Nous avons inclus 37 patients âgés de plus de 18 ans proposés pour chirurgie valvulaire ou pontage aorto coronarien sous CEC. Nous avons suivi la cinétique de TnIc par des dosages immunoenzymatique sur mini-vidas® avant et après la CEC, à H4 et H12 postopératoire puis tous les jours les 4 premiers jours. Le cutoff pour le diagnostic d'IDM post opératoire a été défini comme la valeur moyenne de troponine + deux déviations standards des patients indemnes de complications cardiaques. Résultats Les valeurs de TnIc en préopératoire étaient toutes inférieures au seuil de détection de la méthode de dosage (<0,01µg/l). Les valeurs de TnIc augmentent en postopératoire immédiat pour atteindre un maximum à H4 puis diminuent progressivement pour se normaliser après 4 à 5 jours. Les valeurs seuils ont été déterminées pour H0, H4,H12, H24, H48, H72, H96 et ont été respectivement 1.36, 2.58, 3.1, 3.23, 2.13, 1.53, 1.17 pour la chirurgie coronaire et 3.75, 5.39, 4.22, 3.41, 1.65, 1.3 1.19 pour la chirurgie valvulaire. Conclusion La connaissance de la cinétique de TnIc lors de chirurgie cardiaque non compliquée et la fixation de valeur seuil ou Cutoff permet aux cliniciens de distinguer entre dommage myocardique secondaire à la chirurgie et IDM. PMID:23396754

  11. Estimation of irradiation temperature within the irradiation program Rheinsberg

    CERN Document Server

    Stephan, I; Prokert, F; Scholz, A

    2003-01-01

    The temperature monitoring within the irradiation programme Rheinsberg II was performed by diamond powder monitors. The method bases on the effect of temperature on the irradiation-induced increase of the diamond lattice constant. The method is described by a Russian code. In order to determine the irradiation temperature, the lattice constant is measured by means of a X-ray diffractometer after irradiation and subsequent isochronic annealing. The kink of the linearized temperature-lattice constant curves provides a value for the irradiation temperature. It has to be corrected according to the local neutron flux. The results of the lattice constant measurements show strong scatter. Furthermore there is a systematic error. The results of temperature monitoring by diamond powder are not satisfying. The most probable value lays within 255 C and 265 C and is near the value estimated from the thermal condition of the irradiation experiments.

  12. Estimation of irradiation temperature within the irradiation program Rheinsberg

    International Nuclear Information System (INIS)

    The temperature monitoring within the irradiation programme Rheinsberg II was performed by diamond powder monitors. The method bases on the effect of temperature on the irradiation-induced increase of the diamond lattice constant. The method is described by a Russian code. In order to determine the irradiation temperature, the lattice constant is measured by means of a X-ray diffractometer after irradiation and subsequent isochronic annealing. The kink of the linearized temperature-lattice constant curves provides a value for the irradiation temperature. It has to be corrected according to the local neutron flux. The results of the lattice constant measurements show strong scatter. Furthermore there is a systematic error. The results of temperature monitoring by diamond powder are not satisfying. The most probable value lays within 255 C and 265 C and is near the value estimated from the thermal condition of the irradiation experiments. (orig.)

  13. Food irradiation - the retailer's view

    International Nuclear Information System (INIS)

    During October-November 1978 consignments of irradiated and non-irradiated strawberries were offered for sale in three branches of OK Bazaars. Samples were also subjected to simulated store conditions and the shelf life of both irradiated and non-irradiated packs determined. Irradiated packs were unaffected by decay until the 15th day of storage while the non-irradiated packs started to show signs of decay on the 7th day and were totally contaminated with fungus by the 14th day. In general, the response from the public was one of extreme interest and was to a large extent reflected in the encouraging sales. In March 1979, storage trials were carried out on green and ripe Keitt mangoes. The results of the trials show a marked increase in the shelf life of irradiated mangoes. The problems which exist with regard to the quality of fresh mangoes, namely anthracnose, soft brown rot and mango weevil, were all effectively controlled by irradiation. It must be realised that irradiation is no panacea and is not a substitute for other methods of food preservation. Any future marketing trials must be carried out using exclusively irradiated fruit. The customer must have the opportunity of 'seeing' the better fruit and not comparing it with other fruit which may be so near over-ripening on display that the price may have been reduced. The trials are to be continued on a much larger scale

  14. The wholesomeness of irradiated food

    International Nuclear Information System (INIS)

    It is apparent that there is a need for protection of the consumer and a need for governmental authorities to insure a safe and wholesome food supply for the population. Based on objective and scientific evidence regarding the safety of food irradiation, national and international health authorities are able to determine whether irradiated food is acceptable for human consumption. Following a thorough review of all available data, the Joint FAO/IAEA/WHO Expert Committee unconditionally approved wheat and ground wheat products and papaya irradiated for disingestation at a maximum dose of 100 krad, potatoes irradiated for sprout control at a maximum dose not exceeding 15 krad, and chicken irradiated at a maximum dose of 700 krad to reduce microbiological spoilage. Lastly, it unconditionally approved strawberries irradiated at a maximum dose of 300 krad to prolong storage. Onions at irradiated for sprout control at a maximum dose of 15 krad were temporarily approved, subject to preparation of further data on multigeneration reproduction studies on rats. Codfish and redfish eviscerated after irradiation at a maximum dose of 220 krad to reduce microbiological spoilage were also approved, based on the results of various studies in progress. Temporary, conditional approval of rice irradiated for insect disinfestation at a maximum dose of 100 krad was based on results of long-term studies on rats and monkies, available in the next review. Due to insufficient data, no decision regarding irradiated mushrooms was made. (Bell, E.)

  15. Consumer acceptance of irradiated foods

    International Nuclear Information System (INIS)

    Although the first experiments on food irradiation were carried out in 1916 in Sweden, food irradiation, is for consumers, a relatively new technology. From the sixties food irradiation has been applied more and more, so that the consumer movement has become alert to this technology. Since then a lot of controversies have arisen in the literature about wholesomeness, safety, effects, etc. Food irradiation is currently permitted on a small scale in about 30 countries; in some countries or states food irradiation has been put under a ban (e.g. Australia, New Zealand, New Jersey). The World Health Organization (WHO) and the Food and Agriculture Organization of the United Nations (FAO) have, however, chosen food irradiation as a safe and sound method for preserving and improving the safety of food. Reactions on the part of the consumer organizations of many countries are however not in favour of or are even opposed to food irradiation. In this chapter consumer acceptance related to technological developments is described, then the convergence of the consumer movement on public opinion and concern on food irradiation is discussed. The need for labelling of irradiated food products is discussed and finally recommendations are given of ways to change consumers attitudes to food irradiation. (author)

  16. Gemstone dedicated gamma irradiation development

    International Nuclear Information System (INIS)

    The gemstones gamma irradiation process to enhance the color is widely accepted for the jewelry industry. These gems are processed in conventional industrial gamma irradiation plant which are optimized for other purposes, using underwater irradiation devices with high rejection rate due to its poor dose uniformity. A new conception design, which states the working principles and manufacturing ways of the device, was developed in this work. The suggested device's design is based on the rotation of cylindrical baskets and their translation in circular paths inside and outside a cylindrical source rack as a planetary system. The device is meant to perform the irradiation in the bottom of the source storage pool, where the sources remain always shielded by the water layer. The irradiator matches the Category III IAEA classification. To verify the physical viability of the basic principle, tests with rotating cylindrical baskets were performed in the Multipurpose Irradiator constructed in the CTR, IPEN. Also, simulations using the CADGAMMA software, adapted to simulate underwater irradiations, were performed. With the definitive optimized irradiator, the irradiation quality will be enhanced with better dose control and the production costs will be significantly lower than market prices due to the intended treatment device's optimization. This work presents some optimization parameters and the expected performance of the irradiator. (author)

  17. Gemstone dedicated gamma irradiation development

    Energy Technology Data Exchange (ETDEWEB)

    Omi, Nelson M.; Rela, Paulo R. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)]. E-mails: nminoru@ipen.br; prela@ipen.br

    2007-07-01

    The gemstones gamma irradiation process to enhance the color is widely accepted for the jewelry industry. These gems are processed in conventional industrial gamma irradiation plant which are optimized for other purposes, using underwater irradiation devices with high rejection rate due to its poor dose uniformity. A new conception design, which states the working principles and manufacturing ways of the device, was developed in this work. The suggested device's design is based on the rotation of cylindrical baskets and their translation in circular paths inside and outside a cylindrical source rack as a planetary system. The device is meant to perform the irradiation in the bottom of the source storage pool, where the sources remain always shielded by the water layer. The irradiator matches the Category III IAEA classification. To verify the physical viability of the basic principle, tests with rotating cylindrical baskets were performed in the Multipurpose Irradiator constructed in the CTR, IPEN. Also, simulations using the CADGAMMA software, adapted to simulate underwater irradiations, were performed. With the definitive optimized irradiator, the irradiation quality will be enhanced with better dose control and the production costs will be significantly lower than market prices due to the intended treatment device's optimization. This work presents some optimization parameters and the expected performance of the irradiator. (author)

  18. Food Irradiation Development in Japan

    International Nuclear Information System (INIS)

    In Japan, the first food irradiation research was carried out on the preservation of fish and fishery products. In 1966, the Atomic Energy Commission of the Japanese Government (JAEC) decided to promote the National Project on Food Irradiation and, in 1967, the Steering Committee on food irradiation research in the Atomic Energy Bureau, Science and Technology-Agency, selected the following food items as of economic importance to the country, i.e., potatoes, onions, rice, wheat, ''Vienna'' sausage, ''kamaboko'' (fish meat jelly products) and mandarin oranges. The National Project is expected, to finish at the end of the 1981 fiscal year. Based on the studies by the National Project, irradiated potatoes were given ''unconditional acceptance'' for human consumption in 1972. Already in 1973, a commercial potato irradiator was built at Shihoro, Hokkaido. In 1980, the Steering Committee submitted a final report on the effectiveness and wholesomeness studies on irradiated onions to the JAEC. This paper gives a brief explanation of the legal aspects of food irradiation in Japan, and the present status of wholesomeness studies on the seven items of irradiated foods. In addition, topics concerning food irradiation research on ''kamaboko'', especially on the effectiveness and a new detecting method for the irradiation treatment of these products, are outlined. (author)

  19. Food irradiation development in Japan

    International Nuclear Information System (INIS)

    In Japan, the first food irradiation research was carried out on the preservation of fish and fishery products. In 1966, the Atomic Energy Commission of the Japanese Government (JAEC) decided to promote the National Project on Food Irradiation and, in 1967, the Steering Committee on food irradiation research in the Atomic Energy Bureau, Science and Technology Agency, selected the following food items as of economic importance to the country, i.e., potatoes, onions, rice, wheat, ''Vienna'' sausage, ''kamaboko'' (fish meat jelly products) and mandarin oranges. The National Project is expected to finish at the end of the 1981 fiscal year. Based on the studies by the National Project, irradiated potatoes were given ''unconditional acceptance'' for human consumption in 1972. Already in 1973, a commercial potato irradiator was built at Shihoro, Hokkaido. In 1980, the Steering Committee submitted a final report on the effectiveness and wholesomeness studies on irradiated onions to the JAEC. This paper gives a brief explanation of the legal aspects of food irradiation in Japan, and the present status of wholesomeness studies on the seven items of irradiated foods. In addition, topics concerning food irradiation research on ''kamaboko'', especially on the effectiveness and a new detecting method for the irradiation treatment of these products, are outlined. (author)

  20. Facts about food irradiation: Microbiological safety of irradiated food

    International Nuclear Information System (INIS)

    This fact sheet considers the microbiological safety of irradiated food, with especial reference to Clostridium botulinum. Irradiated food, as food treated by any ''sub-sterilizing'' process, must be handled, packaged and stored following good manufacturing practices to prevent growth and toxin production of C. botulinum. Food irradiation does not lead to increased microbiological hazards, nor can it be used to save already spoiled foods. 4 refs

  1. Truman, "faith-based" diplomatie et ambigüités du Plan Marshall : cas de la France de l'après-guerre

    OpenAIRE

    Autran, Jean-Marie

    2015-01-01

    La "Faith-based" diplomatie américaine et les ambiguïtés du plan Marshall : le cas de la France dans l’après-guerre. Le Président Harry S. Truman (1945-1953) affirme dès 1946 que les E.U. doivent s’armer d'une « diplomatie fondée sur la foi » pour encourager la reconstruction spirituelle d'une Europe « déchristianisée » face au communisme. Pour faire barrage au marxisme de l’Union Soviétique, il fallait commencer par la France, vue comme la pierre de voûte spirituelle. Plus que toute autre na...

