Kozloduy NPP - its 20 years operational experience; AEhS `Kozloduy`: 20-letni opyt ehksploatatsii

Energy Technology Data Exchange (ETDEWEB)

Yankov, M; Grizanov, I; Sabinov, S [Kombinat Atomna Energetika, Kozloduj (Bulgaria)

1996-12-31

The main technical and economic results of 20 year operation of the Kozloduy NPP are summarised. The total electricity produced amounts to more than 200 billions KWh. The energy produced by the plant accounts for more than 40% of the national electricity output since 1993. Details of electricity production in different years by all 6 units are given. The efficiency of units 1-4 (WWER-440) is 29-30% and of units 5-6 (WWER-1000) is 29-33%. The Unit 6 has best characteristics. Since 1989 a safety test is being carried out in cooperation with the IAEA. Units 1 and 2 have been reconstructed in order to enhance safety and reliability. 1 tab.

In vivo pharmacodynamic and pharmacokinetic interactions of Hibiscus sabdariffa calyces extracts with simvastatin.

Science.gov (United States)

Showande, S J; Adegbolagun, O M; Igbinoba, S I; Fakeye, T O

2017-12-01

Increasing number of patients use herbs with their medications. Such practice may result in beneficial or harmful herb-drug interactions. A recent survey reported that some participants co-administered Hibiscus sabdariffa, a widely used beverage, or tea, with their antihyperlipidaemic medications. This study therefore evaluated the effect of concomitant administration of Hibiscus sabdariffa calyces' extracts with simvastatin on hyperlipidaemia and pharmacokinetics of the drug in vivo. Factorial experimental designs were used to evaluate the comparative effectiveness and interactions between simvastatin and aqueous extract of Hibiscus sabdariffa (AEHS) on lipid profile parameters in hyperlipidaemia-induced Wistar rats. Different combinations of low (AEHS 250 mg/kg; simvastatin 10 mg/kg) and high doses (AEHS 500 mg/kg; simvastatin 20 mg/kg) were administered individually and concurrently daily for 2 and 4 weeks. Lipid profile parameters were assessed at these treatment periods. Subsequently, the effect of aqueous beverage of Hibiscus sabdariffa (ABHS) on the pharmacokinetics of single-dose 40 mg simvastatin was also evaluated in six healthy human volunteers using two-period randomized crossover design. Blood samples were collected at predetermined times for 24 hours. The plasma obtained was analysed for simvastatin using RP-HPLC/UV method. Aqueous extract of Hibiscus sabdariffa reduced total cholesterol (T c ) better than simvastatin (P = .031). Low-dose AEHS and low-dose simvastatin used concomitantly caused 38.3% and 57.4% reductions in T c and triglyceride levels, respectively, compared with low-dose simvastatin (P Hibiscus sabdariffa lowered T c better than simvastatin and enhanced the antihyperlipidaemic activity of the drug when co-administered at low doses in an animal model. However, aqueous beverage of Hibiscus sabdariffa caused a significant herb-drug interaction resulting in overall reduction in exposure to simvastatin in humans. Caution should

Main research results in the field of nuclear power engineering of the Nuclear Reactors and Thermal Physics Institute in 2014

International Nuclear Information System (INIS)

Trufanov, A.A.; Orlov, Yu.I.; Sorokin, A.P.; Chernonog, V.L.

2015-01-01

The main results of scientific and technological activities for last years of the Nuclear Reactors and Thermal Physics Institute FSUE SSC RF - IPPE in solving problems of nuclear power engineering are presented. The work have been carried out on the following problems: justification of research and development solutions and safety of NPPs with fast reactors of new generation with sodium (BN-1200, MBIR) and lead (BREST-OD-300) coolants, justification of safety of operating and advanced NPPs with WWER reactor facilities (WWER-1000, AEhS 2006, WWER-TOI), development and benchmarking of computational codes, research and development support of Beloyarsk-3 (BN-600) and Bilibino (BN-800) NPPs operation, decommissioning of AM and BR-10 research reactors, pilot scientific studies (WWER-SKD, ITER), international scientific and technical cooperation. Problems for further investigations are charted [ru

Acetobacter turbidans α-Amino Acid Ester Hydrolase. How a Single Mutation Improves an Antibiotic-Producing Enzyme

NARCIS (Netherlands)

Barends, Thomas R.M.; Polderman-Tijmes, Jolanda J.; Jekel, Peter A.; Williams, Christopher; Wybenga, Gjalt; Janssen, Dick B.; Dijkstra, Bauke W.

2006-01-01

The α-amino acid ester hydrolase (AEH) from Acetobacter turbidans is a bacterial enzyme catalyzing the hydrolysis and synthesis of β-lactam antibiotics. The crystal structures of the native enzyme, both unliganded and in complex with the hydrolysis product D-phenylglycine are reported, as well as

Journal of Genetics | Indian Academy of Sciences

Indian Academy of Sciences (India)

Author Affiliations. Shin-Aeh Lee1 Seung-Gon Lee1 Kyoung-Oh Cho2 Changbaig Hyun1. Section of Internal Medicine, School of Veterinary Medicine, Kangwon National University, Chuncheon 200 701, Korea; Institute of Veterinary Medicine, College of Veterinary Medicine, Chonnam National University, Kwangju 500 757, ...

Promotion of a good safety culture at Ignalina RBMKs; Vnedrenie kul`tury bezopasnosti na Ignalinskoj AEhS

Energy Technology Data Exchange (ETDEWEB)

Shevaldin, V [Ignalina NPP, Visaginas (Lithuania)

1997-12-31

The presentation discusses the following issues: politics of Ignalina nuclear power plant in the area of safety and quality assurance; check of safety conditions; the activities of the Safety committee at the Ignalina NPP.

Influencia del tipo de hormigón y de acero, y de las características geométricas de la estructura, en los costes de materiales y en la superficie ocupada por los pilares en estructuras de edificios de hormigón armado con forjado unidireccional

Directory of Open Access Journals (Sweden)

Gómez Hermoso, J.

1999-12-01

Full Text Available The project and construction experience of building structures permit to affirm that greatest part of this structures usually are concrete frames with one way slab. This is the reason to develop this systematic study about the influence that concrete and steel used have in this structures. The aim is to give some criteria to geometric structure definition and the materials choice. We have calculated 80 structure buildings modified the height (small, intermediate and tall, with 5,12 and 20 tipical flats over ground, respectively, the concrete class (HI 75, H200, H250, H300, H400 y H500, the steel types (AEH400 and AEH500, the distance between columns (short and long, 5,00 and 6,00 m, respectively and the slab depth (24. 26 and 29 cm. When the calculation results were obtained (as shown on a set of tables and graphs, we made an analysis of materials cost (concrete and steel and the surface occupied for the columns.

La experiencia en el proyecto y ejecución de estructuras de edificación permite afirmar que, en un porcentaje muy elevado de ocasiones, se encuentran constituidas por pórticos de hormigón armado y forjados unidireccionales. Este hecho ha sido la causa fundamental que ha motivado el desarrollo de este estudio sistemático sobre la influencia que en estas estructuras puede tener el tipo de hormigón y acero utilizados, persiguiendo como objetivo final facilitar unos criterios para la definición geométrica de la estructura y la elección de materiales. Se ha procedido al cálculo de 80 edificios clasificados en función de la altura (bajo, medio y alto, con 5, 12 y 20 plantas tipo sobre rasante, respectivamente, el tipo de hormigón (H175, H200, H250, H300, H400 y H500, el tipo de acero (AEH400 y AEH500, la luz entre pilares (corta y larga, con 5,00 y 6,00 m, respectivamente y el canto del forjado (24, 26 y 29 cm, siendo la viga plana. Tras la obtención de los resultados (presentados en una serie de tablas y gráficos, se

Safety culture in an RBMK perspective; Sostoyanie i perspektivy razvitiya sistemy povysheniya kul`tury bezopasnosti AEhS Rossii

Energy Technology Data Exchange (ETDEWEB)

Porokhin, V G [Rosenergoatom, Moscow (Russian Federation)

1997-12-31

The presentation discusses the following issues: state and perspectives of the development of the system on Russia NPP safety culture enhancement; steps of Rosehnergoatom on development of system on Russia NPP Russia NPP safety culture enhancement, qualitative and quantitative evaluation of the safety culture, the nearest perspectives on safety culture enhancement in Russia.

Learning To Hope: A Study of the Adult Education for the Homeless Program.

Science.gov (United States)

Drury, Darrel; Koloski, Judy

A comprehensive study of the Adult Education for the Homeless Program (AEH) was conducted using data from the following sources: program files; focus groups conducted with state project administrators; site visits to 9 local programs in 3 states; surveys of 32 state projects, 230 local programs, 588 service delivery sites, and 2,943 program…

Nuclear power plants with reactors WWER-1000 type: today and tomorrow; AEhS s WWER-1000: nastoyashchee i budushchee

Energy Technology Data Exchange (ETDEWEB)

Molchanov, V; Biryukov, G; Novak, K [Opytno-Konstruktorskoe Byuro Gidropress, Podol` sk (Russian Federation)

1996-12-31

There are currently 19 NPP units based on WWER-1000 reactors working in Russia, Ukraine and Bulgaria. They are of four types: V-187, V-302, V-338, V-320. The design principles of these reactors comply with regulations of the eighties, and it is necessary to introduce improvements according to the new regulations and to the operation experience gained. Two approaches for safety and efficiency enhancement are described: AS-91 and AS-92. AS-91 implies gradual improvement of the base WWER-1000/V-320 design by incorporation of new design solutions avoiding the need of building large scale models. AS-92 refers to entirely new design which require experimental research by building a full scale models or by using natural stands. The latter approach will be used for NPP projects to be built after year 2000. The main new feature of AS-92 is the addition of passive safety systems to the active ones in order to protect the fuel from damage.

Malignant neoplasm rate in inhabitants of the Kozloduy NPP area; Zabolevaemost` zlokachestvennymi novoobrazovaniyami sredi naselenya v rajone AEhS `Kozloduy`

Energy Technology Data Exchange (ETDEWEB)

Dimitrov, P [National Centre of Radiobiology and Radiation Protection, Sofia (Bulgaria)

1996-12-31

Illness incidence of malignant formations in lungs, mammary gland, thyroid gland, lymph and blood producing tissues is investigated in the 30 km area around Kozloduy and compared to data from two other locations in Bulgaria. The number of malignant growth in the lungs, mammary or thyroid gland on 100 000 persons is lower than the average number for the country as a whole. The number of malignant formations in lymph and blood producing tissues is higher than the average number for the country but the difference is statistically insignificant. Thyroid gland diseases occur with very small frequency for the investigated period (1985-1990). 8 refs., 4 figs.

Structure of roofing cover for NPP reactor compartment in India. Ustrojstvo krovel'nogo pokrytiya reaktornogo otdeleniya AEhS v Indii

Energy Technology Data Exchange (ETDEWEB)

Movchan, S V

1990-04-01

Technology of fabrication of the roofing cover for NPP reactor compartments in India is briefly described. The cover is two-layer. The underlying thermal-hydroinsulating layer with the thickness of 100 mm is produced of beaten brick on lime-sand mortar. Facing layer of ceramic tile is applied to it.

Safety problems of nuclear power plants with reactors of new generation; Voprosy bezopasnosti v proehktakh AEhS novogo pokoleniya s WWER

Energy Technology Data Exchange (ETDEWEB)

Fedorov, V; Rogov, M; Biryukov, G [Opytno-Konstruktorskoe Byuro Gidropress, Podol` sk (Russian Federation)

1996-12-31

Modernization schemes for safety enhancement of WWER-1000 reactors are proposed. In the case of WWER-1000/V-392 it is based on introduction of additional safety systems and overall design improvement. For WWER-1100 (1000-1100 MW) the safety is enhanced by passive systems built from two-stage heat exchangers. For WWER-500/600 the use of passive safety system is extended to emergency cooling of the active zone and removal of the residual heat emissions from the reactor. The technical characteristics of the three reactors are compared. 3 figs., 1 tab.

Hibiscus sabdariffa L. and Its Bioactive Constituents Exhibit Antiviral Activity against HSV-2 and Anti-enzymatic Properties against Urease by an ESI-MS Based Assay.

Science.gov (United States)

Hassan, Sherif T S; Švajdlenka, Emil; Berchová-Bímová, Kateřina

2017-04-30

For decades, Hibiscus sabdariffa L. and its phytochemicals have been shown to possess a wide range of pharmacologic properties. In this study, aqueous extract of Hibiscus sabdariffa (AEHS) and its bioactive constituent protocatechuic acid (PCA), have been evaluated in vitro for their antiviral activity against HSV-2 clinical isolates and anti-enzymatic activity against urease. Antiherpetic activity was evaluated by the titer reduction assay in infected Vero cells, and cytotoxicity was evaluated by the neutral red dye-uptake method. Anti-urease activity was determined by a developed Electrospray Ionization-Mass Spectrometry (ESI-MS)-based assay. PCA showed potent anti-HSV-2 activity compared with that of acyclovir, with EC 50 values of 0.92 and 1.43 µg∙mL -1 , respectively, and selectivity indices > 217 and > 140, respectively. For the first time, AEHS was shown to exert anti-urease inhibition activity, with an IC 50 value of 82.4 µg∙mL -1 . This, combined with its safety, could facilitate its use in practical applications as a natural urease inhibitor. Our results present Hibiscus sabdariffa L. and its bioactive compound PCA as potential therapeutic agents in the treatment of HSV-2 infection and the treatment of diseases caused by urease-producing bacteria.

Hibiscus sabdariffa L. and Its Bioactive Constituents Exhibit Antiviral Activity against HSV-2 and Anti-enzymatic Properties against Urease by an ESI-MS Based Assay

Directory of Open Access Journals (Sweden)

Sherif T. S. Hassan

2017-04-01

Full Text Available For decades, Hibiscus sabdariffa L. and its phytochemicals have been shown to possess a wide range of pharmacologic properties. In this study, aqueous extract of Hibiscus sabdariffa (AEHS and its bioactive constituent protocatechuic acid (PCA, have been evaluated in vitro for their antiviral activity against HSV-2 clinical isolates and anti-enzymatic activity against urease. Antiherpetic activity was evaluated by the titer reduction assay in infected Vero cells, and cytotoxicity was evaluated by the neutral red dye-uptake method. Anti-urease activity was determined by a developed Electrospray Ionization-Mass Spectrometry (ESI-MS-based assay. PCA showed potent anti-HSV-2 activity compared with that of acyclovir, with EC50 values of 0.92 and 1.43 µg∙mL−1, respectively, and selectivity indices > 217 and > 140, respectively. For the first time, AEHS was shown to exert anti-urease inhibition activity, with an IC50 value of 82.4 µg∙mL−1. This, combined with its safety, could facilitate its use in practical applications as a natural urease inhibitor. Our results present Hibiscus sabdariffa L. and its bioactive compound PCA as potential therapeutic agents in the treatment of HSV-2 infection and the treatment of diseases caused by urease-producing bacteria.

Evaluation of jumbo squid (Dosidicus gigas byproduct hydrolysates obtained by acid-enzymatic hydrolysis and by autohydrolysis in practical diets for Pacific white shrimp (Litopenaeus vannamei

Directory of Open Access Journals (Sweden)

Mayra Lizett González-Félix

2014-09-01

Full Text Available The marine bioprocessing industry offers great potential to utilize byproducts for fish meal replacement in aquafeeds. Jumbo squid is an important fishery commodity in Mexico, but only the mantle is marketed. Head, fins, guts and tentacles are discarded in spite of being protein-rich byproducts. This study evaluated the use of two jumbo squid byproduct hydrolysates obtained by acid-enzymatic hydrolysis (AEH and by autohydrolysis (AH as ingredients in practical diets for shrimp. The hydrolysates were included at levels of 2.5 and 5.0% of the diet dry weight in four practical diets, including a control diet without hydrolysate. Shrimp growth and survival were not significantly affected by the dietary treatments. Postharvest quality of abdominal muscle was evaluated in terms of proximate composition and sensory evaluation. Significantly higher crude protein was observed in the muscle of shrimp fed the highest hydrolysate levels, AH 5% (204.8 g kg- 1 or AEH 5% (201.3 g kg- 1. Sensory analysis of cooked muscle showed significant differences for all variables evaluated: color, odor, flavor, and firmness. It was concluded that Jumbo squid byproducts can be successfully processed by autohydrolysis or acid-enzymatic hydrolysis, and that up to 5.0% of the hydrolysates can be incorporated into shrimp diets without affecting growth or survival.

Software Quality Measurement for Distributed Systems. Volume 3. Distributed Computing Systems: Impact on Software Quality.

Science.gov (United States)

1983-07-01

Distributed Computing Systems impact DrnwrR - aehR on Sotwar Quaity. PERFORMING 010. REPORT NUMBER 7. AUTNOW) S. CONTRACT OR GRANT "UMBER(*)IS ThomasY...C31 Application", "Space Systems Network", "Need for Distributed Database Management", and "Adaptive Routing". This is discussed in the last para ...data reduction, buffering, encryption, and error detection and correction functions. Examples of such data streams include imagery data, video

Trait differences between naturalized and invasive plant species independent of residence time and phylogeny

Science.gov (United States)

Gallagher, R V; Randall, R P; Leishman, M R

2015-01-01

inclusion of quantitative traits, in particular SLA, into the WRA schemes. Diferencia de Características entre Especies de Plantas Naturalizadas e Invasoras Independientes del Tiempo de Residencia y de la Filogenia Resumen La habilidad para predecir cuáles plantas exóticas harán la transición de naturalizadas a invasoras antes de su introducción a regiones nuevas es un objetivo clave para la conservación y tiene el potencial de incrementar la eficiencia de la evaluación de riesgo de hierbas (ERH). Sin embargo, múltiples factores contribuyen al éxito invasor de las plantas (p. ej.: características funcionales, características de cobertura, tiempo de residencia, filogenia) y todos deben considerarse simultáneamente para poder identificar correlaciones significativas del éxito invasor. Recopilamos en Australia 146 parejas de especies de plantas invasoras y naturalizadas emparejadas filogenéticamente (congéneres) y con tiempos de residencia mínima similares (es decir, el tiempo transcurrido desde su introducción en años). Estas parejas se usaron para probar diferencias en cinco características funcionales (duración de la floración, tamaño de la hoja, altura máxima, área específica de la hoja [AEH], masa de la semilla) y en tres características de cobertura nativa de las especies (ocupación de bioma, temperatura media anual y amplitud de pluviosidad) entre especies invasoras y naturalizadas. Las especies invasoras, en promedio, tuvieron una mayor AEH, periodos de floración más largos y fueron más altas que sus parientes congéneres naturalizadas. Las invasoras también exhibieron una mayor tolerancia a diferentes condiciones ambientales en su cobertura nativa, donde ocuparon más biomas y una mayor amplitud de pluviosidad y condiciones de temperatura que sus congéneres naturalizadas. Sin embargo, ni la masa de la semilla ni el tamaño de hoja difirieron entre las parejas de especies naturalizadas e invasoras. Un hallazgo relevante fue el papel de

Safety and upgrading of nuclear power plants with WWER-440/V-230; Voprosy bezopasnosti i modernizatsii AEhS s WWER-440 (V-230)

Energy Technology Data Exchange (ETDEWEB)

Melnikov, N [Opytno-Konstruktorskoe Byuro Gidropress, Podol` sk (Russian Federation)

1996-12-31

Modernization of WWER-440/V-230 reactors is considered according to the WANO project `Proposal for reconstruction of WWER-440/V-230 reactors` (1990). The main technical measures to be taken relate to: 1. Expanding the considered spectrum of design basis accidents; 2. Provision of first loop integrity; 3. Safety system structure and components reliability enhancement; 4. Reduction o initiating events probability; 5. Enhancement of hermeticity and integrity of the area surrounding the first loop; 6. Fire fighting system upgrade; 7. Radiation control system upgrade; 8. Provision of seismic resistance. Details of the recommended technical steps for some NPPs are presented. 1 tab.

On the effect of brazing thermal cycle on the properties of niobium and its alloys

International Nuclear Information System (INIS)

Grishin, V.L.; Cherkasov, A.F.

1975-01-01

The effect of the main parameters of the soldering thermal cycle on the properties of Nb and its alloys was studied by heating the samples under modelled conditions of soldering. The studies were made on commercial VN-niobium, alloys of the Nb-Mo-Zr system VN2A, VN2AEHM) and alloys of the Nb-Mo-Zr-C system (VN5AEH,VN5A). The degree of a preliminary plastic deformation of samples 0.3 to 0.8 mm thick made up 60 to 80%. The heating was made in vacuum (10 -4 to 5x10 -5 mm Hg) or in argon by passing the electric current across the samples. After heating a metallographic study and X-ray electron-probe analysis were made. The studies have shown that the changes in the heating rate result in a proportional change in the recrystallization initiation temperature. At a heating rate 300 deg C/s the recrystallization initiation temperature of commercial Nb is 930 to 960 deg as soon as the heating rate increases up to 900 deg/c the recrystallization initiation temperature rises up to about 1200 deg C. The heating temperature effect on the mechanical characteristics of commercial Nb and alloys VN2, VN2AEH and VN5AEH is shown. It is found that soldered joints of Nb and its alloys could be made of good quality when observing the thermal cycles ensuring the minimum softening of the base material. The main factors affecting the properties of Nb and alloy-VN2 are the heating temperature and the extent of a preliminary cold deformation. In a more deformed material the annealing results in the activation of the recrystallization processes. The production of high-strength soldered joints of commercial Nb is possible at the soldering temperature equal to 1100 deg C, but of Nb-Mo-Zr alloys-at 1200 to 1300 deg C and hold-up periods not exceeding one hour. A heterophase structure of alloys of the Nb-Mo-Zr-C system and the presence of Mo- and Zr-carbide phases in them result in a considerable hardening of the alloys and the increase in their recrystallization temperature. The usage of alloys

Some possible uses of radioisotopes in the rubber industry; Certaines possibilites d'emploi des radioisotopes dans l'industrie du caoutchouc; Nekotorye vozmozhnosti ispol'zovaniya radioaktivnykh izotopov v rezinovoj promyshlennosti; Algunas posibilidades de utilizacion de los radioisotopos en la industria del caucho

Energy Technology Data Exchange (ETDEWEB)

Shimorda, J; Mozhishek, M; Klimanek, L; Staroba, J [Nauchno-Issledovatel' skij Institut Tekhnologii Reziny i Plastmass (NIITRP), Gorod Gotval' dov, Chekhoslovatskaya Sotsialisticheskaya Respublika (Czech Republic)

1962-01-15

A method is described for using beta-emitters (Tl{sup 204} and S{sup 35}) for measuring the wearing qualities of motor-vehicle tyres, checking the homogeneity of tyre rubber, and non-contact thickness-gauging of rubberized fabrics. (author) [French] Le memoire expose une methode permettant d'employer des emetteurs beta ({sup 204}Tl et {sup 35}S) pour la mesure de la resistance des pneumatiques d'automobiles, le controle de l'uniformite du caoutchouc des pneus et la mesure sans contact de l'epaisseur des tissus caoutchoutes. (author) [Spanish] Los autores describen un metodo de utilizacion de emisores {beta} ({sup 204}Tl y {sup 35}S) para la medicion de la resistencia al desgaste de los neumaticos de automovil para la verificacion de la homogeneidad del caucho destinado a la fabricacion de neumaticos y para la medicion a distancia del espesor de las telas cauchutadas. (author) [Russian] Opisana metodika ispol'zovaniya beta-izluchatelej (Tl{sup 204} i S{sup 35}) dlya izmereniya velichiny iznosostojkosti avtomobil'nykh shin, dlya kontrolya gomogennosti shinnykh rezin i dlya beskontaktnogo izmereniya tolshchiny obrezinennykh tkanej. (author)

Indicadores económicos ganaderos de los sistemas agropecuarios extensivos del partido de Saavedra (Buenos Aires)

OpenAIRE

Gargano, Alfredo O.; Saldungaray, María C.; Chimeno, Patricia; Conti, Viviana P.; Adúriz, Miguel A.

2004-01-01

p.227-236 El objetivo fue determinar los resultados económicos ganaderos de los agrosistemas del partido de Saavedra (Buenos Aires) y compararlos con los de la agricultura. Se calcularon los ingresos netos (IN), costos directos (CD), márgenes brutos (MB) y la relación IN-CD. Los MB de los conglomerados, subsistemas ganaderos y estratos por superficie tuvieron mayor dependencia de los IN que de los CD. Los MB de los conglomerados, promedios de las áreas edáficas homogéneas (AEH), oscilaron ...

Cs 137 and Sr 90 content in the Kozloduy NPP environment; Soderzhanie 137Cs i 90Sr v obektakh okruzhayushchej sredy v rajone AEhS `Kozloduy`

Energy Technology Data Exchange (ETDEWEB)

Karaivanova, R; Totseva, R; Badulin, V; Zlatanova, R; Fajtondzhieva, K [National Centre of Radiobiology and Radiation Protection, Sofia (Bulgaria)

1996-12-31

The radioactivity status of soil and plant samples collected in the 12 km controlled zone surrounding Kozloduy has been investigated in the period 1990-1993. The average annual concentrations of Sr-90 and Cs-137 are compared to the values taken at 40 km distance. Cs-137 has in general higher concentrations in soil samples from the NPP close surroundings - e.g. 50-55 Bq/kg in 1992 versus 2-2.5 Bq/kg for Sr-90. Radionuclide concentrations in grass do not differ significantly from the data at 40 km distance. It is concluded that the average annual doses follow the radionuclide dynamics in the global fallout and the effect of Kozloduy operation can not be separated from the background radioactivity status. 4 refs., 21 figs.

Safety systems I/C reliability analysis of the Kozloduy NPP units 5 and 6; Analiz nadezhnosti KIP i sistem bezopasnosti pyatogo i shestogo bloka AEhS `Kozloduy`

Energy Technology Data Exchange (ETDEWEB)

Marinova, B [Risk Engineering Ltd., Sofia (Bulgaria)

1996-12-31

The purpose of the analysis is to assess the safety systems I/C equipment reliability of the Kozloduy-5 and the Kozloduy-6 reactors. The assessment of quantitative and qualitative effect of control systems unavailability on the safety systems unavailability is performed. The analysis is limited to the following systems: sprinkler management, low pressure emergency spray, emergency injection of boric acid, hydro accumulators, pressure compensator and compressed air. The code for probabilistic safety assessment PSAPACK has been used in analysis. Fault trees for all analysed safety systems have been constructed. Results indicates a high reliability of the safety systems management.

Nitrided steel 38CrN3MAFA for supporting elements in nuclear power plants; Vysokoazotistaya stal` tipa 38HN3MAFA dlya krepezhnikh detajlej reaktorov AEhS

Energy Technology Data Exchange (ETDEWEB)

Rasheva, I; Argirov, Kh; Stojchev, T [Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. po Metaloznanie i Tekhnologiya na Metalite

1996-12-31

Nitride doping of steel at different concentrations is achieved by counter-pressure casting in nitrogen ambience. A new type of steel is developed containing 0.05-0.2% N{sub 2}. It is compared to a standard 34NiCrMoV145 steel (DIN). The mechanical properties are improved significantly after a two-stage thermal treatment and are as follows: fluidity limit R{sub 0}.2>=1045 MPa, relative elongation A>=15%, relative shortening Z>=62%, impact viscosity KCU >= 1 MJ/m{sup 2}. The quench hardening consists of heating to 800-850{sup o} C in oil and cooling to 600{sup o} C in air. The steel is suitable for rotors, turbines, compressor shafts and reactor supporting elements in nuclear power plants. 3 refs., 6 figs., 6 tabs.

Kinetic parameters of nitridation of molybdenum and niobium alloys with various structure states

International Nuclear Information System (INIS)

Solodkin, G.A.; Bulgach, A.A.; Likhacheva, T.E.

1985-01-01

Effect of preliminary plastic strain under rolling on kinetic parameters of nitridation of VN-2AEh, VN-3 niobium alloys and molybdenum alloy with hafnium is investigated. Extreme character of dependence of kinetic parameters of nitridation on the degree of reduction under rolling is determined. Preliminary plastic strain at negligible reduction is shown to accelerate growth of the zone of internal nitridation and decelerates growth of the nitride zone. Nitrogen atom removal from the surface to the centre is retarded at the increase of the degree of reduction up to 50% and higher. The degree of deformations is the higher the lower nitridation temperature is

Quality control of repair of equipment for coal preparation plants. Upravlenie kachestvom remonta oborudovaniya ugleobogatitel'nykh fabrik

Energy Technology Data Exchange (ETDEWEB)

Okonishnikov, A I; Neskoromnykh, V M; Surzhenko, V S; Sirichenko, R P; Pavlyuchenko, S G; Lesikov, A V

1984-01-01

The Ukrniiugleobogashchenie, Kalininsk and Sukhodol'sk coal preparation plants have developed the SUKRO system for control of repair quality of coal preparation equipment in the USSR. The system is based on a system of standards used in coal preparation plants. The following systems of standards used by the SUKRO system are analyzed: organization standards (order of repair in a coal preparation plant, repair planning, spare part systems, methods for determining equipment wear, analysis of equipment failures), standards for maintenance and repair (methods for equipment maintenance, service life of each equipment component or system, structure of preventive repair or repair, organizational models of repair operations, lubrication systems), standards for assessment of labor quality during repair operations. Use of the SUKRO system in the Sukhodol'sk coal preparation plant is evaluated. The SUKRO forms a system of standards for repair and maintenance of equipment considering operation conditions in coal preparation plants, requirements for equipment reliability and service life. (4 refs.)

Experience in scientific guidance during start-up and normal operation of NPPs with WWER reactors; Opyt nauchnogo rukovodstva puskom i soprovozhdeniya pri ehkspluatatsii ehnergoblokov AEhS s WWER

Energy Technology Data Exchange (ETDEWEB)

Abagyan, A; Kazakov, V; Kryakvin, L [All-Russian Inst. for NPP Operation, Moscow (Russian Federation)

1996-12-31

The experience gained in the All-Russian Research Institute of NPP Operation (RU) in improvement of reactor start-up and normal operation of NPPs has been reported. The work was carried out on NPPs in Russia, Ukraine, Bulgaria, Hungary and Czechoslovakia. All scientific programmes applied use the system approach, modern methods of safety assessment and the principle of loss effect optimization. For the Kozloduy NPP the following projects have been implemented: design of accelerated unloading system for WWER-1000; refinement of water feeding unit for the WWER-1000 steam generator; response analysis of the safety anti-breakdown system of the second loop. The importance of technical substantiation in the process of decision making is stressed. 6 refs.

Weaving Together Space Biology and the Human Research Program: Selecting Crops and Manipulating Plant Physiology to Produce High Quality Food for ISS Astronauts

Science.gov (United States)

Massa, Gioia; Hummerick, Mary; Douglas, Grace; Wheeler, Raymond

2015-01-01

Researchers from the Human Research Program (HRP) have teamed up with plant biologists at KSC to explore the potential for plant growth and food production on the international space station (ISS) and future exploration missions. KSC Space Biology (SB) brings a history of plant and plant-microbial interaction research for station and for future bioregenerative life support systems. JSC HRP brings expertise in Advanced Food Technology (AFT), Advanced Environmental Health (AEH), and Behavioral Health and Performance (BHP). The Veggie plant growth hardware on the ISS is the platform that first drove these interactions. As we prepared for the VEG-01 validation test of Veggie, we engaged with BHP to explore questions that could be asked of the crew that would contribute both to plant and to behavioral health research. AFT, AEH and BHP stakeholders were engaged immediately after the return of the Veggie flight samples of space-grown lettuce, and this team worked with the JSC human medical offices to gain approvals for crew consumption of the lettuce on ISS. As we progressed with Veggie testing we began performing crop selection studies for Veggie that were initiated through AFT. These studies consisted of testing and down selecting leafy greens, dwarf tomatoes, and dwarf pepper crops based on characteristics of plant growth and nutritional levels evaluated at KSC, and organoleptic quality evaluated at JSCs Sensory Analysis lab. This work has led to a successful collaborative proposal to the International Life Sciences Research Announcement for a jointly funded HRP-SB investigation of the impacts of light quality and fertilizer on salad crop productivity, nutrition, and flavor in Veggie on the ISS. With this work, and potentially with other pending joint projects, we will continue the synergistic research that will advance the space biology knowledge base, help close gaps in the human research roadmap, and enable humans to venture out to Mars and beyond.

AEhLT-1-type image scanner for nuclear-physics and applied problems

International Nuclear Information System (INIS)

Shkundenkov, V.N.

1979-01-01

The design of the AELT-1 automatic scanner intended for measuring 35 mm photographs is presented. The photographs are scanned by the ''flying spot'' method, i.e. by transillumination of a photograph being measured and detection, with the help of a photomultiplier, of instants at which the CRT light spot meets different darkenings (nuclear particle tracks, etc.) available on it. On the CRT scope the light spot moves along lines the position (number) of which is controlled by a computer. Coordinates are measured by means of a special system of reference gratings on which with the aid of semitransparent mirrors a part of the CRT light is directed. Codes of the beginning and end of measured darkenings are fed to the computer for processing. In the process of scanning the computer controls the output signal discrimination level in the film channel. Based on the AELT-1 automatic scanner in JINR a system for processing photographs from a wide gap spark chamber during experiments aimed at studying the secondary electroproduction of pions is developed and put into operation in 1973. The tracks have a small length (1 mm), and the bulk of them has low contrast range. The capacity of the developed processing system is 70 thousand events per year for single shift operation

Concept of control and modifying systems of accelerator components; Kontseptsiya sistem avtomatizatsii kontrolya i upravleniya

Energy Technology Data Exchange (ETDEWEB)

Gudkov, K A; Chepurnov, A S; Shumakov, A V [NNIYaF MGU, Moskva (Russian Federation)

1996-12-31

Paper considers the main trends of development of automated control and monitoring systems of accelerator components. Application of communication ring structures will enable to design highly efficient object-oriented systems of automation of research and process components. 5 refs.

Influence of dose rate of ionizing radiation on working capacity of the oil-filled electrical equipment for NPP; Vliyanie moshchnosti dozy ioniziruyushchego oblucheniya na rabotosposobnost` maslonapolnennogo ehlektrooborudovaniya dlya AEhS

Energy Technology Data Exchange (ETDEWEB)

Tyutnev, A P [and others

1994-12-31

Dependence of radiation electric conductivity transformer oil on the gamma radiation absorbed dose rate and on the energy proton flux is investigated. It is ascertained that the electrical reliability of oil and oil-barrier insulation does not depend on the absorbed dose rate up to the maximum achieved values of 200 rad/s.

Study on radiation resistance of electro insulating materials used in high-voltage equipment at Chernobylsk NPP; Issledovanie radiatsionnoj stojkosti ehlektroizolyatsionnykh materialov, primenyaemykh v vytsfsokovol`tnom oborudovanii na Chernobyl`skoj AEhS

Energy Technology Data Exchange (ETDEWEB)

Lizunov, S D [and others

1994-12-31

Investigations into the radiation resistance of the transformer oil and electro insulating cardboard during emergency irradiation at the NPP in 1986 are conducted. It is shown that as a result of transformer oil irradiation it is decomposed with the release of hydrogen, ethane, ethylene, ethane and other gases.

Phase II study of medroxyprogesterone acetate plus metformin as a fertility-sparing treatment for atypical endometrial hyperplasia and endometrial cancer.

Science.gov (United States)

Mitsuhashi, A; Sato, Y; Kiyokawa, T; Koshizaka, M; Hanaoka, H; Shozu, M

2016-02-01

Metformin, widely used in the treatment of type 2 diabetes mellitus, reduces the risk of cancer and relapse after treatment. Fertility-sparing treatment for endometrial cancer (EC) with progestin is associated with a high chance of disease regression, and the high relapse rate continues to be a problem. We assessed the efficacy of metformin in preventing recurrence after medroxyprogesterone acetate (MPA) as fertility-sparing treatment for atypical endometrial hyperplasia (AEH) and EC. This phase II study enrolled 17 patients with AEH and 19 patients with EC limited to the endometrium (age, 20-40 years). MPA (400 mg/day) and metformin (750-2250 mg/day) were administered for 24-36 weeks to achieve a complete response (CR). Metformin was administered until conception, even after MPA discontinuation. The primary end point was relapse-free survival (RFS) after remission. We analyzed all efficacy end points in the full analysis set. The body mass index was ≥25 kg/m(2) in 27 patients (mean, 31 kg/m(2); range, 19-51 kg/m(2)), and the homeostasis model assessment for insulin resistance index was ≥2.5 in 24 patients (mean, 4.7; range, 0.7-21). Two patients showed progression at 12 weeks [6%; 95% confidence interval (CI) 2-18]. At 36 weeks, 29 (81%; 95% CI 65-90) patients achieved CR, and 5 (14%; 95% CI 6-29) patients achieved partial response. During a median follow-up of 38 months (range, 9-66 months) after remission, relapse was confirmed in three of the patients who had achieved CR (relapse rate, 10%). The 3-year estimated RFS rate was 89%. No patients experienced severe toxicity. Metformin inhibited disease relapse after MPA therapy. The combination of metformin and MPA in EC treatment should be studied further. UMIN 000002210. © The Author 2015. Published by Oxford University Press on behalf of the European Society for Medical Oncology. All rights reserved. For permissions, please email: journals.permissions@oup.com.

Human Research Program: Space Human Factors and Habitability Element

Science.gov (United States)

Russo, Dane M.

2007-01-01

The three project areas of the Space Human Factors and Habitability Element work together to achieve a working and living environment that will keep crews healthy, safe, and productive throughout all missions -- from Earth orbit to Mars expeditions. The Advanced Environmental Health (AEH) Project develops and evaluates advanced habitability systems and establishes requirements and health standards for exploration missions. The Space Human Factors Engineering (SHFE) Project s goal is to ensure a safe and productive environment for humans in space. With missions using new technologies at an ever-increasing rate, it is imperative that these advances enhance crew performance without increasing stress or risk. The ultimate goal of Advanced Food Technology (AFT) Project is to develop and deliver technologies for human centered spacecraft that will support crews on missions to the moon, Mars, and beyond.

Assessment of cellular responses to oxidative stress using MCF-7 breast cancer cells, black seed (N. Sativa L.) extracts and H2O2.