  2. Cinétique de la troponine Ic et valeurs seuils pour le diagnostic d'infarctus du myocarde après chirurgie cardiaque sous circulation extracorporelle

    OpenAIRE

    Kallel, Samy; Jarraya, Anwar; Ellouze, Maged; Frikha, Imed; Karoui, Abbdelhamid

    2012-01-01

    Introduction L'objectif de ce travail était d’étudier la cinétique de la Troponine Ic (TnIc) après chirurgie cardiaque sous circulation extracorporelle (CEC) et établir des valeurs seuils de TnIc pour le diagnostic d'infarctus du myocarde (IDM) post opératoire. Il s'agissait d'une étude prospective type cohorte observationnelle. Méthodes Nous avons inclus 37 patients âgés de plus de 18 ans proposés pour chirurgie valvulaire ou pontage aorto coronarien sous CEC. Nous avons suivi la cinétique d...

  3. Development of a Prototypical Condensation Model for the Nearly Horizontal Heat Exchanger Tube of the APR+ PAFS(Passive Auxiliary Feed-water System)

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Tae Hwan; Yun, Byong Jo; Jeong, Jae Jun [Pusan National Univ., Busan (Korea, Republic of)

    2013-10-15

    In this study, a new condensation heat transfer model was developed for the separated flow regime in the nearly horizontal tube. A new heat transfer model which takes into account of different heat transfer mechanisms occurred in the upper and lower regions of perimeters was developed in the nearly horizontal tube. The present model shows good prediction capability against experimental data. Passive Auxiliary Feed-water System(PAFS) which is adopted in the Korean advanced nuclear power plant, APR+, removes decay heat by condensing steam from the secondary side in the nearly horizontal tubes under the accident condition. The comparison of prediction against PASCAL(2011) experimental data obtained by KAERI indicated that the best estimated safety analysis code such as MARS tends to underestimate the condensation heat transfer coefficient.

  4. Development of a Prototypical Condensation Model for the Nearly Horizontal Heat Exchanger Tube of the APR+ PAFS(Passive Auxiliary Feed-water System)

    International Nuclear Information System (INIS)

    In this study, a new condensation heat transfer model was developed for the separated flow regime in the nearly horizontal tube. A new heat transfer model which takes into account of different heat transfer mechanisms occurred in the upper and lower regions of perimeters was developed in the nearly horizontal tube. The present model shows good prediction capability against experimental data. Passive Auxiliary Feed-water System(PAFS) which is adopted in the Korean advanced nuclear power plant, APR+, removes decay heat by condensing steam from the secondary side in the nearly horizontal tubes under the accident condition. The comparison of prediction against PASCAL(2011) experimental data obtained by KAERI indicated that the best estimated safety analysis code such as MARS tends to underestimate the condensation heat transfer coefficient

  5. La présence des Nabatéens en Italie (ier siècle av.-iie siècle apr. J.-C.)

    OpenAIRE

    Schwentzel, Christian-Georges

    2015-01-01

    La présence des Nabatéens en Italie est attestée par plusieurs documents épigraphiques ainsi que par quelques monuments découverts à Pouzzoles : des autels et des objets de culte, des sculptures. Cette présence s’est sans doute développée à la fin du iie s. av. J.-C., ou au début du ier siècle av. J.-C., avant de s’effacer, probablement au iie siècle apr. J.-C. En tout cas, les documents épigraphiques mentionnant la présence de Nabatéens en Italie sont datés des règnes de Malichos Ier (58-30 ...

  6. The LasB Elastase of Pseudomonas aeruginosa Acts in Concert with Alkaline Protease AprA To Prevent Flagellin-Mediated Immune Recognition.

    Science.gov (United States)

    Casilag, Fiordiligie; Lorenz, Anne; Krueger, Jonas; Klawonn, Frank; Weiss, Siegfried; Häussler, Susanne

    2016-01-01

    The opportunistic pathogen Pseudomonas aeruginosa is capable of establishing severe and persistent infections in various eukaryotic hosts. It encodes a wide array of virulence factors and employs several strategies to evade immune detection. In the present study, we screened the Harvard Medical School transposon mutant library of P. aeruginosa PA14 for bacterial factors that modulate interleukin-8 responses in A549 human airway epithelial cells. We found that in addition to the previously identified alkaline protease AprA, the elastase LasB is capable of degrading exogenous flagellin under calcium-replete conditions and prevents flagellin-mediated immune recognition. Our results indicate that the production of two proteases with anti-flagellin activity provides a failsafe mechanism for P. aeruginosa to ensure the maintenance of protease-dependent immune-modulating functions. PMID:26502908

  7. Modele de simulation de la duree d'humectation des feuilles au champ apres une pluie. Cas d'un couvert homogene

    OpenAIRE

    Huber, L.

    1988-01-01

    La présence d’eau libre à la surface des organes végétaux pendant un temps minimal est un facteur essentiel lors de la contamination de la plante-hôte par un champignon. Afin de prévoir l’occurrence de ce phénomène en terme de durée, un modèle multi-couches de transfert de masse et d’énergie est adapté au cas de la simulation de la durée d’humectation des feuilles après une pluie au sein d’un couvert végétal homogène. Le but est de spatialiser ce paramètre intéressant les phytopathologis...

  8. Facteurs prédictifs d'une intolérance au glucose après un diabète gestationnel

    OpenAIRE

    Guillermin-Spahr, Marie-Luce

    2004-01-01

    Les critères permettant de prédire la persistance d'une IG après un diabète gestationnel sont insuffisants. Nous avons analysé les caractéristiques ante- et post partum (PP) de 239 femmes avec diabète gestationnel. Les résultats de l'hyperglycémie provoquée (HGPO) 6 semaines post partum étaient: 51% normal; 15% IG; 11% diabète vrai; et 23% IG non diagnostique. Des 42 femmes diagnostiquées précocement (< 24ème semaine), 23% avaient un test normal, et 40% avaient un diabète persistant. Les fact...

  9. Facteurs prédictifs d'une intolérance au glucose après un diabète gestationnel

    OpenAIRE

    Guillermin-Spahr, Marie-Luce; Golay, Alain

    2005-01-01

    Les critères permettant de prédire la persistance d'une IG après un diabète gestationnel sont insuffisants. Nous avons analysé les caractéristiques ante- et post partum (PP) de 239 femmes avec diabète gestationnel. Les résultats de l'hyperglycémie provoquée (HGPO) 6 semaines post partum étaient: 51% normal; 15% IG; 11% diabète vrai; et 23% IG non diagnostique. Des 42 femmes diagnostiquées précocement (< 24ème semaine), 23% avaient un test normal, et 40% avaient un diabète persistant. Les fact...

  10. General description of irradiation and post irradiation examination in JMTR

    International Nuclear Information System (INIS)

    The JMTR (Japan Materials Testing Reactor) was designed to provide suitable facilities for conducting nuclear irradiation experiments necessary for the research and development of power reactor in Japan. The JMTR consists of a 50 MW high flux reactor, irradiation facilities and a multi-cell hot laboratory. The available irradiation facilities are various kinds of capsules, hydraulic rabbit facilities, high temperature and high pressure water loop, and high temperature and high pressure gas loop. The aim of this publication is a representation of the information concerned with the irradiation facilities. (author)

  11. Irradiation probe and laboratory for irradiated material evaluation

    International Nuclear Information System (INIS)

    The survey and assessment are given of the tasks carried out in the years 1971 to 1975 within the development of methods for structural materials irradiation and of a probe for the irradiation thereof in the A-1 reactor. The programme and implementation of laboratory tests of the irradiation probe are described. In the actual reactor irradiation, the pulse tube length between the pressure governor and the irradiation probe is approximately 20 m, the diameter is 2.2 mm. Temperature reaches 800 degC while the pressure control system operates at 20 degC. The laboratory tests (carried out at 20 degC) showed that the response time of the pressure control system to a stepwise pressure change in the irradiation probe from 0 to 22 at. is 0.5 s. Pressure changes were also studied in the irradiation probe and in the entire system resulting from temperature changes in the irradiation probe. Temperature distribution in the body of the irradiation probe heating furnace was determined. (B.S.)

  12. Best Estimate Thermal-Hydraulic System Analysis using the MARS Code for the Steam Generator Tube Rupture Accident in the APR1400

    International Nuclear Information System (INIS)

    A postulated SGTR (Steam Generator Tube Rupture) accident of the APR1400 was analysed using the best estimate safety analysis code, MARS (Multidimensional Analysis of Reactor Safety). The SGTR accident is one of the design basis accidents, which has a unique feature of the penetration of the barrier between the reactor coolant system (RCS) and the secondary system resulting from the failure of a steam generator U-tube. The SGTR has an importance in safety due to a concern of a containment bypass of radioactive inventory. In the course of the SGTR, the radioactivity leaking from a broken steam generator Utube mixes with the shell-side water in an affected steam generator. Leak flow from ruptured U-tubes can increase a water level and a pressure of the affected steam generator. Following a reactor trip and a turbine trip, the main steam safety valves (MSSVs) can be open to mitigate an increase in the secondary system pressure. Meanwhile, the SGTR can provide a direct flow path from the primary to the secondary system resulting in the release of fission products into the atmosphere. As one of the most limiting SGTR accidents, a leak flow equivalent to a double-ended rupture of five Utubes was analysed in this study. The main objective of this study is not only to provide physical insight into the system response of the APR1400 reactor during a SGTR but also to investigate the effect of reactor trip type of the HSGL (High Steam Generator Level) trip and the LPP (Low Pressurizer Pressure) trip on the thermal-hydraulic system response

  13. Application of a gamma spectroscopy system to the measurement of neutron cross sections necessary to the development of nuclear energy; Mise au point d'un systeme de spectroscopie pour mesurer des sections efficaces neutroniques applicables a un possible developpement du nucleaire comme source d'energie

    Energy Technology Data Exchange (ETDEWEB)

    Deruelle, O

    2002-09-01

    This work concerns the development of nuclear energy and nuclear waste management in particular. Two parts of this study can be distinguished. In the first part (theoretical), a thorium-plutonium fuel based on MOX and dedicated for PWR was investigated in order to transmute plutonium in a potentially low waste fuel cycle. It was shown that this type of fuel is not regenerative but could be used for a transition to the industrial thorium fuel cycle without building new reactors. Thanks to moderated neutron spectra and high loaded actinide mass in the core, U-233 is quickly created ({approx}300 kg/y) for a loss of about {approx}1200 kg of fissile plutonium. In the second part (experimental), we have developed and built a new reaction chamber to measure neutron cross sections of actinides by alpha-gamma spectroscopy. This experimental device (in principle transportable) was commissioned in the high flux reactor of ILL Grenoble. Neutron flux was measured by gamma spectroscopy of irradiated Al and Co samples and was found to be of the order of 6,0. 10{sup 14} n.cm{sup -2}.s{sup -1} (4%). By the irradiation of 11{mu}g of Am-243 and Pu-242, corresponding capture cross sections were measured in the thermal neutron flux at 50 deg C. These are the results: {sup 243}Am(n,{gamma}) {sup 244fond.}Am = 4,72{+-}1,42b; {sup 243}Am(n,{gamma}) {sup 244total}Am = 74,8{+-}3,25b; {sup 242}Pu (n,{gamma}){sup 243}Pu = 22,7{+-}1,09b. Uncertainties of the measurements are mostly due to the determination of the neutron flux, efficiency of the electronics and ambiguities related to the definition of the area under {alpha}-{gamma} spectra. Although our measured cross sections deviate (by 10-30%) from the corresponding values widely used in evaluated data libraries such as ENDF, JEF and JENDL, in this work we have demonstrated the feasibility and principle of our experimental method. Furthermore, the value for the 243-americium capture cross-section is in very good agreement with the last two

  14. Market testing of irradiated food

    International Nuclear Information System (INIS)

    Viet Nam has emerged as one of the three top producers and exporters of rice in the world. Tropical climate and poor infrastructure of preservation and storage lead to huge losses of food grains, onions, dried fish and fishery products. Based on demonstration irradiation facility pilot scale studies and marketing of irradiated rice, onions, mushrooms and litchi were successfully undertaken in Viet Nam during 1992-1998. Irradiation technology is being used commercially in Viet Nam since 1991 for insect control of imported tobacco and mould control of national traditional medicinal herbs by both government and private sectors. About 30 tons of tobacco and 25 tons of herbs are irradiated annually. Hanoi Irradiation Centre has been continuing open house practices for visitors from school, universities and various different organizations and thus contributed in improved public education. Consumers were found to prefer irradiated rice, onions, litchi and mushrooms over those nonirradiated. (author)

  15. Food irradiation scenario in India

    International Nuclear Information System (INIS)

    Over 3 decades of research and developmental effort in India have established the commercial potential for food irradiation to reduce post-harvest losses and to ensure food safety. Current regulations permit irradiation of onions, potatoes and spices for domestic consumption and operation of commercial irradiators for treatment of food. In May 1997 draft rules have been notified permitting irradiation of several additional food items including rice, wheat products, dry fruits, mango, meat and poultry. Consumers and food industry have shown a positive attitude to irradiated foods. A prototype commercial irradiator for spices set up by Board of Radiation and Isotope Technology (BRIT) is scheduled to commence operation in early 1998. A commercial demonstration plant for treatment of onions is expected to be operational in the next 2 years in Lasalgaon, Nashik district. (author)

  16. Gamma irradiation service in Mexico

    International Nuclear Information System (INIS)