Science.gov (United States)

Farah, Ibrahim O

2005-12-01

Black seed (N. Sativa L) is an oriental spice of the family Ranunculaceae that has long been rationally used as a natural medicine for treatment of many acute as well as chronic conditions including cardiovascular disease and immunological disorders. It has been used in the treatment of diabetes, hypertension, and dermatological conditions. There have been very few studies on the effects of N. Sativa as a chemoprevention of chronic diseases as well as in cancer prevention and/or therapy. Oxidative stress is a condition that underlies many acute as well as chronic conditions. The combination and role of oxidative stress and antioxidants in vivo is still a matter of conjecture. Our objective for the present study was to expose MCF-7 breast cancer cells in vitro (as a chronic disease example) to aqueous and alcohol extracts and in combination with H[2]O[2] as an oxidative stressor. Measurement of cell survival under various concentrations and mixtures was conducted using standard cell culture techniques, exposure protocols in 96 well plates and Fluorospectrosphotometry. Following cellular growth to 90% confluencey, exposure to water (WE) and ethanol (AE) extracts of N. sativa and H[2]O[2] was performed. Cell survival indices were calculated from percent survival using regression analysis. Results showed that the alcohol extract and its mixtures were able to influence the survival of MCF-7 cells (indices ranged from 357.15- 809.50 mug/ml in descending potency for H[2]O[2]+AE to the mix of 3). In contrast, H[2]O[2] alone reduced effectively the survival of MCF-7 cells and the least effective combinations in descending potency were AE+H[2]O[2], WE+H[2]O[2], AE+WE, and WE+AE+H[2]O[2]. Mixtures other than AE+H[2]O[2] showed possible interactions and loss of potency. In conclusion, N. Sativa alone or in combination with oxidative stress was found to be effective (in vitro) in influencing the survival of MCF-7 breast cancer cells, unveiling promising opportunities in the

Assessment of Cellular Responses to Oxidative Stress using MCF-7 Breast Cancer Cells, Black Seed (N. Sativa L. Extracts and H2O2

Directory of Open Access Journals (Sweden)

Ibrahim O. Farah

2005-12-01

Full Text Available Black seed (N. Sativa L is an oriental spice of the family Ranunculaceae that has long been rationally used as a natural medicine for treatment of many acute as well as chronic conditions including cardiovascular disease and immunological disorders. It has been used in the treatment of diabetes, hypertension, and dermatological conditions. There have been very few studies on the effects of N. Sativa as a chemoprevention of chronic diseases as well as in cancer prevention and/or therapy. Oxidative stress is a condition that underlies many acute as well as chronic conditions. The combination and role of oxidative stress and antioxidants in vivo is still a matter of conjecture. Our objective for the present study was to expose MCF-7 breast cancer cells in vitro (as a chronic disease example to aqueous and alcohol extracts and in combination with H2O2 as an oxidative stressor. Measurement of cell survival under various concentrations and mixtures was conducted using standard cell culture techniques, exposure protocols in 96 well plates and Fluorospectrosphotometry. Following cellular growth to 90% confluencey, exposure to water (WE and ethanol (AE extracts of N. sativa and H2O2 was performed. Cell survival indices were calculated from percent survival using regression analysis. Results showed that the alcohol extract and its mixtures were able to influence the survival of MCF-7 cells (indices ranged from 357.15- 809.50 Bg/ml in descending potency for H2O2+AE to the mix of 3. In contrast, H2O2 alone reduced effectively the survival of MCF-7 cells and the least effective combinations in descending potency were AE+H2O2, WE+H2O2, AE+WE, and WE+AE+H2O2. Mixtures other than AE+H2O2 showed possible interactions and loss of potency. In conclusion, N. Sativa alone or in combination with oxidative stress was found to be effective (in vitro in influencing the survival of MCF-7 breast cancer cells, unveiling promising opportunities in the field of cancer

Mine alarm stations for mine haulage systems in coal surface mines. Stantsiya pozharnoi signalizatsii dlya gorno-transportnogo oborudovaniya ugol'nykh razrezov

Energy Technology Data Exchange (ETDEWEB)

Terebilo, N.I.; Bukhanets, B.N.; Rozhkov, V.L.; Martynenko, V.D. (Vsesoyuznyi Nauchno-Issledovatel' skii Institut Gornospasatel' nogo Dela, Donetsk (USSR))

1988-01-01

Describes design and operation of the STs fire alarm station developed by the Spetsavtomatika plant in Minsk and successfully tested in the Borodino surface coal mine. The station consists of 14 measuring circuits with the measuring cycle not longer than 4 s. The station detects fires at earthmoving and haulage equipment, cuts off energy supply to fire zones and activates fire extinguishing equipment. The station will be manufactured on a commercial scale. 2 refs.

Brincar no hospital: estratégia de enfrentamento da hospitalização infantil Playing in the hospital: coping strategy in child hospitalization

Directory of Open Access Journals (Sweden)

Alessandra Brunoro Motta

2004-04-01

Full Text Available Estudos indicam que a hospitalização pode afetar o desenvolvimento da criança, interferindo na qualidade de vida. Para lidar com essa situação, o brincar tem funcionado como estratégia de enfrentamento. Procurando-se avaliar a importância dada ao brincar pela criança e caracterizar atividades lúdicas possíveis no hospital, 28 crianças hospitalizadas com câncer (6-12 anos, em Vitória/ES, foram entrevistadas e responderam a um instrumento especialmente elaborado (AEH - Avaliação das Estratégias de Enfrentamento da Hospitalização - Conjunto B: Brincar no hospital, contendo 20 desenhos de brinquedos e brincadeiras, classificados em jogos de Exercícios, Simbólicos, de Acoplagem, de Regras e Atividades Diversas. 78,6% das crianças relataram que gostariam de brincar no hospital, o que é justificado principalmente pela sua função lúdica, na companhia de outras crianças internadas. Não houve diferenças significativas nas escolhas entre as categorias de brincadeiras. O instrumento mostrou que o brincar pode ser um recurso adequado para a adaptação da criança hospitalizada, permitindo personalizar a intervenção.Studies have shown that the hospitalization can affect a child development interfering with his/her quality of life. In order to deal with this situation, the act of playing has worked as a coping strategy. With the purpose to assess of the importance children give to play and to characterize possible playful activities in the hospital, 28 children hospitalized with cancer (6-12 years in Vitória, ES, were interviewed and took part on an instrument specially developed (AEH Evaluation of the Coping Strategies of the Hospitalization - group B: Playing in the hospital, consisting of 20 drawings of toys and games classified in games of Exercises, Symbolic Game, Game of Connection, Game of Rules and a variety of Activities. 78,6% of the children said that they would like playing in the hospital, which is justified mainly

Absolute Measurement of Radioactive Materials at the Physikalisch-Technische Bundesanstalt; Mesure absolue des substances radioactives a l'Institut federal de physique appliquee; Absolyutnoe izmerenie radioaktivnykh veshchestv v fiziko-tekhnicheskom federal'nom institute; Determinacion absoluta de la actividad de sustancias radiactivas en el Instituto Federal de Fisica Aplicada

Energy Technology Data Exchange (ETDEWEB)

Weiss, H M [Physikalisch-Technische Bundesanstalt, Braunschweig (Germany)

1960-06-15

A short report is given about the routine methods of standardization of radionuclides. The measurements are done by 4 {pi} {beta} proportional counters, 4 {pi} {beta}-{gamma} coincidence counting and for secondary standardization of {gamma} emitters by 4 {pi} {gamma} ionization chamber. The equipments used and the procedures of source preparation are described. (author) [French] L'auteur presente un rapport succinct sur les methodes courantes de normalisation des radionuclides. Les mesures sont effectuees au moyen de compteurs proportionnels 4 {pi} {beta}, par voie de comptage par coincidences 4 {pi}{beta}-{gamma} et, en ce qui concerne la normalisation secondaire des emetteurs de rayons {gamma}, au moyen d'une chambre d'ionisation 4 {pi} {gamma}. Le memoire contient une description du materiel utilise et des procedes employes pour la preparation des sources. (author) [Spanish] En la memoria se describen brevemente los metodos corrientes de calibracion de radionuclidos. Las mediciones a que se refiere se han efectuado con contadores proporcionales {beta} 4 {pi}, contadores de coincidencias {beta}-{gamma} 4{pi}l; para la calibracion secundaria de emisores {gamma} se ha utilizado una camara de ionizacion {gamma} 4 {pi}. Se describen los aparatos empleados y los procedimientos de preparacion de las fuentes. (author) [Russian] Privoditsya kratkij doklad po obychnym metodam standartizatsi i radioizotopov. Izmereniya osushchestvlyalis {beta}-proportsional'nym i schetchikami na 4 {pi}, schetchikami {beta}-{gamma} sovpadenij i {gamma}-ioniziruyushche j kameroj na 4 i dlya vtorichnoj standartizatsi i {gamma}-izluchatelej . Privoditsya opisanie, ispol'zuemogo oborudovaniya i protsedura podgotovki istochnika. (author)

Indicators of Chernobyl NPP personnel irradiation in 1986; Pokazateli obluchaemosti personala ChAEhS za 1986 g.

Energy Technology Data Exchange (ETDEWEB)

Vasil` chenko, V N; Nosovskij, A V; Il` ichev, S V; Snisar, I B [Virobniche Ob` jednannya Chernobil` s` ka AES, Chornobil` (Ukraine)

1996-12-31

The results of retrospective evaluation of ChNPP personnel irradiation during Chernobyl accident consequences mitigation are presented. Only occupational doses received within 30-km exclusion zone are considered.

Determination of P, Cu, Cr, Va and Ti in samples of welded joint No.4 of Kozloduy-1 reactor pressure vessel; Opredelenie soderzhanya fosfora, medi, nikelya, khroma, vanadya i titana v struzhkakh 4 shva 1 bloka AEhS `Kozloduy`

Energy Technology Data Exchange (ETDEWEB)

Taskaev, E [Kombinat Atomna Energetika, Kozloduj (Bulgaria); Penev, I; Taskaeva, M [Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika; Aleksieva, L [Sofia Univ. (Bulgaria); Tsokov, P [Kombinat Atomna Energetika, Kozloduj (Bulgaria)

1996-12-31

An analysis of reactor steel composition has been carried out in 1989 in order to determine metal embrittlement. The samples consist of shavings taken at 3-4 mm depth from the 4-th welded joint of Unit 1 of the Kozloduy NPP. The shavings have been gradually dissolved in a mixture of acids and the solution evaporated. Quantitative analysis has been carried out by spectrophotometry and by ICP emission spectroscopy. The following element concentrations have been found: P - from 0.0462 to 0.052% by weight; Ni - 0.25 - 0.26% (passport data 0.29%); Cr - 1.47 - 1.54 (passport 1.58%); V - 0.1% (passport 0.15%); Cu - 0.11-0.13% (passport 0.12); Ti - 0.002. The data have been used to calculate metal embrittlement. 4 refs., 8 tabs.

Common problems of acquisition of reference data on radiation reliability of structural electro insulating materials used in NPP electrical equipment; Obshchie voprosy polucheniya spravochnykh dannykh po radiatsionnoj nadezhnos ti konstruktsionnykh i ehlektroizolyatsionnykh materialov, ispol`zuemykh v ehlektrooborudovanii AEhS

Energy Technology Data Exchange (ETDEWEB)

Tyutnev, A P; Valeev, R S

1994-12-31

General principles of conducting accelerated radiation testings of electrotechnical products with regard to operation factors typical of NPPs are considered. Non-additivity of effect of these factors on the product and material parameters and parameter dependence on ionizing radiation dose rate are demonstrated.

Human Factors and Habitability Challenges for Mars Missions

Science.gov (United States)

Whitmore, Mihriban

2015-01-01

As NASA is planning to send humans deeper into space than ever before, adequate crew health and performance will be critical for mission success. Within the NASA Human Research Program (HRP), the Space Human Factors and Habitability (SHFH) team is responsible for characterizing the risks associated with human capabilities and limitations with respect to long-duration spaceflight, and for providing mitigations (e.g., guidelines, technologies, and tools) to promote safe, reliable and productive missions. SHFH research includes three domains: Advanced Environmental Health (AEH), Advanced Food Technology (AFT), and Space Human Factors Engineering (SHFE). The AEH portfolio focuses on understanding the risk of microbial contamination of the spacecraft and on the development of standards for exposure to potential toxins such as chemicals, bacteria, fungus, and lunar/Martian dust. The two risks that the environmental health project focuses on are adverse health effects due to changes in host-microbe interactions, and risks associated with exposure to dust in planetary surface habitats. This portfolio also proposes countermeasures to these risks by making recommendations that relate to requirements for environmental quality, foods, and crew health on spacecraft and space missions. The AFT portfolio focuses on reducing the mass, volume, and waste of the entire integrated food system to be used in exploration missions, and investigating processing methods to extend the shelf life of food items up to five years, while assuring that exploration crews will have nutritious and palatable foods. The portfolio also delivers improvements in both the food itself and the technologies for storing and preparing it. SHFE sponsors research to establish human factors and habitability standards and guidelines in five risk areas, and provides improved design concepts for advanced crew interfaces and habitability systems. These risk areas include: Incompatible vehicle/habitat design

Probabilistic safety analysis of the Kozloduy NPP units 1-4 (WWER-440/230) using independent emergency feedwater system; Veroyatnostnyj analiz bezopasnosti I-IV blokov AEhS `Kozloduy` s reaktorami tipa WWER-440 (V 230) pri vklyuchenii nezavisimoj sistemy avarijnoj podpitki PG

Energy Technology Data Exchange (ETDEWEB)

Kalchev, B; Marinov, M; Dimitrov, B; Avdzhiev, K [Energoproekt, Sofia (Bulgaria)

1996-12-31

The safety of the Kozloduy NPP is being promoted by backfitting and improved operational practice. Special measures mitigating potential severe accidents consequences are needed because of some deficiencies in the original design of the four WWER-440 units. In conditions of a total LOCA (Loss Of Coolant Accident) it is impossible to ensure decay heat removal using the existing safety system. In such cases an extra emergency feedwater system independent of the plant`s other systems has been introduced which offers a new alternative means of removing the residual heat from the reactor. A probabilistic safety analysis is carried out using the method of event trees. A comparison between the existing safety system and the newly proposed is made. The simulation results of the unit behaviour prove that the damage frequency of the active zone is lower with the new system. 3 refs., 3 tabs., 2 figs.

Developing reports on safety analysis and probabilistic analysis of safety for operating power units at nuclear power stations with WWER reactors in Russia; Razrabotka otchetov po analizu bezopasnosti i VAB dlya ehkspluatiruyushchikhsya ehnergoblokov AEhS s WWEhR v Rossii

Energy Technology Data Exchange (ETDEWEB)

Malyshev, A B; Morozov, V B [ATOMENERGOPROEKT Institute, Moscow (Russian Federation)

1999-06-01

Report presents the current state-of art in developing safety reports and probabilistic safety analyses for WWER NPPs operated in Russia. Development of these reports and implementation of PSA is done according to the requirements outlined in the basic document `General Statement on Ensuring safety (OPB). At present submitting safety reports to the regulatory authority GAN RF is mandatory for licensing NPPs. Current state of safety reports for the operating WWER type NPPs meets generally the effective Russian standard engineering documents which are approaching the international standards. A mechanism ensuring correspondence of the safety documentation to the current state of operating units is determined. Modernization of the operating units is underway, it is aimed to eliminate existing deviations from requirements of the modern standards in the field of NPP safety

Localized Failure Promoted by Heterogeneous Stresses in Tectonic Mélanges

Science.gov (United States)

Phillips, N. J.; Rowe, C. D.; Ujiie, K.

2017-12-01

Within the shallow (PLC) toolbox developed at the University of Maine, which uses Asymptotic Expansion Homogenization (AEH) over a finite element mesh to determine the instantaneous stress distributions in a multiphase system. We model the shale matrix mélange to be deforming through a modified flow law for viscous creep based on coupled frictional sliding and pressure solution, where at a strain rate of 10-12 s-1 the flow stress is 10 MPa under the temperature (190 ºC) and pressure ( 100 MPa) conditions during deformation, and describe the behaviour of the basaltic blocks using experimentally-derived power law flow laws. The results show that at the strain rates calculated based on plate-rate motion, differential stresses high enough to cause comminution of the basalts ( 300 MPa) correspond strongly to areas around the blocks with basalt derived cataclasites. Within the basalt derived cataclasites, thin zones of ultracataclasite record localized slip. We hypothesize that the heterogeneous stress distributions within subduction mélanges: 1) fractures the strong basalt thereby facilitating weakening through fluid-rock interactions, and 2) promotes localized slip (and occasionally seismicity) within these zones of altered basalt along the margins of strong intact basalt.

2013 Advanced Environmental Health/Advanced Food Technology Standing Review Panel Final Report

Science.gov (United States)

Steinberg, Susan

2014-01-01

The 2013 Advanced Environmental Health/Advanced Food Technology (AEH/AFT) Standing Review Panel (from here on referred to as the SRP) participated in a WebEx/teleconference with members of the Space Human Factors and Habitability (SHFH) Element, representatives from the Human Research Program (HRP), and NASA Headquarters on November 22, 2013 (list of participants is in Section IX of this report). The SRP reviewed the updated research plans for the Risk of Adverse Health Effects Due to Alterations in Host-Microorganism Interactions (Host Microbe Risk) and the Risk of Performance Decrement and Crew Illness Due to an Inadequate Food System (Food Risk). The SRP also received a status update on the Risk of Adverse Health Effects of Exposure to Dust and Volatiles during Exploration of Celestial Bodies (Dust Risk). Overall, the SRP was impressed with the strong research plans presented by the scientists and staff associated with the SHFH Element. The SRP also thought that the updated research plans were thorough, well organized, and presented in a comprehensive manner. The SRP agrees with the changes made to the Host Microbe Risk and Food Risk portfolios and thinks that the targets for Gap closure are appropriate.

Forensic applications of nitrogen and oxygen isotopes in tracing nitrate sources in urban environments

Science.gov (United States)

Silva, S.R.; Ging, P.B.; Lee, R.W.; Ebbert, J.C.; Tesoriero, A.J.; Inkpen, E.L.

2002-01-01

Ground and surface waters in urban areas are susceptible to nitrate contamination from septic systems, leaking sewer lines, and fertilizer applications. Source identification is a primary step toward a successful remediation plan in affected areas. In this respect, nitrogen and oxygen isotope ratios of nitrate, in conjunction with hydrologic data and water chemistry, have proven valuable in urban studies from Austin, Texas, and Tacoma, Washington. In Austin, stream water was sampled during stremflow and baseflow conditions to assess surface and subsurface sources of nitrate, respectively. In Tacoma, well waters were sampled in adjacent sewered and un-sewered areas to determine if locally high nitrate concentrations were caused by septic systems in the un-sewered areas. In both studies, sewage was identified as a nitrate source and mixing between sewage and other sources of nitrate was apparent. In addition to source identification, combined nitrogen and oxygen isotopes were important in determining the significance of denitrification, which can complicate source assessment by reducing nitrate concentrations and increasing ??15N values. The two studies illustrate the value of nitrogen and oxygen isotopes of nitrate for forensic applications in urban areas. ?? Published by Elsevier Science Ltd. on behalf of AEHS.

Physic status and working ability of the persons affected at the Chernobyl accident during recovery and short-term effects of acute radiation disease. Psikhicheskoe sostoyanie i trudosposobnost' postradavshikh pri avarii na Chernobyl'skoj AEhS v period vosstanovleniya i blizhajshikh posledstvij ostroj luchevoj bolezni

Energy Technology Data Exchange (ETDEWEB)

Torubarov, F S; Chinkina, O V [Institut Biofiziki, Moscow (USSR)

1991-01-01

Analysis of the results of clinicopsychological investigation of persons developing ARS (1-3 degree of severity) as a result of the Chernobyl accident has shown that 4-6 mos. after the exposure the psychic status and mental working ability of the affected persons showed close correlation with a degree of ARS. In 12-18 mos. profession and adequate employment played a decisive role in the formation of unfavorable psychic conditions and limited working ability. Later on in 2.5-3 years after exposure a decrease in psychic working ability, the development of unfavorable psychic conditions was noted more frequently in patients with ARS of more severe types and in examinees of older age. At all stages of rehabilitation personality traits of the affected persons play an important role in the revival of working abilities.

Proceedings of the second international scientific and practical conference 'Mitigation of the consequences of the catastrophe at the Chernobyl NPP: state and perspectives'; Materialy II mezhdunarodnoj nauchno-prakticheskoj konferentsii 'Preodolenie posledstvij katastrofy na Chernobyl'skoj AEhS: sostoyanie i perspektivy'simpoziuma 'Aktual'nye problemy dozimetrii'

Energy Technology Data Exchange (ETDEWEB)

Shevchuk, V E; Gurachevskij, V L; Kapitonova, Eh K [eds.

2004-04-01

The proceeding reflects new scientific results and contains three parts - medical consequences of the Chernobyl NPP accident and dose monitoring of human population; problems of the contaminated territories and social and economical development of the regions; radioecological and radiobiological consequences of the accident and their forecasting.

Fertility-sparing treatment of endometrial cancer precursors among young women: a reproductive point of view.