    In 1980 it was installed in Mexico, on the National Institute of Nuclear Research, an irradiator model J S-6500 of a canadian manufacture. Actually, this is the greatest plant in the Mexican Republic that offers a gamma irradiation process at commercial level to diverse industries. However, seeing that the demand for sterilize those products were not so much as the irradiation capacity it was opted by the incursion in other types of products. During 17 years had been irradiated a great variety of products grouped of the following form: dehydrated foods, disposable products for medical use, cosmetics, medicaments, various. Nowadays the capacity of the irradiator is saturated virtue of it is operated the 24 hours during the 365 days of the year and only its operation is suspended by the preventive and corrective maintenance. However, the fresh food market does not be attended since this irradiator was designed for doses greater than 10 kGy (1.0 Mrad)

  17. Irradiation of fruit and vegetables

    International Nuclear Information System (INIS)

    There is likely to be less economic incentive to irradiate fruits and vegetables compared with applications which increase the safety of foods such as elimination of Salmonella or decontamination of food ingredients. Of the fruit and vegetable applications, irradiation of mushrooms may offer the clearest economic benefits in North-Western Europe. The least likely application appears to be sprout inhibition in potatoes and onions, because of the greater efficiency and flexibility of chemical sprout inhibitors. In the longer-term, combinations between irradiation/MAP/other technologies will probably be important. Research in this area is at an early stage. Consumer attitudes to food irradiation remain uncertain. This will be a crucial factor in the commercial application of the technology and in the determining the balance between utilisation of irradiation and of technologies which compete with irradiation. (author)

  18. CEFR Irradiation Test and Application

    International Nuclear Information System (INIS)

    China Experimental Fast Reactor (CEFR) has completed physics start-up tests in 2010 and connected the grid on 40%FP in 2011. During start-up tests, the special irradiation test subassembly has been developed for measurement of distribution of reaction rate, spectrum index and neutron spectrum by using activation method in lower power. Characteristic of neutron field for irradiation in CEFR has been researched by calculation and experiments. In future, CEFR will been operated as an irradiation test facility for fuel, material and other application, and some irradiation projects, such as irradiation of cladding material, MOX fuel and (U, Np)O2 pellet have been planned. Now some irradiation rigs have been developed. (author)

  19. Status of irradiation capsule design

    International Nuclear Information System (INIS)

    For the irradiation test after the restart of JMTR, further precise temperature control and temperature prediction are required. In the design of irradiation capsule, particularly sophisticated irradiation temperature prediction and evaluation are urged. Under such circumstance, among the conventional design techniques of irradiation capsule, the authors reviewed the evaluation method of irradiation temperature. In addition, for the improvement of use convenience, this study examined and improved FINAS/STAR code in order to adopt the new calculation code that enables a variety of analyses. In addition, the study on the common use of the components for radiation capsule enabled the shortening of design period. After the restart, the authors will apply this improved calculation code to the design of irradiation capsule. (A.O.)

  20. Food irradiation: chemistry and applications

    International Nuclear Information System (INIS)

    Food irradiation is one of the most extensively and thoroughly studied methods of food preservation. Despite voluminous data on safety and wholesomeness of irradiated foods, food irradiation is still a “process in waiting.” Although some countries are allowing the use of irradiation technology on certain foods, its full potential is not recognized. Only 37 countries worldwide permit the use of this technology. If used to its full potential, food irradiation can save millions of human lives being lost annually due to food‐borne diseases or starvation and can add billions of dollars to the world economy. This paper briefly reviews the history and chemistry of food irradiation along with its main applications, impediments to its adoption, and its role in improving food availability and health situation, particularly in developing countries of the world

  1. Gamma irradiation of fruits

    International Nuclear Information System (INIS)

    At a Joint FAO/IAEA/WHO Expert Committee on Food Irradiation (JECFI) meeting held in 1976, recommendations were made to rationalize the unnecessarily elaborate wholesomeness evaluation procedures for irradiated foodstuffs. Irradiation at the commercially recommended doses did not adversely affect the constituents of mangoes, papayas, litchis and strawberries at the edible-ripe stage. These favourable radiation-chemical results justified the development of a theoretical model mango which could be used for extrapolation of wholesomeness data from an individual fruit species to all others within the same diet class. Several mathematical models of varying orders of sophistication were evolved. In all of them, it was assumed that the radiant energy entering the system reacted solely with water. The extent of the reaction of the other components of the model fruit with the primary water radicals was then determined. No matter which mathematical treatment was employed, it was concluded that the only components which would undergo significant modification would be the sugars. In order to extrapolate these data from the mango to other fruits, mathematical models of three fruits containing less sugar than the mango, viz. the strawberry, tomato and lemon, were compiled. With these models, the conclusion was reached that the theoretical degradation spectra of these fruits were qualitatively similar to the degradation pattern of the model mango. Theory was again substantiated by the practical demonstration of the protective effect of the sugars in the tomato and lemon. The decrease in radiation damage was enhanced by the mutual protection of the components of the whole synthetic fruits with ultimate protection being afforded by the biological systems of the real fruits

  2. Detection of irradiated chestnuts

    International Nuclear Information System (INIS)

    Full text: Ionizing radiation treatment of food is growing acceptance and application to ever increasing variety of products. The method has indeed proved efficient in reducing food losses and in improving safety of products. Among vegetable products of interest for radiation treatment, chestnuts have recently been considered. Irradiation treatment of chestnuts has been authorized in countries such as Korea as a valid and safe alternative to the widespread use of fumigants. At the Italian level, Montella chestnut is a typical variety recognized as a PGI (Protected Geographical Indication) product and widely used in confectionery industry. In view of an extension of radiation treatment to this kind of product, to permit legal controls and meet consumer consensus, reliable methods for detecting irradiated chestnuts have to be proposed and validated. The task of finding detection methods for irradiated chestnuts can be in principle afforded with different methods. The cellulose and sugar contained in the skin and pulp, respectively, might suggest the use of the protocol EN 1787 and EN 13708, relative to ESR spectroscopy. In particular, the protocol EN 1787, based on ESR technique, is applied to detect cellulose radicals radio-induced in outer shell part of the sample as well as in the seed present in the inner part of the fruit. It is known that ionizing radiation may induce two different ESR signals: cellulose signal and a single line signal centered at g = 2. The protocol EN 1787 uses the low intensity cellulose signal for identification. In the present study, in case of low cellulose content, even the g = 2 is analyzed for setting up an alternative identification procedure. Protocol EN 13708, used to identify food containing crystalline sugar by ESR spectroscopy, is applied to the pulp of fruit. As for luminescence measurements, mineral isolation of silicates and TL measurements is done according to European Standard EN 1788. Preliminary test showed that the

  3. Craniospinal irradiation techniques

    Energy Technology Data Exchange (ETDEWEB)

    Scarlatescu, Ioana, E-mail: scarlatescuioana@gmail.com; Avram, Calin N. [Faculty of Physics, West University of Timisoara, Bd. V. Parvan 4, 300223 Timisoara (Romania); Virag, Vasile [County Hospital “Gavril Curteanu” - Oradea (Romania)

    2015-12-07

    In this paper we present one treatment plan for irradiation cases which involve a complex technique with multiple beams, using the 3D conformational technique. As the main purpose of radiotherapy is to administrate a precise dose into the tumor volume and protect as much as possible all the healthy tissues around it, for a case diagnosed with a primitive neuro ectoderm tumor, we have developed a new treatment plan, by controlling one of the two adjacent fields used at spinal field, in a way that avoids the fields superposition. Therefore, the risk of overdose is reduced by eliminating the field divergence.

  4. Development of blood irradiators

    International Nuclear Information System (INIS)

    Over a period of several years, a small, fully portable blood irradiator has been developed for ultimate use in suppressing early rejection of organ transplants in humans. It could also be useful for other medical problems, e.g., treating some forms of leukemia or arthritis. The units have been successfully evaluated in several animal species, resulting in sharply reduced lymphocyte levels and prolonged skin-graft retention. Work during the past year was directed toward development of hardware in anticipation of kidney transplant studies, to be performed in dogs in FY 1982, and identifying whether dose fractionation significantly changed lymphocyte response

  5. Neoplasms in irradiated populations

    International Nuclear Information System (INIS)

    The paper describes the results of three prospective studies which have been ongoing for 25 years. The study populations include: (1) persons treated with x rays in infancy for alleged enlargement of the thymus gland; (2) persons treated in childhood with x rays and/or radium for lymphoid hyperplasia of the nasopharynx; and (3) women treated with x rays for acute postpartum mastitis. The studies have resulted in the quantification of risk for radiogenic thyroid and breast cancer for periods up to 40 years post irradiation

  6. Microvascular anastomes in irradiated vessels

    International Nuclear Information System (INIS)

    The aim of the study was to investigate the healing of microvascular anastomoses in rat common femoral arteries and veins eight to nine months after the vessels had received irradiation. Patency rates in non irradiated arteries and veins were 92% and 100% respectively. The rate in irradiated arteries and veins (all groups together) was 96% and 69% respectively. The venous patency rate in the 5000, 7000 and 9000 rads groups taken together (13 rats) fell to 55%. (Auth.)

  7. Irradiation stability of welded joints

    International Nuclear Information System (INIS)

    Results are presented of investigations into the neutron irradiation stability of welded joints in two types of steel used for reactor pressure vessels. Details are given of the materials used, method of welding and tests applied. The effect of irradiation on the notch toughness transition curve is shown. The results of the studies into irradiation embrittlement of all the welded joints and parent materials of the steels for the pressure vessels are summarized. (U.K.)

  8. National symposium on food irradiation

    International Nuclear Information System (INIS)

    This report contains abstracts of papers delivered at the National symposium on food irradiation held in Pretoria. The abstracts have been grouped into the following sections: General background, meat, agricultural products, marketing and radiation facilities - cost and plant design. Each abstract has been submutted separately to INIS. Tables listing irradiated food products cleared for human consumption in different countries are given as well as a table listing those irradiated food items that have been cleared in South Africa

  9. Food irradiation facilities at Trombay

    International Nuclear Information System (INIS)

    The process parameters for radiation preservation of foods including grain, fruits, vegetables and seafoods are being evaluated with the experimental cobalt-60 and caesium-137 irradiators. The design features of three irradiators that are being used were considered mainly on the basis of obtaining variable throughputs and variable dose rates, making these facilities flexible for operation for a variety of purposes and the products. The paper highlights certain aspects of these irradiators, modifications carried out, dosimetry and maintenance requirements. (auth.)

  10. Desinfestation of soybeans by irradiation

    International Nuclear Information System (INIS)

    The effect of irradiation with the doses 0.5 and 1.0 kGy on desinfestation of soy beans and on important chemical compounds of this product was studied in this paper. The results showed the effectiveness of applied doses in the control of insect pests of soy beans during its storage and total proteins, fat and moisture and also the identity and quality characteristics of oil extrated from irradiated product which were not change by irradiation

  11. JRR-4 medical irradiation facility

    Energy Technology Data Exchange (ETDEWEB)

    Torii, Y.; Yamamoto, K.; Hori, N.; Kumada, H.; Horiguchi, Y. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-11-01

    JAERI started Boron Neutron Capture Therapy (BNCT) at JRR-2 in 1990. JRR-2 was performed 33 BNCT until 1996 when JRR-2 operation was terminated for decommissioning the reactor. JRR-4 was constructed to research the reactor shielding of the first Japanese nuclear ship ''Mutsu'' in 1965. JRR-4 was modified for reducing fuel enrichment and constructing a new medical irradiation facility at 1997 when after the terminating operation of JRR-2. The medical irradiation facility is especially using for BNCT of brain cancer. JRR-4 medical irradiation facility was designed for both using of thermal neutron beam and epi-thermal neutron. Thermal neutron is using for conventional Japanese BNCT as inter operative irradiation therapy. Epi-thermal neutron beam will be using advanced BNCT for deep cancer and without craniotomy operation for irradiation at the facility. The first medical irradiation for BNCT of JRR-4 was carried out on October 25, 1999. Since then, seven times of irradiation was performed by the end of June 2000. In BNCT irradiation, boron concentration and thermal flux measurements were performed by JAERI. Boron concentration of patient brood was measured using prompt gamma ray analysis technique. Thermal neutron flux was measured by gold wire activation method using beta - gamma coincidence counting system. There data were furnished to medical doctor for determination the irradiation time of BNCT. (author)

  12. Hepatopathy following irradiation and adriamycin

    International Nuclear Information System (INIS)

    This report describes two cases of hepatopathy following irradiation and adriamycin at doses and volumes of irradiation ordinarily considered within the tolerance of hepatic function. In one case, fatal hepatopathy followed 2400 rad/17 fractions/28 days to the entire liver with preceding and concurrent adriamycin. In the second case moderate clinical changes occurred after treatment in which much of the right lobe of the liver was shielded following 2500 rad/23 fractions/32 days with adriamycin administered before, during, and after irradiation. The locally enhancing effects of adriamycin on hepatic tolerance to irradiation are discussed

  13. Societal benefits of food irradiation

    International Nuclear Information System (INIS)