Science.gov (United States)

Ricciardi, E; Maniglio, P; Frega, A; Marci, R; Caserta, D; Moscarini, M

2012-12-01

Early-stage endometrial cancer and complex atypical hyperplasia are treated with hysterectomy and bilateral salpingo-oophorectomy. An emerging issue among younger women affected is the possibility of a fertility-sparing treatment with progestative therapy and close follow-up. To assess the possibility of conceiving after a diagnosis of atypical endometrial hyperplasia among women younger than 40 years old, in term of delaying definitive treatment and achieving pregnancy. 15 women younger than 40 years old with complex CAH or early carcinoma of the endometrium and a wish to preserve fertility. Progestins were administered orally for at least a 12 weeks period. Endometrial biopsies were used at follow-up. In 11 women, a complete pathological remission of the disease was observed. 4 pregnancies were attained in 4 women. 3 showed progression and underwent definitive surgery at 18 months. 1 showed no response at 24 months and 3 cycles and was counseled to receive a hysterectomy. A conservative approach in patients younger than 40 years appears a valid option, and a progestative therapy trial should be attempted whether a valid consensus is attained. Considering the risk to find AEH at biopsies and eventually a carcinoma at hysterectomy (25% of cases) a careful management is strictly required.

Seismic anisotropy from compositional banding in granulites from the deep magmatic arc of Fiordland, New Zealand

Science.gov (United States)

Cyprych, Daria; Piazolo, Sandra; Almqvist, Bjarne S. G.

2017-11-01

We present calculated seismic velocities and anisotropies of mafic granulites and eclogites from the Cretaceous deep lower crust (∼40-65 km) of Fiordland, New Zealand. Both rock types show a distinct foliation defined by cm-scale compositional banding. Seismic properties are estimated using the Asymptotic Expansion Homogenisation - Finite Element (AEH-FE) method that, unlike the commonly used Voigt-Reuss-Hill homogenisation, incorporates the phase boundary network into calculations. The predicted mean P- and S-wave velocities are consistent with previously published data for similar lithologies from other locations (e.g., Kohistan Arc), although we find higher than expected anisotropies (AVP ∼ 5.0-8.0%, AVS ∼ 3.0-6.5%) and substantial S-wave splitting along foliation planes in granulites. This seismic signature of granulites results from a density and elasticity contrast between cm-scale pyroxene ± garnet stringers and plagioclase matrix rather than from crystallographic orientations alone. Banded eclogites do not show elevated anisotropies as the contrast in density and elastic constants of garnet and pyroxene is too small. The origin of compositional banding in Fiordland granulites is primarily magmatic and structures described here are expected to be typical for the base of present day magmatic arcs. Hence, we identify a new potential source of anisotropy within this geotectonic setting.

Tritium in underground-water studies; Emploi du tritium dans les etudes sur les eaux souterraines; Tritij v isledovaniyakh podzemnykh vod; Empleo del tritio en el estudio de las aguas subterraneas

Energy Technology Data Exchange (ETDEWEB)

Alekseev, F A; Gol' bek, G R; Sojfer, V N; Vasil' eva, N A; Majdebor, V N; Sokolovskij, Eh V; Shan' gin, N N

1962-01-15

osnov- nogo kontura zakachivaemoj vody po otnositel'no odnorodnoj chasti plasta so skorost'yu 2 m/sutki. Poslednee sootvetstvuet teoreticheski vychislennym znacheniyam skorostej dvizheniya (1,9/2,2 m/sutki), v predpolozhenii odnorodnosti plasta. Vozmozhna kolichestvennaya otsenka raskhoda zhidkosti pri dvizheniyakh pervogo i vtorogo tipa. Razrabotan metod kontrolya soobshchaemosti mezhdu otdel'nymi proplastkami produktivnoj tolshchi neftyanogo plasta s pomoshch'yu tritievoj vody. Predlagaetsya novyj metod kontrolya razrabotki neftyanykh mestorozhdenij s zakonturnym i vnutrikonturnym zavodneniem s pomoshch'yu prirodnogo tritiya, soderzhashchegosya v zakachivaemykh v plast poverkhnostnykh vodakh. Metod pozvolyaet izuchat' medlennoe dvizhenie kontura v techenie prodolzhitel'nogo vremeni (poryadka 10 let) na krupnykh neftyanykh mestorozhdeniyakh s redkoj setkoj skvazhin. Po dole raspavshegosya tritiya v plastovoj vode ehkspluatatsionnykh skvazhin mogut byt' opredeleny vremena i skorosti dvizheniya vodnogo kontura s tochnost'yu {+-} 1 god. Trebuetsya minimal'nyj ob{sup e}m analiticheskoj raboty (ne bolee 300/500 analizov v god na grupnom mestorozhdenii) dlya kontrolya za dvizheniem kontura. Razrabotana vysokochuvstvitel'naya apparatura dlya izmereniya tritiya v poverkhnostnykh vodakh s ispol'zovaniem standartnykh schetchikov vnutrennego zapolneniya, dostupnaya dlya bol'shinstva promyslovykh organizatsij. (author)

Problems and principles of NPP diagnostics on the basis of mode parameter monitoring. Problemy i printsipy diagnostirovaniya YaEhU na osnove kontrolya rezhimnykh parametrov

Energy Technology Data Exchange (ETDEWEB)

Znyshev, V V

1990-01-01

Ideology of an approach to solving the problem of functional NPP diagnostics according to data on the dynamics of the plant monitored mode parameter dynamics, is presented. Difficulties in solving caused by NPP specific features as a diagnostics object are considered. Practical reasons simplifying the problem are expressed.

Simulation of << Hot >> particles formation during the accident at the Chernobyl NPP.; Modelirovanie obrazovaniya << goryachikh >> chastits vo vremya avarii na ChAEhS.

Energy Technology Data Exchange (ETDEWEB)

Kashparov, V A; Ivanov, Yu A; Prister, B S; Zvarich, S I; Protsak, V P; Khomutinin, Yu V; Polyakov, V D; Gudkov, A N; Kurepin, A D; Pazukhin, Eh M [Yinstitut Syil` s` kogospodars` koyi Radyiologyiyi, Kyiv (Ukraine); [Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)

1994-12-31

Dispersal composition of fuel << hot >> particles formed after oxidation of real Chernobyl nuclear fuel in the air for 3-21 hours at 673-1173 K was obtained. Mechanism of ruthenium particles formation during the accident (with dispersion of nuclear fuel) as a result of ruthenium oxidation, its sublimation, condensation and restoration on materials, presented by the elements of iron group was modelled. Dynamics of relative release of fission products, as well as of transuranium and transplutonium elements from real and modeled << hot >> particles at their high temperature incineration (1273-2273 K) in the inert media was measured.

The Performance of Major Plant Items at Calder Hall; Fonctionnement des elements principaux de la centrale de Calder Hall; Kharakteristika osnovnykh uzlov ustanovki v Kolder-Kholle; Rendimiento de los principales elementos de la central de Calder Hall

Energy Technology Data Exchange (ETDEWEB)

Desbruslais, E. L. [United Kingdom Atomic Energy Authority, Seascale, Cumberland (United Kingdom)

1963-10-15

. Opravdannoj yavlyaetsya ustanovka sdvoennogo vspomogatel'nogo oborudovaniya vmeste s ob{sup e}dineniem parovoj i vodnoj sistem. Oborudovanie B.C.D.G. okazalos' v vysshej stepeni udovletvoritel'nym. Vvidu togo, chto chuvstvitel'nost' gruppy kanalov vyshe chem neobkhodimo, v nastoyashchee vremya planirugtsya izmeneniya s tsel' ukorocheniya tsiklov za schet nekotoroj chuvstvitel'nosti. Obsuzhdayutsya meropriyatiya po pereoborudovaniyu sistemy podachi ehnergii dlya priborov reaktora i konturov bezopasnosti. Rekomenduyutsya klassifikatsiya stepeni opasnosti i vazhnosti i ustrojstvo po pervomu vyklyucheniyu reaktora. Vyyasnyaetsya neobkhodimost' imet' sistemu s dvumya zashchitnymi liniyami i ustanavlivat' tri ili bolee takikh linij. Statistika- pokazala polnuyu nadezhnost' oborudovaniya registratsii dannykh. Opravdyvaetsya neobkhodimost' bol'shoj standartizatsii oborudovaniya po peregruzke topliva. Ispol'zovanie spetsial'nykh ballonov i spetsial'nogo oborudovaniya po razgruzke trebuet mnogo vremeni, i ot ehtogo sleduet otkazat'sya. Opisyvayutsya izmeneniya/ vnesennye v mekhanizmy po zagruzke/razgruzke i vo vspomogatel'nuyu ustanovku. Podcherkivaetsya neobkhodimost' tshchatel'noj obrabotki topliva vo vremya zagruzki. Primenenie televizionnykh kamer v toplivnykh kanalakh i spetsial'nykh zakhvatov pozvolilo sokratit' vremya razgruzki. Nebol'shie neispravnosti otmecheny lish' pri ehkspluatatsii slozhnykh mekhanizmov upravlyayushchikh sterzhnej i sootvetstvuyushchego oborudovaniya po kontrolyu. Naskol'ko ehto vozmozhno, osnovnye sistemy upravleniya ustanovki dolzhny byt' tsentralizovany, i osnovnye tsentry upravleniya i uzly upravleniya ustanovki dolzhny byt' zashchishcheny ot sluchajnogo povrezhdeniya pri obluchenii vneshnimi istochnikami. Priznayutsya neobkhodimymi avtomaticheskie puskovoe i parallel'noe ustrojstva dlya avarijnoj dizel'noj ustanovki, odnako ustanovka mogla by byt' tsentralizovana s pol'zoj dlya dela. (author)

Operating Experience with the BR-5 Reactor; Experience acquise aupres du reacteur BR-5; Opyt ehkspluatatsii reaktora BR-5; Experiencia practica con el reactor BR-5

Energy Technology Data Exchange (ETDEWEB)

Lejpunskij, A. I.; Kazachkovskij, O. D.; Pinkhasik, M. S.; Aristarkhov, N. N.; Karpov, A. V.; Larin, E. P.; Efimov, I. A.

1963-10-15

remontnykh rabot na radioaktivnom zhidkometallicheskom konture reaktora na bystrykh nejtronakh BR-5. Osveshchayutsya voprosy ehkspluatatsii reaktora posle dostizheniya proektnogo 2%-nogo vygoraniya topliva pri nalichii nekotorogo narusheniya plotnosti otdel'nykh teplovydelyaptsikh ehlementov. Provoditsya opyt po razgruzke aktivnoj zony, issledovaniyu sostoyaniya i germetichnosti teplovydelyaptsikh ehlementov, dezaktivatsii oborudovaniya i truboprovodov I radioaktivnogo kontura posle dostizheniya 5% vygoraniya topliva. (author)

Application of multiple magnification roentgenography for the control of reparative process in carpal bones. Primenenie rentgenografii s mnogokratnym uvelicheniem dlya kontrolya za reparativnymi protsessami v karpal'nykh kostyakh

Energy Technology Data Exchange (ETDEWEB)

Prudnikov, I B

1991-04-01

Consideration is given to the first experience in using direct magnification roentgenography for diagnosis of navicular bone fracture and for evaluation of dynamics of reparative processes in carpal bones. Roentgenograms were made by portable X-ray apparatus REIS-D with 9-fold direct magnification. The use of the given type of roentgenography demonstrated its ample scope for both diagnosis of navicular bone fractures and for evaluation of the process of their adhesion.

Low-maturity Kulthieth Formation coal: A possible source of polycyclic aromatic hydrocarbons in benthic sediment of the northern Gulf of Alaska

Science.gov (United States)

Van Kooten, G. K.; Short, J.W.; Kolak, J.J.

2002-01-01

The successful application of forensic geology to contamination studies involving natural systems requires identification of appropriate endmembers and an understanding of the geologic setting and processes affecting the systems. Studies attempting to delineate the background, or natural, source for hydrocarbon contamination in Gulf of Alaska (GOA) benthic sediments have invoked a number of potential sources, including seep oils, source rocks, and coal. Oil seeps have subsequently been questioned as significant sources of hydrocarbons present in benthic sediments of the GOA in part because the pattern of relative polycyclic aromatic hydrocarbon (PAH) abundance characteristic of benthic GOA sediments is inconsistent with patterns typical of weathered seep oils. Likewise, native coal has been dismissed in part because ratios of labile hydrocarbons to total organic carbon (e.g. PAH:TOC) for Bering River coal field (BRCF) sources are too low - i.e. the coals are over mature - to be consistent with GOA sediments. We present evidence here that native coal may have been prematurely dismissed, because BRCF coals do not adequately represent the geochemical signatures of coals elsewhere in the Kulthieth Formation. Contrary to previous thought, Kulthieth Formation coals east of the BRCF have much higher PAH: TOC ratios, and the patterns of labile hydrocarbons in these low thermal maturity coals suggest a possible genetic relationship between Kulthieth Formation coals and nearby oil seeps on the Sullivan anticline. Analyses of low-maturity Kulthieth Formation coal indicate the low maturity coal is a significant source of PAH. Source apportionment models that neglect this source will underestimate the contribution of native coals to the regional background hydrocarbon signature. ?? Published by Elsevier Science Ltd. on behalf of AEHS.

Salmonella Typhi-specific multifunctional CD8+ T cells play a dominant role in protection from typhoid fever in humans.

Science.gov (United States)

Fresnay, Stephanie; McArthur, Monica A; Magder, Laurence; Darton, Thomas C; Jones, Claire; Waddington, Claire S; Blohmke, Christoph J; Angus, Brian; Levine, Myron M; Pollard, Andrew J; Sztein, Marcelo B

2016-03-01

Typhoid fever, caused by the human-restricted organism Salmonella Typhi (S. Typhi), is a major public health problem worldwide. Development of novel vaccines remains imperative, but is hampered by an incomplete understanding of the immune responses that correlate with protection. Recently, a controlled human infection model was re-established in which volunteers received ~10(3) cfu wild-type S. Typhi (Quailes strain) orally. Twenty-one volunteers were evaluated for their cell-mediated immune (CMI) responses. Ex vivo PBMC isolated before and up to 1 year after challenge were exposed to three S. Typhi-infected targets, i.e., autologous B lymphoblastoid cell-lines (B-LCL), autologous blasts and HLA-E restricted AEH B-LCL cells. CMI responses were evaluated using 14-color multiparametric flow cytometry to detect simultaneously five intracellular cytokines/chemokines (i.e., IL-17A, IL-2, IFN-g, TNF-a and MIP-1b) and a marker of degranulation/cytotoxic activity (CD107a). Herein we provide the first evidence that S. Typhi-specific CD8+ responses correlate with clinical outcome in humans challenged with wild-type S. Typhi. Higher multifunctional S. Typhi-specific CD8+ baseline responses were associated with protection against typhoid and delayed disease onset. Moreover, following challenge, development of typhoid fever was accompanied by decreases in circulating S. Typhi-specific CD8+ T effector/memory (TEM) with gut homing potential, suggesting migration to the site(s) of infection. In contrast, protection against disease was associated with low or no changes in circulating S. Typhi-specific TEM. These studies provide novel insights into the protective immune responses against typhoid disease that will aid in selection and development of new vaccine candidates.

Plutonium in the wood of natural trees in the near zone of the Chernobyl NPP.; Plutonij v drevesine zhivykh derev`ev blizhnej zony ChAEhS.

Energy Technology Data Exchange (ETDEWEB)

Kopejkin, V A [VNIIGEOLNERUD, Kazan` (Russian Federation)

1994-12-31

It was for the first time that the fact of radionuclides migration, particularly migration of plutonium in the wood of natural trees, was fixed in the near zone of the Chernobyl NPP. The data obtained show considerably quicker process of radioactive fall-out penetration than it was considered before.

2015 Advanced Environmental Health/Advanced Food Technology Standing Review Panel

Science.gov (United States)

Steinberg, Susan

2015-01-01

The 2015 Advanced Environmental Health/Advanced Food Technology (AEH/AFT) Standing Review Panel (from here on referred to as the SRP) met for a site visit in Houston, TX on December 14 - 15, 2015. The SRP met with representatives from the Space Human Factors and Habitability (SHFH) Element and members of the Human Research Program (HRP) to review the updated research plans for the Risk of Adverse Health Effects Due to Host-Microorganism Interactions (MicroHost Risk) and the Risk of Performance Decrement and Crew Illness due to an Inadequate Food System (Food Risk). During the meeting, the SRP also met with the vehicle engineers to discuss possible food storage options. The SRP would like to commend Dr. Oubre and Dr. Douglas for their detailed presentations, as well the frank, refreshing, and comprehensive engineering presentation. This gave much needed perspective to the food storage issues and reassured the committee about NASA's approach to the problem. In terms of critiques, the SRP remains unconvinced about the rationale for probiotic use other than for specific applications supported by the literature. It is not clear what gap or problem is being addressed by the use of probiotics, and the rationale for their use needs to be clearly rooted in the available literature. The SRP thinks that if low-Earth orbit is associated with immune system impairment, then there may additional risks linked with the use of probiotics. It is not clear to the SRP how NASA will determine if probiotics are having their intended beneficial effect. A similar concern is raised as to what gaps or problems are being addressed by "functional foods". Mixed infections, rather than single species infections, which can augment severity of disease, also represent a significant concern. Overall, the SRP considers this to be a strong program that is well-organized, well-coordinated and generates valuable data.

Elusive Role of the CD94/NKG2C NK Cell Receptor in the Response to Cytomegalovirus: Novel Experimental Observations in a Reporter Cell System

Directory of Open Access Journals (Sweden)

Aldi Pupuleku

2017-10-01

Full Text Available Human cytomegalovirus (HCMV infection promotes the differentiation and persistent expansion of a mature NK cell subset, which displays high surface levels of the activating CD94/NKG2C NK cell receptor, together with additional distinctive phenotypic and functional features. The mechanisms underlying the development of adaptive NK cells remain uncertain but some observations support the involvement of a cognate interaction of CD94/NKG2C with ligand(s displayed by HCMV-infected cells. To approach this issue, the heterodimer and its adaptor (DAP12 were expressed in the human Jurkat leukemia T cell line; signaling was detected by transfection of a reporter plasmid encoding for Luciferase (Luc under NFAT/AP1-dependent control. Engagement of the receptor by solid-phase bound CD94- or NKG2C-specific monoclonal antibodies (mAbs triggered Luc expression. Moreover, reporter activation was detectable upon interaction with HLA-E+ 721.221 (.221-AEH cells, as well as with 721.221 cells incubated with synthetic peptides, which stabilized surface expression of endogenous HLA-E; the response was specifically antagonized by soluble NKG2C- and HLA-E-specific mAbs. By contrast, activation of Jurkat-NKG2C+ was undetectable upon interaction with Human Fetal Foreskin Fibroblasts (HFFF infected with HCMV laboratory strains (i.e., AD169, Towne, regardless of their differential ability to preserve surface HLA-E expression. On the other hand, infection with two clinical isolates or with the endotheliotropic TB40/E strain triggered Jurkat-NKG2C+ activation; yet, this response was not inhibited by blocking mAbs and was independent of CD94/NKG2C expression. The results are discussed in the framework of previous observations supporting the hypothetical existence of specific ligand(s for CD94/NKG2C in HCMV-infected cells.