    Food irradiation has a direct impact on society by reducing the occurrence of food-borne illness, decreasing food spoilage and waste, and facilitating global trade. Food irradiation is approved in 40 countries around the world to decontaminate food of disease and spoilage causing microorganisms, sterilize insect pests, and inhibit sprouting. A recent estimate suggests that 500,000 metric of food is currently irradiated worldwide, primarily to decontaminate spices. Since its first use in the 1960s the use of irradiation for food has grown slowly, but it remains the major technology of choice for certain applications. The largest growth sector in recent years has been phytosanitary irradiation of fruit to disinfest fruit intended for international shipment. For many countries which have established strict quarantine standards, irradiation offers as an effective alternative to chemical fumigants some of which are being phased out due to their effects on the ozone layer. Insects can be sterilized at very low dose levels, thus quality of fruit can be maintained. Irradiation is also highly effective in destroying microbial pathogens such as Salmonella spp., E. coli, and Listeria, hence its application for treatment of spices, herbs, dried vegetables, frozen seafood, poultry, and meat and its contribution to reducing foodborne illnesses. Unfortunately the use of irradiation for improving food safety has been under-exploited. This presentation will provide details on the use, benefits, opportunities, and challenges of food irradiation. (author)

  14. International Developments of Food Irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Loaharanu, P. [Head, Food Preservation Section, Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture, Wagramerstr. 5, A-1400, Vienna (Austria)

    1997-12-31

    Food irradiation is increasingly accepted and applied in many countries in the past decade. Through its use, food losses and food-borne diseases can be reduced significantly, and wider trade in many food items can be facilitated. The past five decades have witnessed a positive evolution on food irradiation according to the following: 1940`s: discovery of principles of food irradiation; 1950`s: initiation of research in advanced countries; 1960`s: research and development were intensified in some advanced and developing countries; 1970`s: proof of wholesomeness of irradiated foods; 1980`s: establishment of national regulations; 1990`s: commercialization and international trade. (Author)

  15. International Developments of Food Irradiation

    International Nuclear Information System (INIS)

    Food irradiation is increasingly accepted and applied in many countries in the past decade. Through its use, food losses and food-borne diseases can be reduced significantly, and wider trade in many food items can be facilitated. The past five decades have witnessed a positive evolution on food irradiation according to the following: 1940's: discovery of principles of food irradiation; 1950's: initiation of research in advanced countries; 1960's: research and development were intensified in some advanced and developing countries; 1970's: proof of wholesomeness of irradiated foods; 1980's: establishment of national regulations; 1990's: commercialization and international trade. (Author)

  16. Generic phytosanitary irradiation treatments

    International Nuclear Information System (INIS)

    The history of the development of generic phytosanitary irradiation (PI) treatments is discussed beginning with its initial proposal in 1986. Generic PI treatments in use today are 150 Gy for all hosts of Tephritidae, 250 Gy for all arthropods on mango and papaya shipped from Australia to New Zealand, 300 Gy for all arthropods on mango shipped from Australia to Malaysia, 350 Gy for all arthropods on lychee shipped from Australia to New Zealand and 400 Gy for all hosts of insects other than pupae and adult Lepidoptera shipped to the United States. Efforts to develop additional generic PI treatments and reduce the dose for the 400 Gy treatment are ongoing with a broad based 5-year, 12-nation cooperative research project coordinated by the joint Food and Agricultural Organization/International Atomic Energy Agency Program on Nuclear Techniques in Food and Agriculture. Key groups identified for further development of generic PI treatments are Lepidoptera (eggs and larvae), mealybugs and scale insects. A dose of 250 Gy may suffice for these three groups plus others, such as thrips, weevils and whiteflies. - Highlights: ► The history of phytosanitary irradiation (PI) treatments is given. ► Generic PI treatments in use today are discussed. ► Suggestions for future research are presented. ► A dose of 250 Gy for most insects may suffice.

  17. Food irradiation and sterilization

    Science.gov (United States)

    Josephson, Edward S.

    Radiation sterilization of food (radappertization) requires exposing food in sealed containers to ionizing radiation at absorbed doses high enough (25-70 kGy) to kill all organisms of food spoilage and public health significance. Radappertization is analogous to thermal canning is achieving shelf stability (long term storage without refrigeration). Except for dry products in which autolysis is negligible, the radappertization process also requires that the food be heated to an internal temperature of 70-80°C (bacon to 53°C) to inactivate autolytic enzymes which catalyze spoilage during storage without refrigeration. To minimize the occurence of irradiation induced off-flavors and odors, undesirable color changes, and textural and nutritional losses from exposure to the high doses required for radappertization, the foods are vacuum sealed and irradiated frozen (-40°C to -20°C). Radappertozed foods have the characteristic of fresh foods prepared for eating. Radappertization can substitute in whole or in part for some chemical food additives such as ethylene oxide and nitrites which are either toxic, carcinogenic, mutagenic, or teratogenic. After 27 years of testing for "wholesomeness" (safety for consumption) of radappertized foods, no confirmed evidence has been obtained of any adverse effecys of radappertization on the "wholesomeness" characteristics of these foods.

  18. Food irradiation and sterilization

    International Nuclear Information System (INIS)

    Radiation sterilization of food (radappertization) requires exposing food in sealed containers to ionizing radiation at absorbed doses high enough (25 to 70 kGy) to kill all organisms of food spoilage and public health significance. Radappertization is analogous to thermal canning in achieving shelf stability (long term storage without refrigeration). Except for dry products in which autolysis is negligible, the radappertization process also requires that the food be heated to an internal temperature of 70 to 800C (bacon to 530C) to inactivate autolytic enzymes which catalyze spoilage during storage without refrigeration. To minimize the occurrence of irradiation induced off-flavors and odors, undesirable color changes, and textural and nutritional losses from exposure to the high doses required for radappertization, the foods are vacuum sealed and irradiated frozen (-400C to -200C). Radappertized foods have the characteristic of fresh foods prepared for eating. Radappertization can substitute in whole or in part for some chemical food additives such as ethylene oxide and nitrites which are either toxic, carcinogenic, mutagenic, or teratogenic. After 27 years of testing for 'wholesomeness' (safety for consumption) of radappertized foods, no confirmed evidence has been obtained of any adverse effects of radappertization on the 'wholesomeness' characteristics of these foods. (author)

  19. Irradiation of food

    International Nuclear Information System (INIS)

    Processing of food with ionizing radiation is a method suitable to enhance shelf-life and hygienic quality. Up to a dose of 10 kGy the method is considered wholesome. In many countries the practical use of food irradiation is increasing, however, in the Federal Republic of Germany the process is strictly forbidden. Applications and methods for radiation processing of food are compiled, limits and prospects are explained, and advantages and disadvantages are compared with traditional methods. Identification of irradiated foods and dosimetry and process control for radiation processing of food are areas where further research is needed. Continuous processing of particulate foods in bulk is an application where electron accelerators might be profitable. Beam parameters and velocity distribution of food particles in the treatment area can be matched for an effective result. Thus, dose distribution can be adjusted for homogeneous treatment and at the same time radiation energy is absorbed almost completely. An example of an experimental plant for radiation processing of grain and spices is shown. Decontamination of spices by radiation processing is an alternative to chemical fumigation, which now is widely forbidden. (orig.)

  20. Facts about food irradiation: Irradiation and food safety

    International Nuclear Information System (INIS)

    This fact sheet focusses on the question of whether irradiation can be used to make spoiled food good. No food processing procedures can substitute for good hygienic practices, and good manufacturing practices must be followed in the preparation of food whether or not the food is intended for further processing by irradiation or any other means. 3 refs

  1. Facts about food irradiation: Packaging of irradiated foods

    International Nuclear Information System (INIS)

    This fact sheet considers the effects on packaging materials of food irradiation. Extensive research has shown that almost all commonly used food packaging materials toted are suitable for use. Furthermore, many packaging materials are themselves routinely sterilized by irradiation before being used. 2 refs

  2. Precificação de consultoria empresarial com a contribuição das estratégias de apreçamento = Entrepreneurial Counseling Pricing with Pricing Strategy Contribution

    Directory of Open Access Journals (Sweden)

    Nivaldo João dos Santos

    2008-11-01

    Full Text Available A precificação de serviços de consultoria também pode se beneficiar dos conceitos e idéias das estratégias de apreçamento de bens de consumo de massa, especificamente na área de consultoria de gestão empresarial. Apesar deste campo ser dominado por grandes corporações multinacionais, ainda existe espaço para empresas e profissionais nacionais. Por se tratar de mercado que envolve valores de grande magnitude, imaginasse que as instituições de sucesso adotem estratégia de apreçamento. Neste trabalho, estratégias de apreçamento foram selecionadas para exame e verificação de aplicabilidade quando do estabelecimento valor pelos serviços da consultoria de gestão empresarial. O apreçamento de desnatação, apreçamento de penetração, apreçamento neutro e apreçamento baseado em valor tiveram seus conceitos sintetizados para fins de verificação. O apreçamento baseado em valor se revelou o mais propício para este tipo de produto (consultoria e o processo de comunicação é o elemento crítico para evidenciar valor, benefícios e, finalmente, justificar o preço do serviço. A sugestão de roteiro para apreçamento de serviço de consultoria empresarial é apresentada ao final, como resultado da análise das diversas estratégias de apreçamento.The pricing of counseling services may also benefit from strategy concepts and ideas ofmass consumption goods pricing, specifically within the entrepreneurial managementcounseling area. Even though this field has been taken over by big multinationalcorporations, there is still some space for national enterprisings and professionals. As itis a market that involves values of great magnitude, it is thought that successfulinstitutions adopt this pricing strategy. In this study, pricing strategies were selectedfor analysis and applicability checking by the time the price for entrepreneurialmanagement counseling service was established. The skimming pricing, penetratingpricing, neutral

  3. Storage tests with irradiated and non-irradiated onions

    International Nuclear Information System (INIS)

    The results of several test series on the storage of irradiated and non-irradiated German grown onion are reported. Investigated was the influence of the irradiation conditions such as time and dose and of the storage conditions on sprouting, spoilage, browning of the vegetation centres, composition of the onions, strength and sensorial properties of seven different onion varieties. If the onions were irradiated during the dormancy period following harvest, a dose of 50 Gy (krad) was sufficient to prevent sprouting. Regarding the irradiated onions, it was not possible by variation of the storage conditions within the limits set by practical requirements to extend the dormancy period or to prevent browning of the vegetation centres, however. (orig.) 891 MG 892 RSW

  4. Consumer acceptance of irradiated poultry

    International Nuclear Information System (INIS)

    A simulated supermarket setting (SSS) test was conducted to determine whether consumers (n = 126) would purchase irradiated poultry products, and the effects of marketing strategies on consumer purchase of irradiated poultry products. Consumer preference for irradiated poultry was likewise determined using a home-use test. A slide program was the most effective educational strategy in changing consumers' purchase behavior. The number of participants who purchased irradiated boneless, skinless breasts and irradiated thighs after the educational program increased significantly from 59.5 and 61.9% to 83.3 and 85.7% for the breasts and thighs, respectively. Using a label or poster did not increase the number of participants who bought irradiated poultry products. About 84% of the participants consider it either 'somewhat necessary' or 'very necessary' to irradiate raw chicken and would like all chicken that was served in restaurants or fast food places to be irradiated. Fifty-eight percent of the participants would always buy irradiated chicken if available, and an additional 27% would buy it sometimes. About 44% of the participants were willing to pay the same price for irradiated chicken as for nonirradiated. About 42% of participants were willing to pay 5% or more than what they were currently paying for nonirradiated chicken. Seventy-three percent or more of consumers who participated in the home-use test (n = 74) gave the color, appearance, and aroma of the raw poultry products a minimum rating of 7 (= like moderately). After consumers participated in a home-use test, 84 and 88% selected irradiated thighs and breasts, respectively, over nonirradiated in a second SSS test

  5. Consumer acceptance of irradiated poultry.

    Science.gov (United States)

    Hashim, I B; Resurreccion, A V; McWatters, K H

    1995-08-01

    A simulated supermarket setting (SSS) test was conducted to determine whether consumers (n = 126) would purchase irradiated poultry products, and the effects of marketing strategies on consumer purchase of irradiated poultry products. Consumer preference for irradiated poultry was likewise determined using a home-use test. A slide program was the most effective educational strategy in changing consumers' purchase behavior. The number of participants who purchased irradiated boneless, skinless breasts and irradiated thighs after the educational program increased significantly from 59.5 and 61.9% to 83.3 and 85.7% for the breasts and thighs, respectively. Using a label or poster did not increase the number of participants who bought irradiated poultry products. About 84% of the participants consider it either "somewhat necessary" or "very necessary" to irradiate raw chicken and would like all chicken that was served in restaurants or fast food places to be irradiated. Fifty-eight percent of the participants would always buy irradiated chicken if available, and an additional 27% would buy it sometimes. About 44% of the participants were willing to pay the same price for irradiated chicken as for nonirradiated. About 42% of participants were willing to pay 5% or more than what they were currently paying for nonirradiated chicken. Seventy-three percent or more of consumers who participated in the home-use test (n = 74) gave the color, appearance, and aroma of the raw poultry products a minimum rating of 7 (= like moderately). After consumers participated in a home-use test, 84 and 88% selected irradiated thighs and breasts, respectively, over nonirradiated in a second SSS test. PMID:7479506

  6. Food irradiation development: Malaysian perspective

    International Nuclear Information System (INIS)

    Malaysia recognised the potential of food irradiation as a technology that can contribute to solving some preservation problems associated with local agricultural produce. Research studies in this technology were initiated in late 1970s and since 1985, all activities pertaining to R and D applications, adoption and technology transfer of food irradiation were coordinated by The National Working Committee on Food Irradiation which comprises of members from research institutes, universities, regulatory agencies and consumer association. To date, technical feasibility studies conducted on 7 food items / agricultural commodities of economic importance demonstrated the efficacy of irradiation in extending shelf-life, improving hygienic quality and overcoming quarantine barriers in trade. Presently, 1 multipurpose Co-60 irradiator (I MCi), 2 gammacells and an electron beam machine (3 MeV) are available at MINT for research and commercial runs. The Malaysian Standards on Guidelines for Irradiation of Food was formulated in 1992 to facilitate application by local food industries. However, Malaysia has not yet commercially adopt the technology. Among many factors contributing to the situation is the apparent lack of interest by food industries and consumers. Consumer attitude study indicated majority of consumers are still unaware of the benefits of the technology and expressed concern for the safety of process and irradiated products due to limited knowledge and adverse publicity by established consumer groups. Although the food processors indicate positive attitude towards food irradiation, there remain many factors delaying its commercial application such as limited knowledge, cost-benefit, logistics and consumer acceptance. On the regulatory aspect, approval is required from the Director-General of Ministry of Health prior to application of irradiation on food and sale of irradiated food but efforts are being geared towards approving irradiation of certain food

  7. Neutronics calculation of an heterogeneous compact and thermal core by means of deterministic and stochastic transport theory. Application to the experimental reactor of the University of Strasbourg; Modelisation neutronique d`un coeur thermique compact et heterogene en theorie du transport deterministe et probabiliste. Application au reacteur experimental de l`Universite de Strasbourg

    Energy Technology Data Exchange (ETDEWEB)

    Jammes, Ch

    1997-11-28

    The aim of this work is to create, validate theoretically and experimentally a calculation route for a thermal irradiation reactor. This is the research reactor of the University of Strasbourg, which presents all of characteristics of this reactor-type: compact and heterogeneous core, slab-type fuel with a high 235-uranium enrichment. This calculation route is based on the first use of the following two modern transport methods: the TDT method and the Monte Carlo method. The former, programmed within the APOLLO2 code, is a two dimensional collision probabilities method. The later, used by the TRIPOLI4 code, is a stochastic method. Both can be applied to complex geometries. After a few theoretical reminders about transport codes, a set of integral experiments is described which have been realized within the research reactor of the University of Strasbourg. One of them has been performed for this study. At the beginning of the theoretical part, significant errors are apparent due to the use of calculation route based on homogenization, condensation and the diffusion approximation. An extensive comparison between the discrete ordinates method and the TDT method carries out that the use of the TDT method is relevant for the studied reactor. The treatment of axial leakage with this method is the only disadvantage. Therefore, the use of the code TRIPOLI4 is recommended for a more accurate study of leakage within a reflector. By means of the experimental data, the ability of our calculation route is confirmed for essential neutronics questions such as the critical mass determination, the power distribution and the fuel management. (author)

  8. Detection methods of irradiated foodstuffs

    International Nuclear Information System (INIS)

    Full text: Food irradiation has, in certain circumstances, an important role to play both in promoting food safety and in reducing food losses. The safety and availability of nutritious food are essential components of primary health care. WHO actively encourages the proper use of food irradiation in the fight against foodborne diseases and food losses. To this end, it collaborates closely with FAO and IAEA. Food irradiation can have a number of beneficial effects, including delay of ripening and prevention of sprouting; control of insects, parasites, helminths, pathogenic and spoilage bacteria, moulds and yeasts; and sterilization, which enables commodities to be stored unrefrigerated for long periods. The 1990s witnessed a significant advancement in food irradiation processing. As a result, progress has been made in commercialization of the technology, culminating in greater international trade in irradiated foods and the implementation of differing regulations relating to its use in many countries. Codex General Standard for Irradiated Foodstuffs and Recommended International Code of Practice for the Operation of Irradiation Facilities Used for the Treatment of Foods regulate food irradiation at international level. At European Union level there are in power Directive 1999/2/EC and Directive1999/3/EC. Every particular country has also its own regulations regarding food irradiation. In Romania, since 2002 the Norms Regarding Foodstuffs and Food Ingredients Treated by Ionizing Radiation are in power. These Norms are in fact the Romanian equivalent law of the European Directives 1999/2/EC and 1999/3/EC. The greater international trade in irradiated foods has led to the demand by consumers that irradiated food should be clearly labeled as such and that methods capable of differentiating between irradiated and nonirradiated products should be available. Thus a practical basis was sought to allow consumers to exercise a free choice as to which food they purchase. If a

  9. National symposium on food irradiation

    International Nuclear Information System (INIS)

    This report contains proceedings of papers delivered at the national symposium on food irradiation held in Pretoria. The proceedings have been grouped into the following sections: general background; meat; agricultural products; marketing; and radiation facilities - cost and plant design. Each paper has been submitted separately to INIS. Tables listing irradiated food products cleared for human consumption in different countries are given

  10. Neutron irradiation effect of silicon

    International Nuclear Information System (INIS)

    Several kinds of silicon wafers were irradiated at four neutron fields with different energy spectra. Electrical resistivity and deep level defect concentrations after the neutron irradiation, and their changes against number of displacement atoms (DPA's) for different neutron fields were compared. The number of DPA's was calculated by N. Yamano's data. (author)

  11. Craniospinal irradiation using Rapid Arc

    Energy Technology Data Exchange (ETDEWEB)

    Fandino, J. M.; Silva, M. C.; Marino, A.; Candal, A.; Diaz, I.; Fernandez, C.; Gesto, C.; Izquierdo, P.; Losada, C.; Poncet, M.; Soto, M.; Triana, G.

    2013-07-01

    Cranio-Spinal Irradiation is technically very challenging, historically field edge matching is needed because of the mechanical limitations of standard linear accelerators. The purpose of this study is to assess the Volumetric Arc Therapy as a competitive technique for Cranio-Spinal Irradiation compared to the conventional 3D Conformal Radiotherapy technique. (Author)

  12. The safety of irradiated foods

    International Nuclear Information System (INIS)

    This state of the art outline review written for 'Food Manufacture' looks at the wholesomeness of irradiated foods, and makes a comparison with conventionally treated products. Topics mentioned are doses, radioresistance of microorganisms especially clostudium botulinum and the problem of bacterial toxins, storage conditions, nutrition, especially vitamin loss, and detection of irradiation. (U.K.)

  13. Food irradiation: a Queensland perspective

    International Nuclear Information System (INIS)

    The National Farmers Federation is satisfied that all safety issues associated with food irradiation have been adequately addressed. It recommends that the Codex Alimentarius standard of 120 kilogray treatment be adopted in Australia. Economic arguments are advanced for the irradiation of horticultural products, fish, seafoods, red meat and chicken meat

  14. Consumer attitude toward food irradiation

    International Nuclear Information System (INIS)

    Consumer attitudes toward food irradiation were evaluated. The influence of educational efforts on consumer concern for the safety of irradiated products and willingness to buy irradiated foods were measured. Demographic and psychological factors were studied in relation to attitudes. An educational leaflet describing current scientific information regarding the safety, advantages, and disadvantages of food irradiation was developed and used in two studies evaluating attitude change. In the first study, attitude change among two groups of consumers with different philosophic orientations was measured. In a second study, the effectiveness of an educational leaflet received through the mail and a poster display were examined. In a third study response to food irradiation was related to value hierarchy, locus of control, innovativeness, and demographic parameters. Initially, subjects showed a higher concern for other areas of food safety, particularly the use of chemicals and sprays on food, than toward food irradiation. After educational efforts, conventional consumers expressed minor concern toward irradiation whereas ecologically sensitive alternative consumers obtained from a food cooperative expressed major concern. A knowledgeable discussion leader lowered irradiation concern among conventional consumers. In contrast, concern among alternative consumers did not diminish when given the opportunity to discuss safety issues with a knowledgeable person

  15. Nutritional aspects of irradiated shrimp

    International Nuclear Information System (INIS)

    Data available in the literature on the nutritional aspects of irradiated shrimp are reviewed and the indication is that irradiation of shrimp at doses up to about 3.2 kGy does not significantly affect the levels of its protein, fat, carbohydrate and ash. There are no reports on the effect of irradiation of shrimp above 3.2 kGy on these components. Limited information available indicates that there are some minor changes in the fatty acid composition of shrimp as a result of irradiation. Irradiation also causes some changes in the amino acid composition of shrimp; similar changes occur due to canning and hot-air drying. Some of the vitamins in shrimp, such as thiamine, are lost as a result of irradiation but the loss is less extensive than in thermally processed shrimp. Protein quality of shrimp, based on the growth of rats as well as that of Tetrahymena pyriformis, is not affected by irradiation. No adverse effects attributed to irradiation were found either in short-term or long-term animal feeding tests

  16. Food irradiation and bacterial toxins

    International Nuclear Information System (INIS)

    The authors' findings indicate that irradiation confers no advantage over heat processing in respect of bacterial toxins (clostridium botulinum, neurotoxin A and staphylococcal enterotoxin A). It follows that irradiation at doses less than the ACINF recommended upper limit of 10 kGy could not be used to improve the ambient temperature shelf life on non-acid foods. (author)

  17. Irradiation damage in lithium ceramics

    International Nuclear Information System (INIS)

    The irradiation response of two candidate tritium-breeding materials, LiAlO2 and Li2ZrO3, was investigated using electron irradiation to produce atomic displacements, and EPR and transmission electron microscopy (TEM) to detect damage responses. In a first set of experiments, single crystals and sintered polycrystals of γ-LiAlO2 were irradiated with 2.5 MeV electrons at a temperature of 20 K. EPR measurements made at 4 K on samples kept at 77 K after electron irradiation confirm that paramagnetic defects are created during irradiation, and that most of these defects disappear at about 100 K. TEM observations at room temperature indicate, however, that annealing of these defects does not result in visible defect aggregates. In a second set of experiments, sintered polycrystalline LiAlO2 and Li2ZrO3 samples were thinned to electron transparency and heavily irradiated in situ with 200 keV electrons. In LiAlO2, laths of LiAl5O8 grew intragranularly under irradiation. Li2ZrO3 showed little or no aggregate damage after extensive irradiation near room temperature. (orig.)

  18. Economic aspects of food irradiation

    International Nuclear Information System (INIS)

    Currently there is a movement towards commercial use of food irradiation. As with other commercial operations, the objective of commercial food irradiation is to process foods to obtain a particular beneficial effect and to market such foods to obtain a profit. Using economic analysis, business management evaluates benefits and risks in order to estimate the profitability of a contemplated venture employing food irradiation. If an economic analysis indicates that an adequate return on the required investment can be obtained, management has a proper basis on which to proceed with the venture. A procedure for obtaining an appropriate economic analysis for commercial use of food irradiation is considered herewith in detail. It covers the use of either a contract service, free standing type of irradiation facility or an integrated in-plant irradiator. The kinds of information needed for the economic analysis are indicated, including those for estimating capital and operating costs. It is emphasized that specific information relevant to the venture under consideration is required. Since commercial use of food irradiation requires that it be profitable, and since profitability is the incentive for a business to undertake it, a number of uses of food irradiation are identified and listed as those that have the potential for yielding cost-benefits. (author). 7 refs, 1 fig., 4 tabs

  19. Commercial implementation of food irradiation

    Science.gov (United States)

    Welt, M. A.