In vitro antioxidant properties, free radicals scavenging activities of extracts and polyphenol composition of a non-timber forest product used as spice: Monodora myristica

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Bruno Moukette Moukette

2015-01-01

Full Text Available BACKGROUND: Excessive production of free radicals causes direct damage to biological molecules such as DNA, proteins, lipids, carbohydrates leading to tumor development and progression. Natural antioxidant molecules from phytochemicals of plant origin may directly inhibit either their production or limit their propagation or destroy them to protect the system. In the present study, Monodora myristica a non-timber forest product consumed in Cameroon as spice was screened for its free radical scavenging properties, antioxidant and enzymes protective activities. Its phenolic compound profile was also realized by HPLC. RESULTS: This study demonstrated that M. myristica has scavenging properties against DPPH',OH',NO', and ABTS'radicals which vary in a dose depending manner. It also showed an antioxidant potential that was comparable with that of Butylated Hydroxytoluene (BHT and vitamin C used as standard. The aqueous ethanol extract of M. myristica barks (AEH; showed a significantly higher content in polyphenolic compounds (21.44 ±0.24 mg caffeic acid/g dried extract and flavonoid (5.69 ± 0.07 quercetin equivalent mg/g of dried weight as compared to the other studied extracts. The HPLC analysis of the barks and leaves revealed the presence of several polyphenols. The acids (3,4-OH-benzoic, caffeic, gallic, O- and P- coumaric, syringic, vanillic, alcohols (tyrosol and OH-tyrosol, theobromine, quercetin, rutin, catechine and apigenin were the identified and quantified polyphenols. All the tested extracts demonstrated a high protective potential on the superoxide dismutase (SOD, catalase and peroxidase activities. CONCLUSION: Finally, the different extracts from M. myristica and specifically the aqueous ethanol extract reveal several properties such as higher free radical scavenging properties, significant antioxidant capacities and protective potential effects on liver enzymes.

Development stage of computerization and automation of machines and equipment used at longwall faces in Polish mines. Sostoyanie rabot po ehlektronizatsii i avtomatizatsii mashin i oborudovaniya, ustanavlivaemogo v lave i primenyaemogo v Pol'skikh shakhtakh

Energy Technology Data Exchange (ETDEWEB)

Sobchik, Yu; Pan' kuv, A; Sikora, W [Gornopromyshlennoe Obedinenie po Avtomatizatsii EMAG, Katowice (Poland)

1988-01-01

Discusses development of control equipment and control systems for machines and equipment used in underground black coal mining in Poland. The following types of control systems are comparatively evaluated: control systems for powered supports used at longwall faces (remote control, control of groups of powered support units, control of individual support units), control systems for shearer loaders (control of shearer loader position at a working face, control of motor loading, motor heating, pressure in hydraulic systems, control of roller bearings etc.), control systems for coal plows (remote start-up of a coal plow and auxiliary equipment, communications between coal miners at a working face, control of motor loading, control of cutting head position, water spraying, etc.), sensors used in control systems and control equipment. Development trends of control systems for equipment used at longwall faces are discussed.

Composition and structure of solid-phase carriers of activity in soils of the exclusion zone.; Stroenie i sostav tverdofaznykh nositelej aktivnosti v pochvakh Zony otchuzhdeniya ChAEhS.

Energy Technology Data Exchange (ETDEWEB)

Bondarenko, G N; Dolin, V V; Val` ter, A A; Tikhanov, Eh K [AN Ukrainskoj SSR, Kiev (Ukraine). Inst. Geokhimii i Fiziki Mineralov; [Nauchno-Proizvodstvennoe Ob` ` edinenie Pripyat` , Chernobyl (Ukraine)

1994-12-31

From four different soils in the exclusion Chernobyl zone 35 << hot >> particles were picked out, their radionuclide and substance composition was investigated. To estimate a specific quantity of solid-phase carriers of activity we have calculated a ratio of activities of {sup 144} Ce and {sup 137} Cs in soils to the particles. Substance composition of the << hot >> particles investigated by the methods of electronic microscopy.

Certain results and problems of experimental retrospective radiation monitoring in the estrangement zone of the Chernobyl NPP.; Nekotorye rezul`taty i problemy ehksperimental`noj retrospektivnoj dozimetrii v Zone otchuzhdeniya ChAEhS.

Energy Technology Data Exchange (ETDEWEB)

Bar` yakhtar, V G; Bugaj, A A; Gajchenko, V A; Koval` , G N; Proskura, N I [AN Ukrainskoj SSR, Kiev (Ukraine). Inst. Poluprovodnikov; [Admyinyistratsyiya zoni vyidchuzhennya, Chornobil` (Ukraine)

1994-12-31

Experimental methods of retrospective radiation monitoring in the estrangement zone of the Chernobyl NPP are described. It is shown that the method of thermoluminescence of quartz particles as well as the method of electron paramagnetic resonance of tooth enamel may be applied both to verify theoretical designs and experimental estimates and to accumulate experimental data on the most interesting and typical cases of accidental irradiation.

Genetic diversity among five T4-like bacteriophages

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Bertrand Claire

2006-05-01

Full Text Available Abstract Background Bacteriophages are an important repository of genetic diversity. As one of the major constituents of terrestrial biomass, they exert profound effects on the earth's ecology and microbial evolution by mediating horizontal gene transfer between bacteria and controlling their growth. Only limited genomic sequence data are currently available for phages but even this reveals an overwhelming diversity in their gene sequences and genomes. The contribution of the T4-like phages to this overall phage diversity is difficult to assess, since only a few examples of complete genome sequence exist for these phages. Our analysis of five T4-like genomes represents half of the known T4-like genomes in GenBank. Results Here, we have examined in detail the genetic diversity of the genomes of five relatives of bacteriophage T4: the Escherichia coli phages RB43, RB49 and RB69, the Aeromonas salmonicida phage 44RR2.8t (or 44RR and the Aeromonas hydrophila phage Aeh1. Our data define a core set of conserved genes common to these genomes as well as hundreds of additional open reading frames (ORFs that are nonconserved. Although some of these ORFs resemble known genes from bacterial hosts or other phages, most show no significant similarity to any known sequence in the databases. The five genomes analyzed here all have similarities in gene regulation to T4. Sequence motifs resembling T4 early and late consensus promoters were observed in all five genomes. In contrast, only two of these genomes, RB69 and 44RR, showed similarities to T4 middle-mode promoter sequences and to the T4 motA gene product required for their recognition. In addition, we observed that each phage differed in the number and assortment of putative genes encoding host-like metabolic enzymes, tRNA species, and homing endonucleases. Conclusion Our observations suggest that evolution of the T4-like phages has drawn on a highly diverged pool of genes in the microbial world. The T4

System approach for evaluation of soil contamination by nitrogen containing pollutants in the 30-km zone power nuclear plant; Sistemnyj podkhod dlya otsenki zagryazneniya okruzhayushchej sredy azotsoderzhashchimi pollyutantami v 30-km zone aehs

Energy Technology Data Exchange (ETDEWEB)

Shevtsova, O. V.; Zhigunova, L. N.; Makovskaya, N. A.; Pavlovich, E. L. [Ob' ' edinennyj institut ehnergeticheskikh i yadernykh issledovanij – Sosny NAN Belarusi, Minsk(Belarus)

2013-01-15

This article presents the results of studies of the nitrogen-containing chemical pollutants of the soil 30 km zone nuclear power plant in order to evaluate the chemical carcinogenic risk to public health. As a result of this work the least amount of NDMA fixed at 0,83 × 10{sup -4} mg/kg, the highest - 128,29 × 10{sup -4} mg/kg, which is 0,83 and 128,3 %, respectively, of Madman established in the Russian Federation and Republic of Kazakhstan, the content of NDMA precursors - nitrite ions varies from 0,07 to 4,43 mg/kg. Found that most of the compounds reported in agricultural land. Calculate the total carcinogenic risk for the population living in the region - the set value corresponds to the maximum risk tolerance, i. e. the upper limit of acceptable risk. These levels are subject to continuous monitoring. (authors)

Estimation of safety of radionuclide localization in temporary areas for radioactive waste localization in the Chernobyl estrangement zone.; Otsenka nadezhnosti lokalizatsii radionuklidov v punkte vremennoj lokalizatsii radioaktivnykh otkhodov Zony otchuzhdeniya ChAEhS.

Energy Technology Data Exchange (ETDEWEB)

Mishunina, I B; Ledenev, A I; Khvesik, O V [Naukovo-Tekhnyichnij Tsentr z dezaktivatsyiyi ta kompleksnogo povodzhennya z radyioaktivnimi vyidkhodami, Zhovtyi Vodi (Ukraine)

1994-12-31

Preliminary estimation of soil water contamination as a result of radionuclide migration from burials is described. The studies necessary to make trustworthy prediction of soil water contamination are outlined.

Post-Construction Testing of the Elk River, Hallam and Piqua Power Reactor Plants; Essais apres construction des centrales nucleaires d'Elk River, de Hallam et de Piqua; Predehkspluatatsionnoe ispytanie Ehlk-riverskoj, Khehlpemskoj i Pikuaskoj ehnergeticheskikh reaktornykh ustanovok; Ensayos posteriores a la construccion de las centrales nucleoelectricas de Elk River, Hallam y Piqua

Energy Technology Data Exchange (ETDEWEB)

Pursel, C. A. [United States Atomic Energy Commission, Argonne, IL (United States)

1963-10-15

mezhdu okonchaniem stroitel'stva (sooruzhenie ehdakij i ustanovka oborudovaniya) i nachalom ehkspluatatsii na moshchnosti (proizvodstvo znachitel'nogo kolichestva ehlektricheskoj ehnergii netto). Ispytaniya presledovali sleduyushchie tseli: 1) proverit' rabochie kharakteristiki ustanovlennogo oborudovaniya; 2) opredelit' nachal'nuyu kritichnost' i koehffitsient reaktivnosti i 3) opredelit' fizicheskie kharakteristiki reaktora i rabochie kharakteristiki ustanovki po mere uvelicheniya moshchnosti. Nakoplennyj opyt mokhet byt' izlozhen v shesti otdel'nykh, no vzaimosvyazannykh razdelakh: 11 programma; 2) stoimost'; 3) potrebnosti v kadrakh; 4) tekhnologiya provedeniya ispytanij; 5) rabota oborudovaniya (vklyuchaya nepoladki) i 6) fakticheskie (po sravneniyu s raschetnymi) kharakteristiki raboty sistemy. Srednyaya proektnaya chislennost' personala, vklyuchaya rabochikh, operatorov, dozimetristov, vspomogatel'nyj tekhnicheskij personal i stazherov, sostavlyaet: dlya ERR - 50, dlya HNPF - 115 i dlya PNPF - 60 chelovek. Podrobnaya tekhnologiya predehkspluatatsionnykh ispytanij v pis'mennom vide byla podgotovlenv dlya kazhdogo vazhnogo komponenta i kazhdoj sistemy ustanovki. Naskol'ko ehto bylo vozmozhno, vse ispytaniya byli provedeny do zagruzki topliva i nachala ehkspluatatsii vsej ustanovki. Oformlenie razreshenij na ehkpluatatsiyu ustanovok (dublikaty litsenzij na neprinadlezhashchie KAEH SSHA ustanovki) zanyalo pochti vse vremya provedeniya predehkspluatatsionnykh ispytanij. Vremya, potrebovavsheesya dlya provedeniya predehkspluatatsionnykh ispytanij kazhdoj iz ehtikh ustanovok, znachitel'no prevysilo pervonachal'no namechennoe vremya. Ispytaniya vskryli ryad yavnykh i predpolagaemykh neispravnostej komponentov, v rezul'tate chego potrebovalos' provesti dopolnitel'nye ispytaniya i analizy. V ryade sluchaev dlya ispravleniya oshibok, dopushchennykh pri izgotovlenii ili konstruirovanii oborudovaniya, komponenty prishlos' remontirovat' ili vidoizmenyat'. Osnovnymi nepoladkami

Cytohematological indices of cattle adaptation to the chronic radiation effect in the exclusion zone of the Chernobyl NPP.; Tsitogematologicheskie pokazateli adaptatsii u krupnogo rogatogo skota pri khronicheskom radiatsionnom vozdejstvii v Zone otchuzhdeniya ChAEhS.

Energy Technology Data Exchange (ETDEWEB)

Panchenko, N A; Filimonov, I S; Zagorujko, E E; Gashchak, S P; Korisheva, A P [Myizhgaluzevij Naukovo-Tekhnyichnij Tsentr ` ` Ukrittya ` ` , Natsyional` na Akademyiya Nauk Ukrayini, Chornobil` (Ukraine); [Nauchno-Proizvodstvennoe Ob` ` edinenie Pripyat` , Chernobyl (Ukraine)

1994-12-31

Peripheral blood cells have been examined in cattle from the experimental farm in the 10 km zone of the Chernobyl NPP. With that aim 25 animals of different age groups and generations were investigation. Appearance of heteropholic granulocytes and << specific >> basophilic cells which heterogeneity is explained by their morphological and functional attribution has been observed.

Results of complex studies in radiation state of temporary areas for radioactive waste localization in the Chernobyl estrangement zone.; Rezul`taty kompleksnykh issledovanij radiatsionnogo sostoyaniya punktov vremennoj lokalizatsii radioaktivnykh otkhodov v Zone otchuzhdeniya ChAEhS.

Energy Technology Data Exchange (ETDEWEB)

Ledenev, A I; Ovcharov, P A; Mishunina, I B; Antropov, V M [Naukovo-Tekhnyichnij Tsentr z dezaktivatsyiyi ta kompleksnogo povodzhennya z radyioaktivnimi vyidkhodami, Zhovtyi Vodi (Ukraine)

1994-12-31

Describing complex studies in radiation state of temporary areas for radioactive waste localization in the nearest Chernobyl NPP zone, the paper provides results of these studies as well as results of inspection of radioactive waste hidden in 1990 - 1994.

Distribution of {sup 90} Sr and {sup 137} Cs in vertical soil sections of the Chernobyl exclusion zone.; Raspredelenie form nakhozhdeniya {sup 90} Sr i {sup 137} Cs po vertikal`nym pochvennym razrezam Zony otchuzhdeniya ChAEhS.

Energy Technology Data Exchange (ETDEWEB)

Bondarenko, G N; Kononenko, L.V. [AN Ukrainskoj SSR, Kiev (Ukraine). Inst. Geokhimii i Fiziki Mineralov

1994-12-31

Water-soluble, exchangeable and acid-soluble (IM HCI) forms of {sup 90} Sr and {sup 137} Cs were determined in 15 layer-by-layer (1 cm) samples of podzolis and peaty soils from the Chernobyl exclusion zone taken in 1991 and 1992. Positions of centers of {sup 137} Cs and {sup 90} Sr supply as well as their water-soluble and exchangeable forms were estimated. The data obtained testify to deceleration of vertical migration of {sup 137} Cs in soils till the early 90th. The conclusion is made on evolution of dominating mechanisms of vertical migration of radionuclides. It consists in a decrease of the lessivage significance.

Identification and estimation ot carbohydrates using radioisotopic methods; Identification et dosage des hydrates de carbone a l'aide des radioisotopes; Identifikatsiya i opredelenie karbogidratov s pomoshch'yu radioizotopnykh metodov; Identificacion u valoracion de hidratos de carbono con ayuda de radioisotopos

Energy Technology Data Exchange (ETDEWEB)

Phillips, G O; Criddle, W J [Department of Chemistry, University College, Cardiff (United Kingdom)

1962-01-15

sostavnykh chastej : Mozhno razlichit' d- i i-izomery i proizvesti individual'nuyu otsenku kazhdogo iz nikh. EHtot metod primenyaetsya pri reshenii drugikh analiticheskikh problem v khimii karbogidratov. V doklade daetsya opisanie novogo metoda graficheskogo izobrazheniya i zapisi radio- aktivnosti po liniyam khromogrammy na bumage, chto vozmozhno osushchestvit' pri neznachitel'nykh zatratakh na modifikatsiyu obychnogo schetnogo oborudovaniya. (author)

Performance Characteristics of the Experimental Boiling Water Reactor from 0 to 100 MW(t); Performances de l'EBWR de 0 a 100 MW; Rabochaya kharakteristika ehksperimental'nogo kipyashchego reaktora EBWR pri moshchnosti 0 - 100 mgvt.; Rendimiento del reactor experimental de agua hirviente (EBWR) entre 0 y 100 MW

Energy Technology Data Exchange (ETDEWEB)

Iskenderian, A.; Lipinski, W. C.; Petrick, M.; Wimunc, E. A. [Argonne National Laboratory, Argonne, IL (United States)

1963-10-15

entonces de comportarse como reactor de agua hirviente de ciclo directo; en cierto modo, funciona como reactor de ciclo doble y circulacion natural. (author) [Russian] 25 maya 1962 goda Argonnskaya natsional'naya laboratoriya poluchila razreshenie KAEH SSHA na ehkspluatatsiyu reaktora EBWR na moshchnosti 100 mgvt. Administrativnoe razreshenie na ehkspluatatsiyu reaktora bylo predostavleno sistemoj garantij. Mezhdunarodnogo agentstva po atomnoj ehnergii 11 iyulya 1961 goda. 15 noyabrya 1962 goda byl dostignut uroven' moshchnosti v 100 mgvt. 6 dekabrya 1962 goda ehksperimental'naya programma byla zakonchena. Odnoj iz osnovnykh tselej ee byla tshchatel'naya proverka reaktora dlya polucheniya dannykh i informatsii rabochej kharakteristiki ehtogo tipa reaktora. Ehta programma byla pervoj programmoj takogo roda i pervoj vypolnennoj programmoj. Dlya polucheniya nuzhnykh dannykh neobkhodimo bylo razrabotat' mnogie novye pribory. TSel' byla dostignuta, polucheno mnogo novykh dannykh o rabochej kharakteristike kipyashchego reaktora s estestvennoj tsirkulyatsiej. Tak,naprimer, poluchena informatsiya otnositel'no skorosti potoka tsirkulyatsii v zamknutom tsikle, predelov separatsii zhidkogo para (vydelenie para v osadok v spusknoj trube i unos zhidkosti ehflu- entom para), nedogreva, lokalizatsii dejstvitel'noj poverkhnosti razdela v reaktore i ee svyazi s urovnem vodnoj kolonki, skorosti razrusheniya para v spusknoj trube, pustotnykh koehffitsientov, reaktivnoj sposobnosti H{sub 3}BO{sub 3}, temperaturnykh koehffitsientov, ispol'zovaniya sterzhnej iz bora dlya tselej kontrolya, ispol'zovaniya svezhikh toplivnykh ehlementov, peredatochnykh funktsij,analiza shuma, nekotorykh izmerenij potoka, stabil'nosti i t.d. Krome togo, byli polucheny dannye o povedenii i tselostnosti nekotorykh reaktornykh komponentov i sistem, takikh, kak bornokislaya kontrol'naya reaktsiya, urovni radiatsii, raspredelenie produktov korrozii, vykhod iz stroya oborudovaniya, toplivo i reguliruyushchie sterzhni i t

Double-Sampling Method for Carrying Out Quality Control of a Fabrication Process; Methode du Double Echantillonnage pour le Controle de la Qualite d'un Procede de Fabrication; Metod dvukh obraztsov dlya osushchestvleniya kontrolya za kachestvom v protsesse izgotovleniya; Metodo de Muestreo Doble para el Control de Calidad de un Proceso de Fabricacion

Energy Technology Data Exchange (ETDEWEB)

Cerrolaza, J. A.; Lago, A.; Montojo, Rosa M. [Junta de Energia Nuclear, Madrid (Spain)