    In July 1981, the first specifically designed multi-purpose irradiation facility for food irradiation was put into service by the Radiation Technology, Inc. subsidiary Process Technology, Inc. in West Memphis, Arkansas. The operational experience gained, resulted in an enhanced design which was put into commercial service in Haw River, North Carolina, by another subsidiary, Process Technology (N.C.), Inc. in October 1983. These facilities have enabled the food industry to assess the commercial viability of food irradiation. Further impetus towards commercialization of food irradiation was gained in March 1981 with the filing in the Federal Register, by the FDA, of an Advanced Proposed Notice of Rulemaking for Food Irradiation. Two years later in July 1983, the FDA approved the first food additive regulation involving food irradiation in nineteen years, when they approved the Radiation Technology, Inc. petition calling for the sanitization of spices, onion powder and garlic powder at a maximum dosage of 10 kGy. Since obtaining the spice irradiation approval, the FDA has accepted four additional petitions for filing in the Federal Register. One of the petitions which extended spice irradiation to include insect disinfestation has issued into a regulation while the remaining petitions covering the sanitization of herbs, spice blends, vegetable seasonings and dry powdery enzymes as well as the petition to irradiate hog carcasses and pork products for trichinae control at 1 kGy, are expected to issue either before the end of 1984 or early in 1985. More recently, food irradiation advocates in the United States received another vote of confidence by the announcement that a joint venture food irradiation facility to be constructed in Hawaii by Radiation Technology, is backed by a contractual committment for the processing of 40 million pounds of produce per year. Another step was taken when the Port of Salem, New Jersey announced that the Radiation Technology Model RT-4104

  20. Food irradiation seminar: Asia and the Pacific

    International Nuclear Information System (INIS)

    The report covers the Seminar for Asia and the Pacific on the practical application of food irradiation. The seminar assessed the practical application of food irradiation processes, commercial utilisation and international trade of irradiated food

  1. Safer food means food irradiation

    International Nuclear Information System (INIS)

    In this article the author presents the sanitary advantages that are brought by food irradiation. OMS experts state that this technique is safe and harmless for any average global dose between 10 KGy and 100 KGy. Whenever a seminar is held on the topic, it is always concluded that food irradiation should be promoted and favoured. In France food irradiation is authorized for some kinds of products and exceptionally above a 10 KGy dose. Historically food irradiation has been hampered in its development by its classification by American Authorities as food additives in 1958 (Delanay clause). The author draws a parallel between food irradiation and pasteurization or food deep-freezing in their beginnings. (A.C.)

  2. Eatability of the irradiated food

    International Nuclear Information System (INIS)

    A food is eatable and innocuous when it has an acceptable nutritional quality, it is toxicological and microbiologically safe for the human consumption. Not one preservation treatment allows to assure this in absolute form. As it happens with other conservation methods, the irradiation produce biological, chemical and physical changes in the treated food. For to check if such changes could cause damages to the health of the consumer, its have been carried out extensive studies to evaluate the inoculate of the irradiated foods. Analyzing diverse toxicity studies to prove the eatability of the irradiated foods, in this work those are presented but important in chronological order. In summary, until today it exists a great heap of tests that they demonstrate without place to doubts that the foods irradiated with a dose up to 10 KGy its are capable for the human consumption, for what can to be concluded that a safety margin exists to consume foods irradiated. (Author)

  3. Consumer acceptance of irradiated food

    International Nuclear Information System (INIS)

    There was a widely held opinion during the 1970's and 1980's that consumers would be reluctant to purchase irradiated food, as it was perceived that consumers would confuse irradiated food with food contaminated by radionuclides. Indeed, a number of consumer attitude surveys conducted in several western countries during these two decades demonstrated that the concerns of consumers on irradiated food varied from very concerned to seriously concerned.This paper attempts to review parameters conducting in measuring consumer acceptance of irradiated food during the past three decades and to project the trends on this subject. It is believed that important lessons learned from past studies will guide further efforts to market irradiated food with wide consumer acceptance in the future. (Author)

  4. Indication method of irradiated meat

    International Nuclear Information System (INIS)

    An injury of Chromosome DNA of irradiated meat was indicated by mitochondria DNA (mt DNA) method. Sample was irradiated by 60Co-γ ray at 6 kGy/h of dose rate at 0degC. Mitochondria DNA was obtained by the mitochondria partition method and analyzed by an electrophoresis method. mt DNA of irradiated ox liver can be indicated by PCR method, restriction enzyme method and supercoil/ring opening comparative method. However, the other meat such as chicken and other parts of meat could not be indicated depends on large fat content. About 4 kGy irradiation on liver can indicate whether it was irradiated or not. (S.Y.)

  5. Consumer acceptance of irradiated food

    Energy Technology Data Exchange (ETDEWEB)

    Loaharanu, P. [Head, Food Preservation Section, Joint FAO/ IAEA Division of Nuclear Techniques in Food and Agriculture, Wagramerstr. 5, A-1400, Vienna (Austria)

    1997-12-31

    There was a widely held opinion during the 1970`s and 1980`s that consumers would be reluctant to purchase irradiated food, as it was perceived that consumers would confuse irradiated food with food contaminated by radionuclides. Indeed, a number of consumer attitude surveys conducted in several western countries during these two decades demonstrated that the concerns of consumers on irradiated food varied from very concerned to seriously concerned.This paper attempts to review parameters conducting in measuring consumer acceptance of irradiated food during the past three decades and to project the trends on this subject. It is believed that important lessons learned from past studies will guide further efforts to market irradiated food with wide consumer acceptance in the future. (Author)

  6. Irradiation environment and materials behavior

    International Nuclear Information System (INIS)

    Irradiation environment is unique for materials used in a nuclear energy system. Material itself as well as irradiation and environmental conditions determine the material behaviour. In this review, general directions of research and development of materials in an irradiation environment together with the role of materials science are discussed first, and then recent materials problems are described for energy systems which are already existing (LWR), under development (FBR) and to be realized in the future (CTR). Topics selected are (1) irradiation embrittlement of pressure vessel steels for LWRs, (2) high fluence performance of cladding and wrapper materials for fuel subassemblies of FBRs and (3) high fluence irradiation effects in the first wall and blanket structural materials of a fusion reactor. Several common topics in those materials issues are selected and discussed. Suggestions are made on some elements of radiation effects which might be purposely utilized in the process of preparing innovative materials. (J.P.N.) 69 refs

  7. Irradiated mandibular autografts

    International Nuclear Information System (INIS)

    The cosmetic and functional disability associated with mandibular resection has been a major problem to the patient with direct invasion of the mandible by oral cancer. Marginal resections with combined postoperative radiation therapy have frequently been substituted for the more preferred segmental resections and resultant deformities. Presented are 15 cases of oral cavity cancer involving resection of the mandible, immediate radiation to 10,000 rad, and primary reconstruction as irradiated mandibular autografts. The longest following is 4 years and 3 months, with a success rate of 66%. Morbidity is minimal as compared to autogenous bone grafting. Tumor size, previous radiation, or use of regional flaps have not been a factor in the success of this method in reconstruction of the mandible primarily

  8. Irradiation effects in glasses

    International Nuclear Information System (INIS)

    The deposition of irradiation energy can alter the physical properties of glasses through bond-breaking (energetic photons; fast particles) and atomic displacements (Coulombic and collisional: n0, e, ions). These processes can alter UV-visible optical properties via electron-hole trapping and IR-spectra as a result of network damage. The movement of network atoms results in volume dilatation which change the hardness, refractive index, and dissolution rates. All of these changes can be realized with ion implantation and, in addition, implantation of chemically active species can lead to compound formation in the implanted regions. For this reason, emphasis will be placed on the implantation-induced surface modifications of glasses (mostly silicates). The paper includes crystallization, surface stress, refractive index changes and optoelectronic application and chemical reactivity

  9. Effets d'irradiation sur l'oxydation du zirconium et la diffusion de l'uranium dans la zircone

    OpenAIRE

    Bererd, Nicolas

    2003-01-01

    Cette thèse a pour contexte l'entreposage direct des assemblages de combustible usé après fonctionnement en réacteur. Afin d'obtenir des données sur les capacités de la gaine comme barrière à la diffusion de l'uranium, nous avons mené une étude fondamentale visant à modéliser l'évolution de la face interne de la gaine sous et en l'absence d'irradiation. Le comportement du zirconium en conditions réacteur a tout d'abord été étudié auprès du réacteur à haut flux de l'Institut Laue Langevin (ILL...

  10. A Study on Scenario Selection for Evaluation of Fission Product Behavior during a Severe Accident at APR 1400 Nuclear Power Plants

    International Nuclear Information System (INIS)

    As a part of an 'Evaluation of the State-of-the-Art on the Fission Product Behavior and Improvement of the Iodine Evaluation Model' Project, we at KINS plan to investigate source term behavior during a severe accident by MELCOR and to eventually compare it with results by RAIM which is an add-on code to MELCOR including iodine behavior model developed by KINS. Since species and amount of fission products in the containment depend on a specific accident, it is necessary to select accident scenarios for the study, especially taking account of its relative importance of occurrence or resultant effects for a specific plant. In this regard, we have reviewed U.S.NRC's Stateof- the-Art Reactor Consequence Analyses (SOARCA) and applied the SOARCA's method of scenario selection to Probabilistic Safety Assessment (PSA) for Shin-Kori 3·4 nuclear power plants which are APR1400 type reactors. Furthermore, we have selected scenarios from the PSA results with a new criterion in the light of risk, which consists of probability and consequence of accidents of interest. In this study, we have selected scenarios for evaluation of fission product behavior during a severe accident. Applying the U.S.NRC's SOARCA method to Shin-Kori 3·4 PSA revealed that it is practically useful to set a relative criterion for scenario studies since making a definite criterion as in SOARCA requires to consider many spatiotemporal factors such as regulation policies and safety technologies. With this in mind, the relative criterion of the scenario selection has been created using release frequency and release fraction of source term in the respect of risk from APR 1400 type Shin-Kori 3·4 Level 2 PSA. The selected representing scenarios are ISLOCA, SGTR, and SBO. A preliminary analysis has been tried for a SBO sequence with more severe and simple assumptions using MELCOR. The results show early release of volatile elements in the containment

  11. A Study on Scenario Selection for Evaluation of Fission Product Behavior during a Severe Accident at APR 1400 Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, E. S.; Kim, Han-Chul [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Cho, Song-Won [NSETec, Daejeon (Korea, Republic of)

    2015-05-15

    As a part of an 'Evaluation of the State-of-the-Art on the Fission Product Behavior and Improvement of the Iodine Evaluation Model' Project, we at KINS plan to investigate source term behavior during a severe accident by MELCOR and to eventually compare it with results by RAIM which is an add-on code to MELCOR including iodine behavior model developed by KINS. Since species and amount of fission products in the containment depend on a specific accident, it is necessary to select accident scenarios for the study, especially taking account of its relative importance of occurrence or resultant effects for a specific plant. In this regard, we have reviewed U.S.NRC's Stateof- the-Art Reactor Consequence Analyses (SOARCA) and applied the SOARCA's method of scenario selection to Probabilistic Safety Assessment (PSA) for Shin-Kori 3·4 nuclear power plants which are APR1400 type reactors. Furthermore, we have selected scenarios from the PSA results with a new criterion in the light of risk, which consists of probability and consequence of accidents of interest. In this study, we have selected scenarios for evaluation of fission product behavior during a severe accident. Applying the U.S.NRC's SOARCA method to Shin-Kori 3·4 PSA revealed that it is practically useful to set a relative criterion for scenario studies since making a definite criterion as in SOARCA requires to consider many spatiotemporal factors such as regulation policies and safety technologies. With this in mind, the relative criterion of the scenario selection has been created using release frequency and release fraction of source term in the respect of risk from APR 1400 type Shin-Kori 3·4 Level 2 PSA. The selected representing scenarios are ISLOCA, SGTR, and SBO. A preliminary analysis has been tried for a SBO sequence with more severe and simple assumptions using MELCOR. The results show early release of volatile elements in the containment.

  12. Analysis of PAFS (Passive Auxiliary Feedwater System) horizontal heat exchanger in APR+ and the scale-up capability of experimental loop

    International Nuclear Information System (INIS)

    APR+ (Advanced Power Reactor Plus) is the next generation nuclear power plant in Korea. It adopts PAFS (Passive Auxiliary Feedwater System) on the secondary system. It can replace the conventional active system for auxiliary feedwater injection to the steam generator, and it enables the coolant to be supplied by a passive system. It cools down the secondary system by heat transfer at a horizontal U-tube in PCCT (Passive Condensation Cooling Tank). High pressure steam flow from the steam generator is condensed in the horizontal heat exchanger. The water in PCCT is maintained at an atmospheric pressure, so that boiling heat transfer at the outside wall of heat exchanger and natural convection occur in PCCT pool. The heat exchanger and PCCT is higher than the steam generator, so condensate can be drained and injected to feedwater system without any active system. This study aims at analyzing the heat removal capacity for the design of the horizontal heat exchanger in PAFS. To design the condensation heat exchanger in PAFS, and the two-phase flow phenomena in horizontal U-tube and were investigated by MARS (Multi-dimensional Analysis for Reactor Safety, a thermal hydraulic system analysis code) calculation. By benchmarking with NOKO experimental result, MARS code showed a reasonable capability to quantitatively predict the condensation in horizontal tube heat exchanger. For the design of PAFS heat exchanger in APR+, the calculation results proved to sufficiently remove the decay heat of 138 MW in total by the condensation heat transfer without any active auxiliary feedwater system during TLOFW (Total Loss of Feed Water) accident. In the analysis, the distribution of thermal equilibrium quality and local liquid fraction in the horizontal U-tube was also investigated. In order to experimentally investigate the condensation phenomena and natural convection in PAFS, a test loop with a single horizontal U-tube and PCCT is under construction at KAERI (Korea Atomic Energy

  13. Irradiation preservation of Korean shellfish

    International Nuclear Information System (INIS)

    Pacific oyster, hard clam and mussel were irradiated at doses up to 0.5 Mrad, the optimum dose rather than the maximum permissible was sought for in each species and post-irradiation storage characteristics studied at 00 and 50C. No shellfish meat irradiated at doses as high as 0.5 Mrad produced any adverse odor. However the organoleptic quality of each sample irradiated at lower doses was superior to those irradiated at the higher during the early storage period. The optimum dose was determined to be 0.2 Mrad for Pacific oyster and mussel and 0.1 Mrad for hard clam. By irradiating at the optimum dose, the storage life of Pacific oyster could be extended from less than 14 days to 35 days at 00C and from only 3 days to 21 days at 50C. A similar storage extension was observed from 7 days to 14 days at 00C and from 3 days to 12 days at 50C. The hard clam meats were particularly susceptible to tissue softening by irradiation; an earlier onset and more extensive softening were observed with increasing dose. (author)

  14. Gamma Irradiation of Polyesters Film

    International Nuclear Information System (INIS)

    Experimental investigations on the effects of gamma irradiation in air of aromatic polyesters are carried out, in order to evaluate the influence of aromatic density and the role of oxygen on the radiation resistance. The thermoplastic polyesters PolyEthyleneTerephthalate (PET), PolyButylene Terephthalate (PBT), PolyEthyleneNaphthalate (PEN), Poly1,4-cyclohexanedimethylen terephthalate-co-ethyleneterephthalate (PCT-co-ET) are moulded in thin films of 50 micron and irradiated at different absorbed doses, ranging from 0 to 1000 kGy, using a Co-60 gamma source. The structural changes in the polymers are studied by means of several physical-chemical and nuclear techniques. Electron Paramagnetic Resonance analyses are carried out to detect the radicals induced by irradiation and to follow their decay by oxygen permeation. Viscometric measurements show a similar trend for the different irradiated polyesters: in particular, chain scission induced by irradiation depends on the aromatic density contained in the polymer and shows a saturation effect at the highest doses. Positron Annihilation Lifetime Spectroscopy points out a decrease of the ortho-positronium signal caused by the production of oxidized species inhibiting the positronium formation. Finally, the experimental results obtained on the irradiated films are compared with previous studies carried out on the same polyesters moulded in sheets of 1-2 mm of thickness and γ-irradiated at the same adsorbed doses

  15. Gamma-irradiation of tomatoes

    International Nuclear Information System (INIS)

    The influence of gamma-ray on tomatoes picked in a pink-red ripening stage, good for consumption, is studied. For that purpose tomatoes of ''Pioneer 2'' variety packed in perforated 500 g plastic bags were irradiated on a gamma device (Cobalt-60) at a dose power of 1900 rad/min with doses 200 or 300 krad. Samples were stored after irradiation at room temperature (20 - 22sup(o)C). Microbiological studies demonstrated that 44 resp. 99.96 per cent of the initial number of microorganisms was destroyed after irradiation with 200 resp. 300 krad. The time required for the number of microorganisms to be restored was accordingly increased. Irradiation delayed tomato ripening by 4 to 6 days, demonstrable by the reduced content of the basic staining substances - carotene and licopine. Immediately after irradiation the ascorbic acid content was reduced by an average of 13 per cent. After 18 days the amount of ascorbic acid in irradiated tomatoes was increased to a higher than the starting level, this is attributed to reductone formation during irradiation. The elevated total sugar content shown to be invert sugar was due to further tomato ripening. (Ch.K.)

  16. Method of detecting irradiated pepper

    International Nuclear Information System (INIS)

    Spices represented by pepper are generally contaminated by microorganisms, and for using them as foodstuffs, some sterilizing treatment is indispensable. However, heating is not suitable to spices, accordingly ethylene oxide gas sterilization has been inevitably carried out, but its carcinogenic property is a problem. Food irradiation is the technology for killing microorganisms and noxious insects which cause the rotting and spoiling of foods and preventing the germination, which is an energy-conserving method without the fear of residual chemicals, therefore, it is most suitable to the sterilization of spices. In the irradiation of lower than 10 kGy, the toxicity test is not required for any food, and the irradiation of spices is permitted in 20 countries. However, in order to establish the international distribution organization for irradiated foods, the PR to consumers and the development of the means of detecting irradiation are the important subjects. The authors used pepper, and examined whether the hydrogen generated by irradiation remains in seeds and it can be detected or not. The experimental method and the results are reported. From the samples without irradiation, hydrogen was scarcely detected. The quantity of hydrogen generated was proportional to dose. The measuring instrument is only a gas chromatograph. (K.I.)

  17. Nanoindentation on ion irradiated steels

    International Nuclear Information System (INIS)

    Radiation induced mechanical property changes can cause major difficulties in designing systems operating in a radiation environment. Investigating these mechanical property changes in an irradiation environment is a costly and time consuming activity. Ion beam accelerator experiments have the advantage of allowing relatively fast and inexpensive materials irradiations without activating the sample but do in general not allow large beam penetration depth into the sample. In this study, the ferritic/martensitic steel HT-9 was processed and heat treated to produce one specimen with a large grained ferritic microstructure and further heat treated to form a second specimen with a fine tempered martensitic lath structure and exposed to an ion beam and tested after irradiation using nanoindentation to investigate the irradiation induced changes in mechanical properties. It is shown that the HT-9 in the ferritic heat treatment is more susceptible to irradiation hardening than HT-9 after the tempered martensitic heat treatment. Also at an irradiation temperature above 550 deg. C no detectable hardness increase due to irradiation was detected. The results are also compared to data from the literature gained from the fast flux test facility.

  18. Microbiological Principles in Food Irradiation

    International Nuclear Information System (INIS)

    This paper reviews the important microbiological objectives of irradiation treatments, with special reference to the definitions of the proposed new terms, radappertization, radicidation and radurization. Emphasis is placed on the nature of the food in determining the microbiological requirements of the irradiation treatment. It is suggested that, just as with heat-processed foods, classifications into the major groups of ''acid'' or ''cured'' foods will remain valid with the irradiation process, and that different microbiological criteria will apply to these different classes of foods. The differences depend in part on the influence which the nature of the food has on the effectiveness of the irradiation treatment itself, but more especially on the way in which the nature of the food affects the activities of those microorganisms which might survive irradiation. The principles used to calculate the appropriate doses of radiation are discussed, with comments on the reliability of the fundamental assumptions or the need for further experimentation. The microbiological characteristics of irradiated foods are compared with those of corresponding heat- processed foods, to emphasize points of difference, with special reference to the appropriateness of suggested classifications for heat-processed foods. Finally, some general difficulties are considered, such as uncertainty about the significance and behaviour of food-borne viruses, and about the significance of the mutations which might conceivably be induced in microorganisms surviving-an irradiation process. (author)

  19. Detection of some irradiated foods

    International Nuclear Information System (INIS)

    This study was performed to investigate the possibility of using two rapid methods namely Supercritical Fluid Extraction (SFE) and Direct Solvent Extraction (DSE) methods for extraction and isolation of 2-dodecylcyclobutanone (2-DCB) followed by detecting this chemical marker by Gas chromatography technique and used this marker for identification of irradiated some foods containing fat (beef meat, chicken, camembert cheese and avocado) post irradiation, during cold and frozen storage. Consequently, this investigation was designed to study the following main points:- 1- The possibility of applying SFE-GC and DSE-GC rapid methods for the detection of 2-DCB from irradiated food containing fat (beef meat, chicken, camembert cheese and avocado fruits) under investigation.2-Studies the effect of gamma irradiation doses on the concentration of 2-DCB chemical marker post irradiation and during frozen storage at -18 degree C of chicken and beef meats for 12 months.3-Studies the effect of gamma irradiation doses on the concentration of 2-DCB chemical marker post irradiation and during cold storage at 4±1 degree C of camembert cheese and avocado fruits for 20 days.

  20. Irradiation's potential for preserving food

    International Nuclear Information System (INIS)

    The first experimental studies on the use of ionizing radiation for the preservation of foods were published over thirty years ago (1, 2) . After a period of high expectations and perhaps exaggerated optimism a series of disappointments occurred in the late '60s .The first company specifically created to operate a food irradiation plant, Newfield Products Inc, ran into financial difficulties and had to close its potato irradiation facility in 1966. The irradiator, designed to process 15,000t of potatoes per month for inhibition of sprouting, was in operation during one season only. In 1968 the US Food an Drug Administration refused approval for radiation-sterilisation of ham and withdrew the approval it had granted in 1963 for irradiated bacon. An International Project on the Irradiation of Fruit and Fruit juices, created in 1965 at Seibersdorf, Austria, with the collaboration or 9 countries, ended with general disappointment after three years. The first commercial grain irradiator, built in the Turkish harbour town of Iskenderun by the International Atomic Energy Agency with funds from the United Nations Development Program, never received the necessary operating licence from the Turkish Government and had to be dismantled in 1968. The US Atomic Energy Commission terminated its financial support to all research programmes on food irradiation in 1970. For a number of years, little chance seemed to remain that the new process would ever be practically used. However, research and development work was continued in a number of laboratories all over the world, and it appears that the temporary setbacks now have been overcome. Growing quantities of irradiated foods are being marketed in several countries and indications are that irradiated foods will eventually be as generally accepted as are frozen, dried or heatsterilised foods

  1. Pork fat peroxidation by gamma-irradiation

    International Nuclear Information System (INIS)

    In this paper, pork fat peroxidation by γ-irradiation and the possible effects of oxygen, UV-irradiation and storage after the γ-irradiation have been investigated. It has been found that the level of peroxides in irradiated pork increases linearly with the increasing absorbed dose. The chemical yield of peroxides formed in the irradiated fat is about 4.2 and independent on the sample temperature or absorbed dose rate, but dependent on storage time of sample before γ-irradiation. The irradiated pork exhibits some unusual features as following: 1) the peroxide content in irradiated pork is higher than that in unirradiated one; 2) the peroxide content in irradiated pork increases gradually on storage and is essentially constant in unirradiated one, which is very useful for the detection of irradiated pork; 3) the further peroxidation in irradiated pork is much more susceptible to UV radiation than that in unirradiated pork

  2. Facts about food irradiation: Irradiation and food additives and residues

    International Nuclear Information System (INIS)

    This fact sheet considers the issue of the irradiation of food containing food additives or pesticide residues. The conclusion is that there is no health hazard posed by radiolytic products of pesticides or food additives. 1 ref

  3. New facility for post irradiation examination of neutron irradiated beryllium

    Energy Technology Data Exchange (ETDEWEB)

    Ishitsuka, Etsuo; Kawamura, Hiroshi [Oarai Research Establishment, Ibaraki-Ken (Japan)

    1995-09-01

    Beryllium is expected as a neutron multiplier and plasma facing materials in the fusion reactor, and the neutron irradiation data on properties of beryllium up to 800{degrees}C need for the engineering design. The acquisition of data on the tritium behavior, swelling, thermal and mechanical properties are first priority in ITER design. Facility for the post irradiation examination of neutron irradiated beryllium was constructed in the hot laboratory of Japan Materials Testing Reactor to get the engineering design data mentioned above. This facility consist of the four glove boxes, dry air supplier, tritium monitoring and removal system, storage box of neutron irradiated samples. Beryllium handling are restricted by the amount of tritium;7.4 GBq/day and {sup 60}Co;7.4 MBq/day.

  4. Irradiation a boon to farmers

    International Nuclear Information System (INIS)

    Irradiation sterilization is emerging as a process of tremendous value to the food marketing industry. Much of the latest research has been done by the Atomic Energy Board at Pelindaba, using the strong gamma rays produced by cobalt-60 to kill the pathogens, microprobes, small insects and other food destroying agents usually found in food and fruit. Irradiation also helps delay ripening and ageing to a slight degree, a property of great value to food and fruit exporters. The advantages of various irradiated food are shortly discussed

  5. Irradiation services for crops improvement

    International Nuclear Information System (INIS)

    As an effort to pioneer and promote the use of nuclear technology in plant breeding in Malaysia, MINT has developed the procedures, methodology and service for the irradiation of ornamental plants, food and industrial crops. This paper discusses the issues related to the irradiation services for plant samples for the period of 15 years since the service was started. The main issues include the procedures for sample irradiation, statistics for the services that have been provided, problems and the solutions in providing the services. (Author)

  6. Nutritional Value of Irradiated Potatoes

    International Nuclear Information System (INIS)

    Rats received dried potatoes, irradiated with 10 krad, in an amount of 72% of the diet. Control groups received the same amount of non-irradiated potatoes. The experiment began on 7 May 1965 and is still running. To date, there is no difference between the groups fed with irradiated potatoes and the controls as far as weight gain and protein efficiency are concerned. Another experiment has been running for 12 weeks under the same conditions, except that the radiation dose was 100 krad. Here, too, no difference to the control groups can be observed. (author)

  7. International status of food irradiation

    International Nuclear Information System (INIS)

    Recent international moves that are likely to result in an increasing acceptance of irradiated foods are reviewed. Particular attention is given to the activities of the FAO, WHO, Codex Alimentarius and to attitudes in the United States and the Asian-Pacific region. In 1979, the Codex Alimentarius Commission adopted a Recommended General Standard for Irradiated Food. A resume is given of a revised version of the standard that is presently under consideration. However, remaining barriers to trade in irradiated food are briefly discussed, such as legal and regulatory problems, labelling, public acceptance and economic viability

  8. AFIP-4 Irradiation Summary Report

    International Nuclear Information System (INIS)

    The Advanced Test Reactor (ATR) Full size plate In center flux trap Position (AFIP) experiment AFIP-4 was designed to evaluate the performance of monolithic uranium-molybdenum (U-Mo) fuels at a scale prototypic of research reactor fuel plates. The AFIP-4 test further examine the fuel/clad interface and its behavior under extreme conditions. After irradiation, fission gas retention measurements will be performed during post irradiation (PIE). The following report summarizes the life of the AFIP-4 experiment through end of irradiation, including a brief description of the safety analysis, as-run neutronic analysis results, hydraulic testing results, and thermal analysis results.