1966-02-15

In fabricating components for use in reactors, two basic factors are of decisive importance, namely the need for very high quality, which allows of only a very small percentage of defective parts, and the very high cost of each of the components. Because of these two considerations, control during fabrication has to follow an operating curve with a very high power and, provided that this condition is fulfilled, the number of pares destroyed in each inspection has to be kept to a minimum. The usual methods, which are based on the determination of the error of first kind, cannot be used because they are generally not effective enough. Cave has developed a method in which the size of the samples and the limits of control are established as a function of the errors of first and second kind. This method, although applicable, is not really practicable for the inspection of reactor components since the samples required are too large. The present paper presents a method which is similar to that of Cave but which relies on double sampling and thus considerably reduces the average size of the sample. (author) [French] La fabrication des elements constitutifs des reacteurs nucleaires presente deux caracteristiques essentielles, qui la conditionnent: la qualite superieure exigee reduit fortement le pourcentage des pieces defectueuses que l'on peut admettre et le prix de revient de chaque element est tres eleve. Etant donne ces deux conditions, les controles en cours de fabrication doivent se multiplier a mesure que l'on avance dans la chaftie des operations; d'autre part, il faut que le nombre des pieces detruites lors de chaque inspection soit aussi reduit que possible, tout en respectant la premiere condition. Les methodes habituelles de controle qui visent essentiellement a limiter le risque inherent a la premiere condition ne sauraient etre appliquees car, d'une maniere generale, elles ne sont pas suffisamment efficaces. Cave a mis au point une methode dans laquelle la taille des echantillons et le degre de controle sont determines en fonction des risques inherents a la premiere et a la deuxieme condition. Bien que cette methode soit applicable, elle est fort peu pratique quand il s'agit de controler des pieces de reacteurs, car les echantillons qu'elle exige sont de dimensions excessives. Le memoire expose une methode analogue a celle de Cave mais qui consiste a etablir un double echantillonnage dans lequel la taille moyenne de l'echantillon est beaucoup plus reduite. (author) [Spanish] La fabricacion de componentes que han de ser empleados en reactores nucleares presenta dos caracteristicas fundamentales que condicionan el proceso: la exigencia de una calidad muy elevada que limita a valores muy bajos el porcentaje de piezas defectuosas admisibles, y el coste muy alto de cada uno de los componentes. Estas dos condiciones obligan a que el control durante la fabricacion posea una curva de operacion con potencia muy elevada, y, por otra parte, a que el numero de piezas destruidas en cada inspeccion sea un pequeno como se pueda, siempre que se cumpla la condicion anterior. Los metodos usuales de control, basados en fijar el riesgo de primera especie, no son aplicables, ya que en general su eficacia no es suficiente. Cave ha desarrollado un metodo en que, tanto el tamano de las muestras como los limites de control, se fijan en funcion de los riesgos de primera y segunda especie. Este metodo, si bien es aplicable, resulta poco practico en el control de componentes para reactores, ya que se necesitan muestras de un tamano excesivamente grande. En el presente trabajo se desarrolla un metodo semejante al de Cave, pero en el que se establece un muestreo doble, con lo que el tamano medio de la muestra es mucho mas reducido. (author) [Russian] Pri izgotovlenii komponentov dlja ispol'zovanija v reaktorah reshajushhee znachenie imejut dva osnovnyh faktora, a imenno: neobhodimost' obespechit' ochen' vysokoe kachestvo, dopuskajushhee lish' ochen' malyj procent defektnyh detalej, i ochen' vysokaja stoimost' kazhdogo iz komponentov. Po jetim soobrazhenijam v hode izgotovlenija neobhodimo tshhatel'no priderzhivat'sja krivoj proizvodstvennyh operacij, i pri sobljudenii jetogo uslovija chislo detalej, razrushaemyh pri kazhdoj proverke, dolzhno byt' minimal'nym. Obychnye metody, osnovannye na opredelenii oshibki pervogo roda, ne mogut byt' ispol'zovany, tak kak oni voobshhe nedostatochno jeffektivny. Kave razrabotal metod, pri kotorom razmer obrazcov i predely kontrolja javljajutsja funkciej oshibok pervogo i vtorogo roda. Jetot metod, hotja on i primenim, nevozmozhno ispol'zovat' dlja proverki komponentov reaktora, poskol'ku pri jetom nuzhny slishkom bol'shie obrazcy. Daetsja opisanie metoda, analogichnogo metodu Kave, no osnovannogo na ispol'zovanii dvuh obrazcov, blagodarja chemu znachitel'no umen'shaetsja srednij razmer obrazca. (author)

Control Methods Used in the Department of Metallurgy for Structure and Fuel Elements; Methodes de Controle Utilisees au Departement de Metallurgie pour les Elements de Structure et les Elements Combustibles; Metody kontrolya struktury toplivnykh ehlementov v departamente metallurgii; Metodos de Control Utilizados en el Departamento de Metalurgia para los Elementos Estructurales y Combustibles

Energy Technology Data Exchange (ETDEWEB)

Destribats, Marie-Therese; Allain, C.; Prot, A.; Thome, P. [Centre d' Etudes Nucleaires de Saclay (France)

1965-09-15

Studies of various reactor types undertaken by the Commissariat a l'energie atomique have led to the use and-development of many non-destructive methods of testing the various materials employed in their construction, and especially methods involving the use of X- and {gamma}-rays, ultrasonic waves and eddy currents. A summary is given below of the tests carried out during the construction of EDF (graphite gas) and EL 4 (heavy water) reactor types and of co-laminated elements. Emphasis is laid on certain typical aspects of these various methods, some of which are well known. EDF type: ultrasonic measurement of the wall thicknesses of uranium or uranium alloy tubes; gamma- radiographic detection of voids in the tubes; ultrasonic inspection following heat treatment of the tubes ultrasonic flaw detection (inclusions, pipes) in billets and rough casts for MgZr cladding; leak-tightness testing of slugs by helium eliquation. EL4 type: ultrasonic and eddy-current measurements of the wall thicknesses of Zircaloy pressure and guide tubes; ultrasonic inspection of Zircaloy pressure tubes and stainless-steel cladding tubes; in vacuo radiography of Be claddings; leak-tightness testing of pencils by helium eliquation. Co-laminated elements; cladding thickness measurements by pulsed eddy currents; determination of core position in tubes and plates, using X-rays, gamma counting and pulsed eddy currents; checking of fuel homogeneity by gamma counting; ultrasonic and gamma-radiographic flaw detection in ZrU billets; detection of unbonded areas in plates, using ultrasonic waves, pulsed eddy currents and resistivity measurements. The methods have been developed for industrial use. Several of the inspections already constitute routine manufacturing procedures, others will be introduced shortly and a further number are likely to come into use at a later date. (author) [French] Les etudes de divers types de reacteurs entreprises par le CEA ont conduit a utiliser et a mettre au point de nombreuses methodes de controle non destructif pour les differents materiaux entrant dans leur realisation, en particulier: radiographie et gammagraphie, methodes ultrasonores et courants de Foucault. Le memoire decrit les controles effectues au cours de la fabrication des reacteurs des filieres EDF (graphite- gaz) et EL4 (eau lourde) et des elements colamines. Les auteurs insistent sur quelques points caracteristiques de ces diverses methodes, dont certaines sont bien connues. Filiere EDF: mesure des epaisseurs des parois des tubes en uranium ou uranium allie, par ultrasons; recherche des cavites de ces tubes, par gammagraphie; controle des traitements thermiques de ces tubes, par ultrasons; recherche des defauts (inclusions, criques), par ultrasons dans les billettes et ebauches des gaines en MgZr; controle de l'etancheite des cartouches, par ressuage d'helium. Filiere EL 4: mesure des epaisseurs des parois des tubes de force, et de guidage en Zircaloy, par ultrasons et courants de Foucault; examen des tubes de force en Zircaloy et tube de gaine en acier inoxydable par ultrasons; radiographie sous vide des gaines en Be; controle d'etancheite des crayons, par ressuage d'helium. Elements colamines : mesure de l'epaisseur des gaines, par courants de Foucault puises; recherche de la position de l'ame sur tubes et plaques, par radiographie, comptage gamma et courants de Foucault puises; controle de l'homogeneite.du combustible, par comptage gamma; detection des defauts dans les billettes en ZrU, par ultrasons et gammagraphie; recherche des zones decollees des plaques, par ultrasons, courants de Foucault puises et mesure de resistivite. Ces mises au point ont ete faites en vue de leur utilisation industrielle. Plusieurs de ces controles sont effectues couramment en cours de fabrication, d'autres le seront prochainement et certains sont susceptibles de l'etre a plus longue echeance. (author) [Spanish] Los estudios del Commissariat a l'Energie Atomique sobre diversos tipos de reactores indujeron a utilizar y a perfeccionar numersos metodos no destructivos destinados a inspeccionar los distintos materiales que intervienen en la construccion de esos reactores; en particular radiografia y gamma- grafia, metodos ultrasonicos y empleo de corrientes de Foucault.. A continuacion se enumeran las operaciones de control llevadas a cabo durante la construccion de reactores pertenecientes a las familias EdF (grafito-gas) y EL 4 (agua pesada), y de elementos colaminados; se hace hincapie en ciertos aspectos caracteristicos de estos metodos, algunos de los cuales son ya bien conocidos. Familia EdF: metodos ultrasonicos para medir el espesor de las paredes de tubos de uranio o aleacion de uranio ; localizacion de las cavidades en esos tubos por gammagraffa; empleo de medios ultrasonicos para control de los tratamientos termicos a que se someten los tubos; empleo de procedimientos ultrasonicos para buscar fallas (inclusiones, grietas) en las palanquillas y barras con que se elaboran las vainas de Mg-Zr; control de la estanqueidad de los elementos mediante exudacion de helio. EL4: uso de metodos ultrasonicos y corrientes de Foucault para medir espesores de pared en tubos de Zircaloy, sean de fuerza o de guia; empleo de metodos ultrasonicos para inspeccionar tubos de fuerza de Zircaloy y vainas de acero inoxidable; radiografia al vacio de vainas de Be; control de la estanqueidad de barras huecas mediante exudacion de helio. Elementos colimados: medida del espesor de vainas mediante el empleo de corrientes de Foucault pulsadas; verificacion de la posicion del alma en tubos y placas mediante radiografia, recuento gamma y aplicacion de corrientes de Foucault pulsadas; control de la homogeneidad del combustible por recuento gamma; deteccion de defectos en barras de Zr-U mediante procedimientos ultrasonicos y gammagraficos; determinacion de las zonas despegadas en placas, empleando metodos ultrasonicos, corrientes de Foucault pulsadas y medicion de resistividad. Estos metodos se han desarrollado con miras a su utilizacion industrial. Algunos de ellos se aplican ya corrientemente durante la fabricacion; otros se utilizaran proximamente y el resto es susceptible de aplicacion a mas largo plazo. (author) [Russian] Nachatoe v KAJe izuchenie razlichnyh tipov reaktorov privelo k ispol'zovaniju i razrabotke mnogih metodov nedestruktivnogo kontrolja razlichnyh materialov, v chastnosti radiografii, gammagrafii, ul'trazvukovyh voln i metoda tokov Fuko. Nizhe govoritsja o kontrole v processe stroitel'stva reaktorov sistemy EDF (grafit- gaz), EL4 (tjazhelaja voda) i izgotovlenija sovmestno prokatannyh jelementov. Vydeleny nekotorye harakternee momenty jetih razlichnyh metodov, chast' kotoryh horosho izvestna. Sistema EDF: izmerenie tolshhiny stenok trub iz urana ili iz uranovogo splava ul'trazvukom; vyjavlenie polostej v jetih trubkah s pomosh'ju gammagrafii; kontrol' za termicheskoj obrabotkoj ul'trazvukom jetih trub; izuchenie defektov (vkraplenija, treshhiny) ul'trazvukom v slitkah i zagotovkah obolochek iz MgZr; kontrol' za germetichnost'ju toplivnyh jelementov s pomoshh'ju gelija. Sistema EL 4: izmerenie tolshiny stenok silovyh trub i napravljajushhih trub iz cirkal- loja s pomoshh'ju ul'trazvuka i tokov Fuko; proverka s pomoshh'ju ul'trazvuka trub iz cirkal- loja, rasschitannyh na davlenie, i trubchatogo pokrytija iz nerzhavejushhej stali; vakuumnaja radiografija obolochek iz Be; kontrol' germetichnosti sterzhnej s pomoshh'ju gelija. Sovmestno prokatannye jelementy: izmerenie tolshhiny pokrytija pul'sirujushhimi tokami Fuko; vyjavlenie polozhenija serdechnika po otnosheniju k trubam i plastinkam s pomoshh'ju radiografii, scheta gamma-chastic i pul'sirujushhih tokov Fuko; kontrol' za gomogennost'ju topliva metodom scheta gamma-chastic; obnaruzhenie treshhin v slitkah iz ZrU s pomoshh'ju ul'trazvuka i gammagrafii; vyjavlenie otsloennyh uchastkov plastinok s pomoshh'ju ul'trazvuka, pul'sirujushhih tokov Fuko, a takzhe izmerenie udel'nogo soprotivlenija. Jeti razrabotki byli predprinjaty s uchetom ih promyshlennogo primenenija. Nekotorye iz jetih metodov kontrolja primenjajutsja v processe proizvodstva, drugie najdut svoe primenenie v blizhajshem budushhem, a rjad metodov verojatno vojdet v praktiku pozdnee. (author)

The Technical Training Programme for Nuclear Power Station Personnel; Programme de formation technique du personnel des centrales nucleaires; Programma tekhnicheskoj podgotovki personala yadernoj ehlektrostantsii; El programa de formacion tecnica del personal de una central nucleoelectrica

Energy Technology Data Exchange (ETDEWEB)

Howey, G. R. [Hydro-Electric Power Commission of Ontario, Toronto, Ontario (Canada)

1963-10-15

kvalifikatsii v zavisimosti ot potrebnostej v rabote; (3) obsluzhivayushchij personal po kontrol'no-izmeritel'nym priboram - chetyre.urovnya kvalifikatsii; neset otvetstvennost' za remont vsekh apparatov, oborudovaniya po upravleniyu i ehlektrooborudovaniya; (4) mekhaniki po remontu - nesut otvetstvennost' za remont vsego mekhanicheskogo oborudovaniya (montazhnye raboty, svarka i t.d.); (5) obsluzhivayushchij personal - neset otvetstvennost' za raznoobraznye raboty, kotorye trebuyut bolee nizkoj kvalifikatsii. V dopolnenie k ehtim obshchim kategoriyam trebuetsya nebol'shoe kolichestvo spetsialistov, takikh kak khimiki i sluzhashchie po radiatsionnoj zashchite. Obsuzhdaetsya organizatsionnaya struktura personala NPD i programma ego obucheniya dlya budushchikh nuzhd yadernoj ehnergetiki. (author)

The Problems of Controlling Defects in the Materials Used for the First Czechoslovak Nuclear-Power Station; Problemes de Controle des Defauts dans les Materiaux Utilises a la Premiere Centrale Nucleaire de Tchecoslovaquie; Problemy defektoskopicheskogo kontrolya stroitel'nykh materialov reaktora pervoj chekhoslovatskoj atomnoj ehlektrostantsii; Problemas de Control de Defectos en los Materiales Utilizados en la Primera Central Nuclear de Checoslovaquia

Energy Technology Data Exchange (ETDEWEB)

Radislav, Filipp [Zavody Im.V.I. Lenina, Pl' zen, Czechoslovakia (Czech Republic)

1965-09-15

The paper briefly describes the reactor vessel of the first Czechoslovak nuclear power station. In order to meet the stringent design and structural requirements involved in fabricating the reactor vessel, which consists of low-alloy, non-aging steel of considerable thickness (650 mm), it was necessary to devise a ''control'' method for non-destructive testing of the basic material and welded joints. The ultrasonic pulse method, using one probe, is used extensively in testing the quality of the basic material and welded joints. The paper describes the methods used for carrying out tests and interpreting the results during the investigation of the basic material, and the methods for testing the quality of molten-slag arcless electric welds, carbon-dioxide welds, and manual arc welds. An automatic flaw-detection apparatus made in Czechoslovakia is used to test flat forgings and rolled products. The apparatus consists of two parts: a travelling mechanism and a UID-A2 ultrasonic flaw-detector made in Czechoslovakia. The apparatus incorporates a number of new features. The effect of distance on the height of the defect signal pulse is compensated and the height remains constant. The effect of irregularity of the acoustic link is also compensated since the data-unit conveys pulses to the remote recording device. An attenuator is used to determine the size of the flaw. An automatic apparatus is now being developed for testing on a vertical cylindrical surface. Assembly welds on circumferences must be tested at a high temperature. In the V.I. Lenin Plant at Pilsen a special data-unit has been developed for this purpose which makes it possible to carry out tests at elevated temperatures with a high degree of accuracy. Non-destructive tests of welded structures are also carried out using radiography. The testing of thin longitudinal seam welds and their roots at a high temperature is carried out with an X-ray unit with circular radiation characteristics, using special cassettes. In radiographing thick welds, betatrons of Czechoslovak manufacture are used. The paper describes the methods used for testing and the results obtained and compares the Czechoslovak 15-MeV betatron with the Siemens' betatron. (author) [French] Le memoire donne une description succincte de la cuve du reacteur de la premiere centrale nucleaire de Tchecoslovaquie. En raison des specifications rigoureuses auxquelles doivent repondre les methodes de construction et d'assemblage de la cuve du reacteur, en acier inoxydable faiblement allie de grande epaisseur (650 mm), il a fallu elaborer une methode de controle non destructif du materiau de base et des soudures, fondes sur l'emploi de ' temoins ' . Pour controler la qualite du materiau de base et des sourdures, on utilise essentiellement des ultrasons puises et une sonde. Le memoire decrit les methodes d'essais et l'evaluation des donnees au cours de l'examen du materiau de base, ainsi que le procede qui permet de verifier la qualite des soudures electriques a scorie, des soudures en atmosphere de gaz carbonique et des soudures a l'arc faites a la main. Le controle des plaques forgees et laminees se fait au moyen d'un dispositif automatique de defectoscopie qui a ete mis au point en Tchecoslovaquie. Ce dispositif se compose de deux parties: un mecanisme mobile et un detecteur a ultrasons du type U1D-A2, de fabrication tchecoslovaque. Il comprend plusieurs elements inedits. On a compense l'effet de la distance sur l'ampleur du signal declenche par un defaut de maniere que cette ampleur reste constante. On a compense aussi l'effet du aux irregularites de la liaison acoustique, les impulsions etant communiquees a un dispositif d'enregistrement a distance. L'importance du defaut est evalue a l'aide d'unattenuateur. On metau point un dispositif automatique pour controler une surface cylindrique verticale. Les soudures d'assemblage circulaire doivent etre verifiees a une temperature elevee. Dans les usines V. I. Lenine de Pilsen, on a elabore a cet effet un instrument special grace auquel on peut faire des controles a haute temperature avec une grande precision. Le controle non destructif des pieces soudees peut se faire egalement par radioscopie. La verification de petites epaisseurs et celle, a haute temperature, de la base d'une soudure longitudinale sont realisees a l'aide des rayons X provenant d'un appareil a emanation circulaire, et de cassettes speciales. Pour la radioscopie des pieces soudees de grande epaisseur, on a recours a un betratron de fabrication tchecoslovaque. L'auteur decrit les methodes d'essai, indique les resultats obtenus et fait une etude comparative entre le betatron tchecoslovaque de 15 MeV et celui de Siemens. (author) [Spanish] En la memoria se describe brevemente el cuerpo del reactor de la primera central nuclear de Checoslovaquia. Las rigurosas normas seguidas en su construccion (acero inoxidable de baja aleacion, de 650 mm de espesor) exigieron elaborar un metodo de 'testigos'para proceder al control no destructivo del material basico y de las soldaduras. Para el control de calidad del material basico y de las soldaduras se recurrio en gran medida al metodo de impulsos ultrasonicos, utilizando una sonda. En la memoria se describe la tecnica empleada y se evaluan los datos obtenidos; tambien se expone el metodo de control de calidad de las piezas soldadas electricamente con formacion de escorias y de las soldadas en atmosfera de anhidrido carbonico, asf como las soldadas a mano mediante arco electrico. La integridad de las placas forjadas o laminadas se controla automaticamente en una instalacion de defectoscopia de fabricacion checoslovaca, qoe consta de dos partes: un mecanismo movil y un defectoscopio de ultrasonidos U1D-A2. La instalacion se distingue por poseer varios elementos nuevos. La influencia ejercida por la distancia sobre la amplitud de la sen al originada por el defecto se compensa de manera que la altura de la senal permanece constante. Igualmente, se compensa el efecto de la irregularidad del acoplamiento acustico; el dispositivo envia impulsos al dispositivo del registro a distancia. Las dimensiones del defecto se determinan con ayuda de un atenuador. En la actualidad, se esta montando una instalacion automatica que permitira proceder al control de la superficie de un cilindro vertical. En el caso de las soldaduras, es necesario efectuar el control en la parte exterior a temperatura elevada. Con esa finalidad, en la fabrica 'V.I. Lenin' d e Pilsen se ha construido un dispositivo especial que permite procecer a controles de gran exactitud a altas temperaturas. El control no destructivo de los elementos soldados se efectua igualmente por rayos X. La medicion de pequenosi espesores y del metal base de una soldadura se hace mediante rayos X caracteristicos, utilizando chasis especiales. En la radioscopia de piezas soldadas de gran espesor se recurre a un betatron de procedencia checoslovaca. En la memoria se describe la tecnica de los ensayos, los resultados obtenidos y se comparan las caracteristicas del mencionado betatron de 15 MeV con otro construido por la firma Siemens. (author) [Russian] Daetsja kratkoe opisanie korpusa reaktora pervoj chehoslovackoj atomnoj jelektrostancii. Vysokie tre- bovanija k konstrukcii i tehnologii izgotovlenija korpusa reaktora, vypolnennogo iz nizko- legirovannoj nestarejushhej stali (tolshhina stenok 650 mm), priveli k neobhodimosti razra- botki metoda 'svidetelej' dlja kontrolja prochnosti konstrukcii bez razrushenija osnovnogo materiala i svarnyh soedinenij. Dlja kontrolja kachestva osnovnogo materiala i svarnyh soedinenij v bol'shoj mere is- pol'zuetsja ul'trazvukovoj impul'snyj metod s primeneniem odnogo zonda. Daetsja opisanie metodiki ispytanij i ocenki pokazanij vo vremja issledovanija osnovnogo materiala, a takzhe metodiki ispytanija kachestva jelektroshlakovyh svarnyh soedinenij, svarnyh soedinenij, provedennyh v atmosfere uglekislogo gaza , i ruchnyh dugovyh soedinenij. Kontrol' cel'nosti ploskih pakovok i prokata poizvodits ja avtomaticheskoj defekto- skopicheskoj ustanovkoj, razrabotannoj v ChSSR. Ustanovka sostoit iz podvizhnogo meha- nizma i ul'trazvukovogo defektoskopa UID-A2, razrabotannogo v ChSSR. Ustanovka otli- chaetsja rjadom novyh jelementov. Vlijanie rasstojanija na vysotu vspleska signala defekta kompensirovano, i vysota ostaetsja postojannoj. Takzhe kompensirovano vlijanie neravno- mernosti akusticheskoj svjazi, prichem datchik dzet impul'sy na distancionnoe registriruju- shhee ustrojstvo. Razmer defekta ocenivaetsja pri pomoshhi atenuatora. V nastojashhee vremja razrabatyvaetsja avtomaticheskoe ustrojstvo , pozvoljajushhee kontrolirovat' vertikal'nye cilindricheskie poverhnosti. Montazhnye svarnye shvy po okruzhnosti nuzhno kontrolirovat' pri povyshennoj tempera- ture. Nazavodah im. V.I. Lenina v g . Pl'zen' dlja jetih celej byl razrabotan special'nyj datchik, pozvoljajushhij osushhestvljat' kontrol' s bol'shoj tochnost'ju pri povyshennoj tempera- ture . Nedestruktivnyj kontrol' svarnyh konstrukcij provoditsja takzhe prosvechivaniem.Ne- bol'shie tolshhiny i korni prodol'nogo svarnogo shva pri povyshennoj temperature kontroliru- jutsja rentgenom s krugovoj harakteristikoj izluchenija pri ispol'zovanii osobyh kasset. Pri prosvechivanii bol'shih tolshhin svarnyh soedinenij ispol'zujutsja betatrony chehoslovackogo proizvodstva. Daetsja opisanie metodiki ispytanij i poluchennyh rezul'tatov. Betatron chehoslovackogo proizvodstva 15 Mjev sravnivaetsja s betatronom firmy Simens. (author)

Limitations of Ir{sup 192} as a Radiographic Source for the Control of Reactor Pressure-Vessels; Limitations de {sup 192}Ir en Tant que Source pour l'Examen Radiographique des Caissons Etanches de Reacteurs; Nedostatki Iridiya-192 v kachestveradiograficheskogo istochnika dlya kontrolya za korpusami reaktorov vysokogodavleniya; Limitaciones del {sup 192}Ir como Fuente Radiografica en el Control de Recipientes de Presion para Reactores

Energy Technology Data Exchange (ETDEWEB)

Horvat, D. [Nuclear Institute ' ' J. Stefan' ' Ljubljana, Yugoslavia (Slovenia)

1965-09-15

Published data and the results of our own investigations have shown that the advantage of Ir{sup 192} with regard to the quality of radiographs is obvious when comparing it with Co{sup 60} even with thicknesses over 80 mm of irradiated steel. The application of Ir{sup 192} in practice is limited by the alternative: either a very long exposure time or a source of very high activity. Where the exposure (Ci. min) for 1 m of radiographed weld is plotted against the specific activity of the source, diagrams show that, for practically attainable specific activities kilo-curie sources must be used for greater thicknesses. For such sources, self-absorption may become an important factor. An analysis of the influence of self-absorption causing a reduction of the source effectiveness and the filtration effect in the source is made by determining an equivalent increase of thickness of irradiated steel and by calculating the effective linear absorption coefficient as a function of the source dimensions and the thickness of the irradiated steel. Even in cases of relatively large source dimensions the filtration effect does not diminish the effective linear absorption coefficient to such an extent that the advantage in quality against Co{sup 60} would be lost. Possibilities of improvement due to a new shape of radiographic sources are discussed. In the case of narrow primary beams these new sources give smaller effective dimensions and allow shorter source-to-film distances. A further advantage of Ir{sup 192} is obvious from the diagrams of the weight of the exposure equipment for Ir{sup 192} and Coso taking in account equivalent activities of both sources regarding the same exposure time. The economic disadvantages, because of the short half-life,of Ir{sup 192} are discussed and a rough economical comparison between Co{sup 60} and Ir{sup 192} at different extensiveness and densities of the radiographic control is given. (author) [French] Les donnees publiees et les resultats des etudes faites par l'auteur montrent que, pour ce qui est de la qualite des radiographies,{sup 192}Ir presente un avantage tres net sur {sup 60}Co, meme pour des epaisseurs d'acier irradie superieures a 80 mm. Dans la pratique, l'emploi de {sup 192}Ir est limite parce qu'il faut un temps d'exposition tres long ou une source tres intense. Des diagrammes donnent, en fonction de l'activite specifique de la source, le temps d'exposition necessaire pour radiographier une soudure de 10 cm; ces diagrammes montrent que, compte tenu des activites specifiques que l'on peut obtenir dans la pratique, il faut des sources de l'ordre du kilocurie pour des epaisseurs plus importantes. Pour de telles sources, l'auto-absorption peut devenir un facteur important. Onanalysel'influence de l'auto-absorption, qui reduit l'efficacite de la source, et l'effet de filtration dans la source en determinant l'augmentation correspondante de l'epaisseur d'acier irradie et en calculant le coefficient reel d'absorption lineique en fonction des dimensions de la source et de l'epaisseur d'acier irradie. Meme lorsque les dimensions de la source sont relativement importantes, l'effet de filtration ne diminue pas le coefficient reel d'absorption lineique au point de faire disparaitre l'avantage de {sup 192}Ir sur {sup 60}Co quant a la qualite de la radiographie. L'auteur examine les possibilites d'amelioration grace a. une forme nouvelle des sources. Ces nouvelles sources donnent, dans le cas de faisceaux primaires etroits, des dimensions efficaces plus reduites et permettent de diminuer la distance source-film. Un autre avantage de {sup 192}Ir ressort nettement des diagrammes donnant le poids des appareils de radiographie avec {sup 192}Ir et {sup 60}Co, compte tenu de l'intensite de la source dans chaque cas pour obtenir un meme temps d'exposition. L'auteur discute les desavantages de {sup 192}Ir sur le plan economique, du fait de sa courte periode; sur ce meme plan, il compare approximativement Registered-Sign Degree-Sign Co et {sup 192}Ir suivant la sensibilite et la precision desirees lors de l'examen radiographique. (author) [Spanish] Los datos publicados en la literatura y los resultados de las investigaciones del autor han puesto de manifiesto las ventajas evidentes que el {sup 192}Ir presenta sobre el {sup 60}Co en cuanto a la calidad de las radiografias obtenidas, aun con espesores de acero superiores a 80 mm. En la practica, la aplicacion del {sup 192}Ir esta supeditada a la siguiente alternativa: exposicion sumamente prolongada, o bien empleo de una fuente de actividad muy elevada. Si se representa graficamente la exposicion (Ci x min) correspondiente a 1 m de soldadura radiografiada, en funcion de la actividad especifica de la fuente, se observa que para espesores superiores a 80 mm y con las actividades especificas alcanzables en la practica, es necesario usar fuentes del orden del kilocurie. En ellas, la autoabsorcion puede llegar a ser un factor de importancia. Se analizan en la memoria la disminucion que la autoabsorcion provoca en la eficacia de la fuente y el efecto de filtracion en la misma; para ello se determina un aumento equivalente en el espesor del acero y se calcula el coeficiente de absorcion lineal efectiva en funcion de las dimensiones de la fuente y del espesor del acero irradiado. Aun tratandose de fuentes de dimensiones relativamente grandes, el efecto de diltracion no provoca en el coeficiente de absorcion lineal efectiva una disminucion capaz de anular las ventajas respecto del {sup 60}Co. Se analizan en el trabajo las posibilidades de mejora debidas al empleo de fuentes radiograficas modificadas. En el caso de haces primarios angostos, estas nuevas fuentes dan menores dimensiones efectivas y permiten trabajar con menores distancias entre fuente y pelicula. Otra ventaja del {sup 192}Ir se observa al comparar los pesos de los equipos necesarios para el {sup 192}Ir y para el {sup 60}Co, tomando en cuenta actividades equivalentes de ambas fuentes para igual tiempo de exposicion. Se analizan en el trabajo las desventajas economicas del {sup 192}Ir debidas a su corto periodo, y se presenta una comparacion economica aproximada entre {sup 60}Co y {sup 192}Ir para diferentes espesores y densidades del control radiografico. (author) [Russian] Opublikovannye dannye i rezul'taty nashih sobstvennyh issledovanij pokazali, chto preimushhestvo iridija-192 v otnoshenii kachestva rentgenovskih snimkov javljaetsja ochevidnym po sravneniju s kobal'- tom-60 dazhe pri Julpine obluchaemoj stali svyshe 80 mm. Primenenie iridija-192 na praktike ogranichivaetsja al'ternativoj: ili trebuetsja ochen' dlitel'noe vremja obluchenija ili istochnik ochen' vysokoj aktivnosti. Diagrammy, gde vychercheno obluchenie, vyrazhennoe v kjuri v minutu dlja odnogo metra radiografirovannoj svarki v otnoshenii udel'noj aktivnosti istochnika, pokazyvajut, chto v otnoshenii prakticheski dostupnyh udel'nyh aktivnostej istochniki v kilokjuri prihoditsja ispol'zovat' dlja bol'shej tolshhiny. Dlja takih istochnikov samopogloshhenie mozhet stat' vazhnym faktorom. Analiz vlijanija samopogloshhenija, vyzyvajushhego snizhenie jeffektivnosti istochnika i jeffektov fil'tracii v istochnike, proizvoditsja putem opredelenija jekvivalentnogo uvelichenija tolshhiny obluchaemoj stali i putem rascheta kojefficienta jeffektivnogo linejnogo pogloshhenija v kachestve funkcii razmerov istochnika i tolshhiny obluchaemoj stali. Dazhe v sluchajah s razmerami sravnitel'no krupnyh istochnikov jeffekt fil'tracii ne umen'shaet kojefficient jeffektivnogo linejnogo pogloshhenija v takoj stepeni, chtoby proishodila uterja preimushhestva v kachestve po sravneniju s kobal'tom-60. Obsuzhdajutsja vozmozhnosti uluchshenija v svjazi s novoj konfiguraciej radiograficheskih istochnikov. Jeti novye istochniki dajut v sluchae uzkih pervichnyh puchkov men'shie jeffektivnye razmery i dopuskajut men'shie rasstojanija mezhdu istochnikom i plenkoj. Drugoe preimushhestvo iridija-192 vidno iz diagramm vesa oborudovanija dlja obluchenija dlja iridija-192 i kobal'ta-60, uchityvaja jekvivalentnye aktivnosti oboih istochnikov v otnoshenii togo zhe samogo vremeni obluchenija. Obsuzhdae.tsja vopros ob jekonomicheskih nedostatkah iridija-192 vvidu ego korotkogo perioda poluraspada, i daetsja gruboe jekonomicheskoe sravnenie jeffektivnosti kobal'ta-60 i iridija-192 pri razlichnyh diapazonah i plotnostjah radiograficheskogo kontrolja. (author)

Elements of a thermic method of preparing beta-sources with fused carriers, including strontium-90; Elements d'une methode thermique de preparation de sources beta avec des entraineurs fondus, y compris le strontium-90; Osnovy termicheskogo metoda prigotovleniya beta-istochnikov s plavlennymi nositelyami, vklyuchayushchimi strontsij-90; Bases de un metodo termico de preparacion de fuentes beta con portadores fundidos, incluido el estroncio-90

Energy Technology Data Exchange (ETDEWEB)

Bogdanov, N I; Zakharova, K P; Zimakov, P V; Kulichenko, V V

1962-01-15

avtomaticheskogo kontrolya i regulirovaniya proizvodstvennykh protsessov. Tekhnologicheskij protsess izgotovleniya istochnikov osnovan na obezvozhivanii smesi, sostoyashchej iz radioaktivnogo rastvora azotnokislogo strontsiya i komponentov tipa bornogo angidrida, okisi kremniya, okisi alyuminiya i dr. Termicheskaya obrabotka obezvozhennoj smesi pri vysokoj temperature privodit k obrazovaniyu legkopodvizhnogo rasplava, posle okhlazhdeniya kotorogo poluchaetsya steklovidnaya massa, vklyuchayushchaya v sebya neobkhodimye kolichestva radioizotopa Sr{sup 90}. Privodyatsya dannye i obsuzhdayutsya rezul'taty issledovaniya protsessa obezvozhivaniya sistemy SrO-B{sub 2}O{sub 3}-SiO{sub 2} v intervale temperatur' 100 - 1000{sup o} i obosnovyvaetsya vybor osnovnykh parametrov tekhnologicheskogo protsessa. Izlagayutsya osnovy metoda naneseniya steklovidnogo preparata s neobkhodimym kolichestvom radioizotopa Sr{sup 90} na podlozhki razlichnykh form i razmerov iz stali, keramiki i drugikh materialov. Rassmatrivayutsya osnovnye parametry, kharakterizuyushchie nadezhnost' i bezopasnost' v ehkspluatatsii razlichnykh tipov istochnikov i privodyatsya dannye po istochnikam na osnove Sr{sup 90}, izgotavlivaemym termicheskim metodom. (author)

Sorption/desorption reversibility of polycyclic aromatic hydrocarbons (PAHs) in soils and carbonaceous materials

Energy Technology Data Exchange (ETDEWEB)

Wang, Guohui

2008-07-01

Understanding sorption/desorption is an important prerequisite for the prediction of fate and transport of pollutants in the environment. During the last two decades, numerous studies have reported hysteresis phenomenon for the interaction of hydrophobic organic contaminants (HOCs) with natural organic matter (NOM). It manifests as nonsingular sorption/desorption isotherms or different rates for sorption and desorption, where during desorption a higher affinity of a compound on a given sorbent and a longer time scale for release than for sorption is observed. Other studies showed that some of the reported sorption/desorption hysteresis phenomena are due to experimental artifacts, mainly resulting from non-attainment of sorption equilibrium before desorption experiments, which result in 'pseudo-hysteresis'. Except for the hypothesis of sorbent reconfiguration, clear experimental evidence for the physical or chemical mechanisms proposed to lead to hysteresis is still lacking. In this study, sorption/desorption equilibrium and kinetics of phenanthrene sorption/desorption from two soils and three carbonaceous samples were investigated using both batch and column techniques. The main objective of this work was to monitor hysteresis phenomenon by carefully recovering the solute mass in the system and to compare sorption/desorption equilibria and kinetics thermodynamically. Nonsingular isotherms and higher desorption enthalpies as well as increased activation energies with proceeding desorption are expected if significant hysteresis exists. Sorption-desorption cycles were carried out to compare equilibrium isotherms and associated sorption/desorption enthalpies (AeH, isosteric heats). Instead of the traditional decant-and-refill batch method, the experiments were conducted using a newly designed batch protocol, which enables the determination of sorption/desorption isotherms at different temperatures using a closed batch system. This method additionally allows

Sorption/desorption reversibility of polycyclic aromatic hydrocarbons (PAHs) in soils and carbonaceous materials

Energy Technology Data Exchange (ETDEWEB)

Wang, Guohui

2008-07-01

Understanding sorption/desorption is an important prerequisite for the prediction of fate and transport of pollutants in the environment. During the last two decades, numerous studies have reported hysteresis phenomenon for the interaction of hydrophobic organic contaminants (HOCs) with natural organic matter (NOM). It manifests as nonsingular sorption/desorption isotherms or different rates for sorption and desorption, where during desorption a higher affinity of a compound on a given sorbent and a longer time scale for release than for sorption is observed. Other studies showed that some of the reported sorption/desorption hysteresis phenomena are due to experimental artifacts, mainly resulting from non-attainment of sorption equilibrium before desorption experiments, which result in 'pseudo-hysteresis'. Except for the hypothesis of sorbent reconfiguration, clear experimental evidence for the physical or chemical mechanisms proposed to lead to hysteresis is still lacking. In this study, sorption/desorption equilibrium and kinetics of phenanthrene sorption/desorption from two soils and three carbonaceous samples were investigated using both batch and column techniques. The main objective of this work was to monitor hysteresis phenomenon by carefully recovering the solute mass in the system and to compare sorption/desorption equilibria and kinetics thermodynamically. Nonsingular isotherms and higher desorption enthalpies as well as increased activation energies with proceeding desorption are expected if significant hysteresis exists. Sorption-desorption cycles were carried out to compare equilibrium isotherms and associated sorption/desorption enthalpies (AeH, isosteric heats). Instead of the traditional decant-and-refill batch method, the experiments were conducted using a newly designed batch protocol, which enables the determination of sorption/desorption isotherms at different temperatures using a closed batch system. This method additionally allows the

Some Possibilities of the Eddy-Current Method for Multi-Parameter Testing of Structural Components; Quelques Possibilites Offertes par la Methode des Courants de Foucault pour le Controle de Nombreux Parametres des Elements de Construction; Nekotorye vozmozhnosti metoda vikhrevykh tokov dlya mnogoparametrovogo kontrolya ehlementov konstruktsij; Algunas Posibilidades que Brinda el Metodo de las Corrientes de Foucault para Controlar Numerosos Parametros de los Elementos de Construccion

Energy Technology Data Exchange (ETDEWEB)

Vjahorev, V. G.; Gerasimov, V. G.; Deniskin, V. P.; Trahtenberg, L. I.; Shkarlet, Ju. M. [Gosudarstvennyj Komitet po Ispol' zovaniju Atomnoj Jenergii SSSR, Moskva, SSSR (Russian Federation)