  9. Methodology for RPV steels irradiations

    International Nuclear Information System (INIS)

    As a result of the popularity of the Agencies report 'Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels' of 1975, it was decided that another report on this broad subject would be of use. In this report, background and contemporary views on specially identified areas of the subject are considered as self-contained chapters, written by experts. The methodology for reactor pressure vessel (RPV) steels irradiations is elaborated. Irradiation in a materials test reactor and surveillance of the state of embrittlement in 'typical' plant specific materials are considered

  10. Food irradiation, profits and limitations

    International Nuclear Information System (INIS)

    The utility of the irradiation to overcome diverse problems of lost nutritious, it has been demonstrated in multiple investigation works, that its have confirmed the value and the inoculation of the irradiated foods. The quantity of energy applied to each food, is in function of the wanted effect. In this document a guide with respect to the practical application and the utility of the irradiation process in different foods, as well as the suggested dose average is shown. Among the limitations of the use of this technology, its are the costs and not being able to apply it to some fresh foods. (Author)

  11. Food irradiation dispelling the doubts

    International Nuclear Information System (INIS)

    Irradiation processing of the food item eliminates the use of harmful chemicals for treatment of food items and the produce can be conserved fresh. Another important aspect of this process is that it can help to stabilize the prices and give better remuneration to the farmer and hygienic product to the consumer. The already growing Indian nuclear industry can provide the source as well as the pros and cons of food technology for installation of irradiation facilities. The pros and cons of irradiation process are described. (M.K.V.)

  12. Growing acceptance of food irradiation

    International Nuclear Information System (INIS)

    In the table are listed food products treated by irradiation which have been cleared for human consumption in a number of Member States of the Agency. The details are based on information up to 1 February 1968. Two words already known to food experts investigating nuclear techniques for preserving food and preventing wastage but perhaps unfamiliar as yet to others, appear in the table. They are radappertization and radurization. The first means sterilization by irradiation and the second extension of market life, also by irradiation. (author)

  13. Therapeutic postprostatectomy irradiation.

    Science.gov (United States)

    Youssef, Emad; Forman, Jeffrey D; Tekyi-Mensah, Samuel; Bolton, Susan; Hart, Kim

    2002-06-01

    The purpose of this study was to determine the outcome of patients receiving external beam radiation for an elevated postprostatectomy prostate-specific antigen (PSA) level. Between December 1991 and September 1998, 108 patients received definitive radiation therapy for elevated postprostatectomy PSA levels. The median dose of irradiation was 68 Gy (range, 48-74 Gy). During treatment, the PSA levels were checked an average of 5 times (range, 3-7 times). Prostate-specific antigen values were judged to decline or increase during treatment if they changed by more than 0.2 ng/mL. After treatment, biochemical failure was defined as a measurable or rising PSA > 0.2 ng/mL. Median follow-up was 51 months (range, 3-112 months). Fifty-eight patients (54%) had evidence of biochemical failure. The 3- and 5-year actuarial biochemical relapse-free (bNED) survivals for all patients were 55% and 39%, respectively. Upon univariate analysis, intratreatment PSA and preradiation PSA were significant predictors of bNED survival. Patients with a PSA level that decreased during treatment had a 5-year bNED survival of 43% compared to 10% in patients with an increasing PSA level (P = 0.0002). Using the preradiation therapy PSA value as a continuous variable, higher preradiation therapy PSA levels were associated with an increased risk of failure (P = 0.004). Cut points of pretreatment PSA were derived at 0.9 ng/mL and 4.2 ng/mL using the Michael Leblanc recursive partitioning algorithm. The 5-year bNED rate for patients with a preradiation therapy PSA or = 4.2 ng/mL (P = 0.0003). Patients with a Gleason score of 7 (P = 0.27). Other factors examined individually that did not reach statistical significance included time from surgery to radiation therapy, race, seminal vesicle involvement, pathological stage, surgical margin, and perineural invasion. Upon multivariate analysis, only preradiation therapy PSA (P < 0.001) and the PSA trend during radiation therapy (P < 0.001) were significant

  14. Étude des anomalies chromosomiques après radiothérapie chez des patients traités pour lymphome malin non-Hodgkinien

    Science.gov (United States)

    Mahe, M. A.; André, M. J.; Moyon, E.; Le Mevel, A.; Soubeyran, P.; Hamidou, M.; Milpied, N.; Bourdin, S.; Cuillière, J. C.; Chatal, J. F.

    1998-04-01

    Structural chromosome defects were evaluated in the lymphocytes of 30 patients (pts) who had undergone radiotherapy for non Hodgkin's lymphoma (NHL). Twelve had received 20 Grays (Gy) over the abdomen (group I), 12 whole body irradiation at 1.5 Gy (group II) and 6 whole body irradiation at 15 Gy (group III). A cohort of 468 unirradiated pts served as controls. For the irradiated group, 7% of cells had aberrations compared to 0.4% in controls {P statistically higher in group I (12%) than in group II (3.5%) and III (2.5%) . In group I, frequency of aberrations was statistically higher in pts who had additionnal extra-abdominal involved field irradiation, those with evolutive NHL and those receiving chemotherapy at the time of the cytogenetic analysis. Les aberrations chromosomiques ont ,été, mesurées sur les lymphocytes de 30 patients (pts) irradiés pour lymphome malin non-hodgkinien (LNH) selon 3 modalités : 20 Grays (Gy) sur l'abdomen (groupe I : 12 pts), Irradiation corporelle totale 1,5 Gy (groupe II : 12 pts), ou 15 Gy (groupe III : 6 pts). Une population non irradiée de 468 pts a servi de témoin. Dans le groupe irradié, 7 % des cellules présentaient des anomalies contre 0,4 % dans le groupe témoin {P <10-6}. Les aberrations ,étaient statistiquement plus nombreuses dans le groupe I (12 % des cellules) que dans les groupes II (3,5 %) et III (2,5 %). Dans le groupe I, les anomalies , étaient statistiquement plus fréquentes chez les pts ayant eu une irradiation localisée extra-abdominale en complément de celle de l'abdomen ainsi que chez ceux en rechute de leur LNH et ceux recevant une chimiothérapie lors de l',étude cytogénétique.

  15. Currently developing opportunities in food irradiation and modern irradiation facilities

    International Nuclear Information System (INIS)

    I. Factor currently influencing advancing opportunities for food irradiation include: heightened incidence and awareness of food borne illnesses and causes. Concerns about ensuring food safety in international as well as domestic trade. Regulatory actions regarding commonly used fumigants/pesticides e.g. Me Br. II. Modern irradiator design: the SteriGenics Mini Cell. A new design for new opportunities. Faster installation of facility. Operationally and space efficient. Provides local onsite control. Red meat: a currently developing opportunity. (Author)

  16. Facts about food irradiation: Safety of irradiation facilities

    International Nuclear Information System (INIS)

    This fact sheet considers the safety of industrial irradiation facilities. Although there have been accidents, none of them has endangered public health or environmental safety, and the radiation processing industry is considered to have a very good safety record. Gamma irradiators do not produce radioactive waste, and the radiation sources at the facilities cannot explode nor in any other way release radioactivity into the environment. 3 refs

  17. Impaired epithelial differentiation of induced pluripotent stem cells from ectodermal dysplasia-related patients is rescued by the small compound APR-246/PRIMA-1MET.

    Science.gov (United States)

    Shalom-Feuerstein, Ruby; Serror, Laura; Aberdam, Edith; Müller, Franz-Josef; van Bokhoven, Hans; Wiman, Klas G; Zhou, Huiqing; Aberdam, Daniel; Petit, Isabelle

    2013-02-01

    Ectodermal dysplasia is a group of congenital syndromes affecting a variety of ectodermal derivatives. Among them, ectrodactyly, ectodermal dysplasia, and cleft lip/palate (EEC) syndrome is caused by single point mutations in the p63 gene, which controls epidermal development and homeostasis. Phenotypic defects of the EEC syndrome include skin defects and limbal stem-cell deficiency. In this study, we designed a unique cellular model that recapitulated major embryonic defects related to EEC. Fibroblasts from healthy donors and EEC patients carrying two different point mutations in the DNA binding domain of p63 were reprogrammed into induced pluripotent stem cell (iPSC) lines. EEC-iPSC from both patients showed early ectodermal commitment into K18(+) cells but failed to further differentiate into K14(+) cells (epidermis/limbus) or K3/K12(+) cells (corneal epithelium). APR-246 (PRIMA-1(MET)), a small compound that restores functionality of mutant p53 in human tumor cells, could revert corneal epithelial lineage commitment and reinstate a normal p63-related signaling pathway. This study illustrates the relevance of iPSC for p63 related disorders and paves the way for future therapy of EEC. PMID:23355677

  18. Development of a New Condensation Heat Transfer Model for the Nearly Horizontal Tube of the APR+ PAFS (Passive Auxiliary Feed-water System)

    International Nuclear Information System (INIS)

    Korea Atomic Energy Research Institute (KAERI) has recently conducted PASCAL experiment to confirm the performance of PAFS. From the work, it is founded that the condensation heat transfer coefficient predicted by best estimated safety analysis code MARS (Multi-dimensional Analysis of Reactor Safety) was underestimated compared to the experimental data. Shah correlation embedded in MARS code is the typical model using the empirical two-phase multiplier to determine condensation heat transfer coefficient for annular flow in the condensing tube. On the other hand, the PASCAL experiment indicated that a stratified-wavy flow generally tends to occur in the downward inclined tube of the condensation heat exchanger. Therefore, in order to improve the prediction capability of safety analysis codes for PAFS, the present study has proposed a new condensation heat transfer model package for the nearly horizontal tube, which determines mechanistically the local heat transfer coefficient based on the flow regimes. To enhance prediction capability of one-dimensional best estimated code MARS for the PAFS of the Korean 3.5 generation nuclear power plant APR+, a new condensation heat transfer model package has been developed. The model package consists of the one-dimensional separated model for the void fraction, a flow regime model based on wetted angle, and the condensation heat transfer correlations. The model package considers the inclination angle of the condensing tube and various flow regimes that are expected in the tube during condensation process

  19. Coseismic Dip Slip Distribution of the 1 Apr 2007 Solomon Islands Mw8.1 Earthquake from a Fully Bayesian Inversion

    Science.gov (United States)

    Chen, T.

    2009-12-01

    102 uplift and subsidence measurements over the southeastern end of the rupture zone from two field surveys shortly after 1 Apr 2007 Solomon Islands Earthquake provide a unique geodetic constraint in the following inversion of distributed slip. In the conventional inversion of geodetic data for spatial distribution of fault slip the solution is maintained by minimizing the second-order spatial derivative of slip and the smoothing parameter is often selected subjectively at the bend of the trade-off curve of misfit as a function of slip roughness. A fully Bayesian slip inversion method[Fukuda et al.,2008] is used to overcome the deficiency of selecting the smoothing parameter subjectively. The smoothing parameter is estimated with the distributed slip at the same time under a unified theoretical Bayesian framework. The joint posterior probability density function of distributed slip and smoothing parameter is formulated using Bayes’ theorem and sampled with Markov chain Monte Carlo method. I will apply this method to coseismic slip distribution associated with the 2007 Mw8.1 Solomon Islands earthquake and compare the results of this method with conventional method and the coseismic finite fault model of Furlong et al.[2009].

  20. Numerical Analysis of In-Vessel Retention using MARS-Ga for APR1400 under the Ga-based External Reactor Vessel Cooling

    International Nuclear Information System (INIS)

    To stabilize and terminate the severe accident through enhancing the coolability of the degraded core, this paper introduces an approach to avoid heat removal limit by replacing flooding material from the borated water to the liquid metal, gallium. The attractive properties such as the low melting point, high boiling point, and no reaction with water ensure that gallium can play an important role in nuclear safety as an alternative coolant in the gap between the vessel and the vessel insulation. The properties of liquid gallium compared to other materials are indicated. For the investigation on the effect of gallium for IVR-ERVCS, numerical simulation for severe accident in APR 1400 using MARS-LMR was performed. In this study, the numerical analysis of gallium-based IVR-ERVCS using MARS-LMR was performed. The range of temperature distribution in this system was considered as an important factor and then the possibility of ERVC using liquid gallium was confirmed. In addition, It will perform the sensitivity studies for the heat transfer area between liquid gallium and borated water to design the optimum ERVC using liquid gallium