1965-09-15

The paper discusses the pattern of occurrence of problems of non-destructive multiparameter testing in nuclear technology and the advisability of approaching these problems by the eddy-current method. The application of electric models is justified for solving testing problems using a long follow-through coil. Design formulae are given and the principles of designing applied eddy-current probes are explained. An arrangement for testing tube-wall thickness is described: in this apparatus the effect of movement of the tube under testing on the measurement results is eliminated with the aid of a servo-system controlled by a signal depending on the probe voltage phase. The paper describes how a self-oscillating circuit containing a test-coil is used as the probe of an apparatus for testing tubes. On the basis of calculated and experimental data various possibilities are indicated for the construction of single-frequency applied eddy-current testing probes for simultaneous measurement of more than two parameters. (author) [French] Les auteurs montrent que les problemes du controle non-destructif de plusieurs parametres en technologie nucleaire surgissent selon certaines lois et que la methode des courants de Foucault convient particulierement a la solution de plusieurs d'entre eux. Ils justifient l'utilisation de modeles electriques pour la solution des problemes de controle au moyen d'une longue bobine creuse. Us donnent des formules et exposent une methode pour le calcul de detecteurs a courants de Foucault. Us decrivent le schema d'un dispositif permettant de verifier l'epaisseur des parois de tubes, dans lequel le deplacement du tube a controler n'exerce aucune influence sur les resultats des mesures grace a l'emploi d'un moniteur actionne par un signal qui depend de la phase de tension du detecteur. Comme detecteur, on a employe un dispositif destine au controle des tubes d'un autogenerateur, apres avoir inclus dans son circuit une bobine d'essai. En partant des donnees calculees et experimentales, les auteurs indiquent diverses possibilites de realisation de detecteurs a courants de Foucault de frequence unique permettant le controle avec modification simultanee de plusieurs parametres. (author) [Spanish] Los autores demuestran que los problemas del control no destructivo de diversos parametros se plantean en la tecnologia nuclear segun ciertas leyes y que el metodo de las corrientes de Foucault se adapta particularmente a la solucion de varios de esos problemas. Los autores justifican la utilizacion de modelos electricos para resolver problemas de control con ayuda de una larga bobina hueca. Presentan formulas y exponen un metodo para el calculo de detectores a base de corrientes parasitas. Describen un dispositivo que permite verificar el espesor de las paredes de tubos; en este dispositivo, el desplazamiento del tubo a controlar no ejerce influencia alguna sobre los resultados de las mediciones, gracias al empleo de un monitor accionado por una senal dependiente de la fase de tension del detector. En calidad de detector se ha empleado un dispositivo destinado al control de los tubos de un autogenerador despues de haber incluido en su circuito una bobina de ensayo. Partiendo de datos calculados y experimentales, los autores senalan diversas posibilidades de realizacion de detectores a base de corrientes de Foucault de frecuencia unica, que permiten efectuar el control con modificacion simultanea de varios parametros. (author) [Russian] Pokazana zakonomernost' voznikno- venija zadach o nerazrushajushhem mnogoparametrovom kontrole v jadernoj tehnologii i celeso- obraznost' reshenija nekotoryh iz nih metodom vihrevyh tokov. Obosnovano primenenie jelektricheskih modelej dlja reshenija zadach kontrolja s ispol'zovaniem dlinnoj prohodnoj katushki. Privodjatsja raschetnye formuly i izlagaetsja metodika rascheta nakladnyh toko- vihrevyh datchikov. Opisana shema pribora dlja kontrolja tolshhiny stenki trub, v kotorom vlijanie pereme- shhenij kontroliruemoj truby na rezul'taty izmerenij ustranjaetsja putem primenenija sledja- shhej sistemy, upravljaemoj signalom, zavisjashhim ot fazy naprjazhenija datchika. Soobshhaetsja o primenenii v kachestve datchika pribora dlja kontrolja trub avtogenera- tora, s vkljuchennoj v ego kontur ispytatel'noj katushkoj. Na osnove raschetnyh i jeksperimental'nyh dannyh pokazany nekotorye vozmozhnosti postroenija odnochastotnyh tokovihrevyh nakladnyh datchikov dlja kontrolja pri odnovremen- nom izmenenii bolee chem dvuh parametrov. (author)

The System for Controlling Source and Special Nuclear Material at the Eurochemic Reprocessing Plant; Systeme de Controle des Matieres Nucleaires Brutes et Speciales a l'Usine de Traitement D'Eurochemic; Sistema kontrolya nad iskhodnym i spetsial'nym yadernym materialom na zavode evrokhimicheskoj kompanii po regeneratsii yadernogo topliva; Control de Materiales Nucleares Basicos y de Materiales Fisionables Especiales en la Planta de Regeneracion de la Eurochemic

Energy Technology Data Exchange (ETDEWEB)

Frenzel, W.; Schueller, W. [EUROCHEMIC, MOL (Belgium)

1966-02-15

Eurochemic is constructing a reprocessing plant near Mol (Belgium). The main characteristics of the plant and the different process steps are summarized. To maintain proper control of source and special nuclear material, the facilities of the company are divided into material balance areas. All transfers into and out of these areas are determined. Depending on their significance for the overall material balance, different precision requirements have been established according to a scale of significance which is briefly discussed. To adjust the book balance, physical inventories are periodically performed. The corresponding inventory procedures are outlined. The books used for nuclear materials accounting and the principles of the accounting system are summarized. (author) [French] La societe Eurochemic fait actuellement construire une usine de traitement chimique pres de Mol (Belgique). L'auteur indique succinctement les principales caracteristiques de l'usine et les differentes etapes du traitement. Pour assurer un controle correct des matieres nucleaires brutes et speciales, les installations d'Eurochemic sont divisees en secteurs de mesures. Tous les transferts entre ces secteurs de mesure sont determines quantitativement. Les mesures sont faites avec des degres de precision differents qui ont ete fixes en fonction de leur importance pour le bilan matieres general; les auteurs examinent brievement les criteres appliques a cette fin. Pour verifier le bilan, on procede periodiquement a des inventaires materiels. La facon dont sont menes ces inventaires est exposee dans ses grandes lignes. Les auteurs indiquent les livres utilises pour la comptabilite des matieres nucleaires et resument les principes du systeme comptable. (author) [Spanish] La compania Eurochemic esta construyendo una planta de regeneracion en Mol (Belgica). Los autores resumen las principales caracteristicas de la instalacion, y las distintas fases del proceso industrial. Para mantener un control adecuado de los materiales nucleares basicos y de los materiales fisionables especiales, las instalaciones de la compaliia estaran divididas en diversas zonas de balance de materiales. Toda entrada y salida de materiales de estas zonas quedara registrada. Teniendo en cuenta su importancia en relacion con el balance global de materiales, se han fijado distintos requisitos en materia de precision basados en una escala de valores que los autores describen brevemente. Periodicamente se efectuaran inventarios de material a fin de proceder al balance de asientos. Se exponen los correspondientes procedimientos de inventario. Los autores describen los libros utilizados en la contabilidad de los materiales nucleares y enuncian los principios en que se basa el sistema de contabilidad. (author) [Russian] Kompanija Evrohimik v nastojashhee vremja stroit zavod po pererabotke jadernogo topliva okolo Molja (Bel'gija). Summirujutsja glavnye harakteristiki zavoda i razlichnyh stadij obrabotki. Dlja provedenija nadlezhashhego kontrolja nad ishodnym i special'nym jadernym materialom ustanovki kompanii razdeleny na zony material'nogo balansa. Opredeljajutsja vse peremeshhenija v jeti zony i iz nih. B zavisimosti ot vazhnosti jetih materialov dlja obshhego material'nogo balansa ustanovleny razlichnye trebovanija v otnoshenii tochnosti v sootvetstvii so shkaloj vazhnosti, kotoraja kratko opisyvaetsja. Dlja pravil'nogo sostavlenija zhurnal'nogo balansa periodicheski provodjatsja fizicheskie inventarizacii. Izlagajutsja sootvetstvujushhie metody inventarizacii. Daetsja kratkoe opisanie zhurnalov ucheta jadernyh materialov i principov sistemy u cheta. (author)

Radioactive apparatus for measuring the thickness of hot sheet-metal; Jauge d'epaisseur radioactive pour la mesure a chaud de plaques metalliques; Radioaktivnyj izmeritel' tolshchiny goryachego listovogo prokata; Calibrador radiactivo para la medicion en caliente de chapas

Energy Technology Data Exchange (ETDEWEB)

Vasichev, B N; Latyshev, V K; Pliskin, Yu S; Felinger, A K

1962-01-15

}Cs de actividad equivalente a la de 9,2 g de radio, es posible medir el espesor de chapas calientes del espesor mencionado con un margen de aproximacion de {+-} 0,1 mm. El aparato efectua las mediciones a razon de una por segundo y funciona satisfactoriamente en las condiciones que exigen las operaciones de laminado. (author) [Russian] Dlya polucheniya vysokoj tochnosti izmerenij v usloviyakh prokatnogo proizvodstva vybran dinamicheskij metod kompensatsii, pri kotorom parametr sravneniya prokhodit vse znacheniya v izmeryaemoj oblasti, a nul'-organ otmechaet lish' moment ravenstva izmeryaemogo parametra i parametra sravneniya. Ispol'zovanie ehtogo metoda dalo vozmozhnost' osvobodit'sya ot mekhanicheskikh obratnykh svyazej i peremennykh po svoemu kharakteru peremeshchenij, svojstvennykh metodu staticheskoj kompensatsii, i sozdat' pribor, udovletvoryayushchij kak trebovaniyam tochnosti, tak i bystrodejstviya v slozhnykh usloviyakh prokatnogo proizvodstva. V doklade izlagaetsya printsipial'naya skhema pribora dlya kontrolya tolshchiny lista v protsesse prokatki, rassmatrivayutsya faktory, vliyayushchie na tochnost' izmereniya tolshchiny goryachego lista (temperatura, volnistost', nalichie vody na poverkhnosti lista, material lista i ego polozhenie na rol'gange). Opisyvaetsya konstruktivnoe vypolnenie opytno-promyshlennogo obraztsa pribora na diapazone tolshchin ot 14 mm do 44 mm. Promyshlennye ispytaniya pribora pokazali, chto pri istochnike izlucheniya Cs{sup 137} aktivnost'yu 9,2 g-ehkv. radiya tochnost' izmereniya tolshchiny goryachego lista v ukazannom vyshe diapazone sostavlyaet {+-}0,1 mm. Bystrodejstvie pribora - odno izmerenie v sekundu. Pribor nadezhno rabotaet v usloviyakh prokatnogo tsekha. (author)

A reward semi-Markov process with memory for wind speed modeling

Science.gov (United States)

Petroni, F.; D'Amico, G.; Prattico, F.

2012-04-01

-order Markov chain with different number of states, and Weibull distribution. All this model use Markov chains to generate synthetic wind speed time series but the search for a better model is still open. Approaching this issue, we applied new models which are generalization of Markov models. More precisely we applied semi-Markov models to generate synthetic wind speed time series. The primary goal of this analysis is the study of the time history of the wind in order to assess its reliability as a source of power and to determine the associated storage levels required. In order to assess this issue we use a probabilistic model based on indexed semi-Markov process [4] to which a reward structure is attached. Our model is used to calculate the expected energy produced by a given turbine and its variability expressed by the variance of the process. Our results can be used to compare different wind farms based on their reward and also on the risk of missed production due to the intrinsic variability of the wind speed process. The model is used to generate synthetic time series for wind speed by means of Monte Carlo simulations and backtesting procedure is used to compare results on first and second oder moments of rewards between real and synthetic data. [1] A. Shamshad, M.A. Bawadi, W.M.W. Wan Hussin, T.A. Majid, S.A.M. Sanusi, First and second order Markov chain models for synthetic gen- eration of wind speed time series, Energy 30 (2005) 693-708. [2] H. Nfaoui, H. Essiarab, A.A.M. Sayigh, A stochastic Markov chain model for simulating wind speed time series at Tangiers, Morocco, Re- newable Energy 29 (2004) 1407-1418. [3] F. Youcef Ettoumi, H. Sauvageot, A.-E.-H. Adane, Statistical bivariate modeling of wind using first-order Markov chain and Weibull distribu- tion, Renewable Energy 28 (2003) 1787-1802. [4]F. Petroni, G. D'Amico, F. Prattico, Indexed semi-Markov process for wind speed modeling. To be submitted.

Administrative Co-ordination of Fissile Material Management and Accounting in the U.K.A.E.A; Coordination Administrative de la Gestion et de la Comptabilite des Matieres Fissiles dans les Etabussements de l'Autorite de l'Energie Atomique du Royaume-Uni; Administrativnaya koordinatsiya kontrolya i ucheta delyashchikhsya materialov v upravlenii po atomnoj ehnergii soedinennogo korolevstva; Coordinacion Administrativa de la Gestion y la Contabilidad de Materiales Fisionables en la Comision de Energia Atomica del Reino Unido

Energy Technology Data Exchange (ETDEWEB)

Hood, St. C.C. [United Kingdom Atomic Energy Authority, London (United Kingdom)

1966-02-15

The Authority are engaged as suppliers in fissile material production, distribution, recycle and reprocessing. As consumers, the Authority require fissile material for power reactors, a variety of prototypes, MTRs, zero-energy facilities and fuel development projects; and for other experimental and research purposes in laboratory quantities. Executive responsibility for these activities lies with the four Groups through which the Authority discharge these functions. It has been found useful to keep these activities under review in specialized inter-Group Committees, with a common secretariat. These Committees: (a) study all projects all proposals or work involving significant quantities of fissile material (plutonium and enriched uranium, other than natural U or U depleted in {sup 235}U) in the light of expected supplies over a number of years from all sources, including new production, scrap recovery and imports; and all uses including burn-up, losses and exports; (b) recommend the optimum allocation of specific amounts for approved purposes in relation to other calls upon available supplies, and having regard to the economic issues involved; (c) record and progress all approved allocations, and examine the nature, amount and purpose of all existing stockholdings in relation to current policies and objectives; (d) record and study all losses of fissile material during fabrication or other processing and the measures taken to reduce them; (e) assist in developing procedures and incentives to ensure that material is used economically and returned promptly. Each Group has considerable autonomy in its day-to-day use of fissile material. The administrative machinery described above provides a means by which the Authority's scientists, engineers, accountants and administrators concerned with fissile material problems can operate collectively in a common frame of reference with a minimum of paperwork. The paper is illustrated with a simplified flowsheet of the main flows of fissile material within the Authority for civil purposes during the year ending 31.3.65. (author) [French] En tant que fournisseur, l'Autorite s'occupe de la production, de la distribution, du recyclage et du traitement chimique des matieres fissiles. En tant que consommateur, elle a besoin de matieres fissiles pour ses reacteurs de puissance, pour une serie de prototypes, pour ses reacteurs d'essai des materiaux, pour ses reacteurs de puissance zero et pour ses travaux de mise au point de combustibles; il lui en faut egalement, en petites quantites, pour ses experiences et ses recherches en laboratoire. L'Autorite confie a quatre groupes la direction de ces. activites. Elle a juge utile de faire suivre regulierement ces activites par des comites specialises intergroupes ayant un secretariat commun. Ces comites ont les attributions suivantes: a) etudier tous travaux ou projets de travaux qui necessitent l'utilisation de quantites importantes de matieres fissiles (plutonium et uranium enrichi a l'exclusion de l'uranium naturel ou de l'uranium appauvri en uranium-235), en tenant compte de tous les approvisionnements prevus pendant un certain nombre d'annees en provenance de toutes sources, y compris la production sur place, la recuperation des dechets et les importations; en tenant compte aussi de toutes les utilisations, y compris la combustion, les pertes et les exportations; b) recommander, compte tenu des autres besoins en matieres disponibles et des imperatifs economiques, la meilleure attribution possible de quantites determinees destinees a des fins agreees; c) enregistrer toutes les attributions approuvees de matieres et suivre leur utilisation, et etudier la nature, les quantites et la destination de tous les stocks existants en tenant compte des directives en vigueur et des objectifs poursuivis; d) enregistrer et etudier toutes les pertes de matieres fissiles en cours de fabrication ou de traitement ainsi que les mesures prises pour les reduire; e) aider a mettre au point des procedures et des methodes permettant d'assurer que les matieres sont utilisees de facon economique et renvoyees rapidement. Chaque groupe dispose d'une assez large autonomie en ce qui concerne l'utilisation courante des matieres fissiles. Le systeme administratif precedemment decrit permet aux savants et ingenieurs de l'Autorite, ainsi qu'aux comptables et administrateurs charges de resoudre les problemes relatifs aux matieres fissiles, de travailler collectivement dans un cadre commun en ayant a etablir un minimum de documents. Le memoire est illustre par un diagramme simplifie indiquant les principaux circuits d'operations concernant des matieres fissiles destinees a des fins civiles et traitees dans les etablissements de l'Autorite au cours de l'annee se terminant le 31 mars 1965. (author) [Spanish] La Comision de Energfa Atomica del Reino Unido suministra y consume materiales fisionables: por una parte, tiene a su cargo la produccion, la distribucion , el reciclado y la regeneracion de dichos materiales y, por otra, los necesita para reactores de potencia, prototipos, reactores de ensayo de materiales, instalaciones de potencia cero y proyectos de desarrollo de nuevos combustibles; los utiliza tambien, en cantidades menores, para otros fines experimentales y de investigacion. En lo que respecta a esas actividades, la responsabilidad ejecutiva recae en los cuatro Grupos por mediacion de los cuales la Comision desempena sus funciones. Se ha encontrado conveniente someter todas las actividades mencionadas a la fiscalizacion de comites mixtos de estos Grupos, con una secretaria comun. Dichos comites: a) estudian todos los proyectos y propuestas que requieren el empleo de cantidades importantes de materiales fisionables (plutonio, uranio enriquecido, etc., con exclusion del uranio natural y del uranio empobrecido en {sup 235}U) teniendo en cuenta los suministros que durante un periodo de varios anos se espera recibir de todas las fuentes - produccion, recuperacion de desechos, importacion - y todas las cantidades empleadas, incluidos los materiales agotados, las perdidas y las exportaciones; b) recomiendan la mejor manera de asignar cantidades determinadas de materiales para fines aprobados, teniendo en cuenta el conjunto de las necesidades, el volumen de las existencias y los aspectos economicos de la operacion; c) registran y controlan todas las asignaciones aprobadas; en relacion con los criterios y los objectivos establecidos, verifican la naturaleza de los materiales que se estan utilizando, sus cantidades, y los fines a que se les destina; d) registran y estudian todas las perdidas de material fisionable que se producen durante los procesos de elaboracion y tratamiento, asf como las medidas adoptadas para evitar dichas perdidas; e) contribuyen a establecer procedimientos y a crear incentivos para lograr que los materiales se empleen con economia y se devuelvan con rapidez. (author) [Russian] Kak postavshhik deljashhihsja materialov Upravlenie po atomnoj jenergii zanimaetsja ih proizvodstvom, raspredeleniem i pererabotkoj. Upravleniju, kak potrebitelju, deljashhiesja materialy nuzhny dlja ispol'zovanija v kachestve topliva v opytnyh jenergeticheskih reaktorah razlichnyh tipov, reaktorah dlja ispytanija materialov, issledovatel'skih reaktorah nulevoj moshhnosti, v rabotah po sozdaniju novyh tipov teplovydeljajushhih jelementov, a takzhe dlja provedenija laboratornyh jeksperimentov i issledovanij. Ispolnitel'nye funkcii po jetim vidam dejatel'nosti vozlozheny na chetyre strukturnyh podrazdelenija upravlenija (gruppy). Bylo najdeno poleznym derzhat' jeti vidy dejatel'nosti pod nabljudeniem special'nyh mezhgruppovyh komitetov s obshhim sekretariatom. Jeti komitety: a) zanimajutsja izucheniem vseh proektov ili predlozhenij otnositel'no rabot, svjazannyh so znachitel'nymi kolichestvami deljashhihsja materialov (plutonija i obogashhennogo urana pomimo prirodnogo urana ili obednennogo urana) v svete ozhidaemyh postavok za celyj rjad let v rezul'tate novogo proizvodstva, pererabotki skrapa i importa, a takzhe vseh vidov ispol'zovanija, v tom chisle vygoranija, poter' i jeksporta; b) vnosjat rekomendacii po voprosam vydachi deljashhihsja materialov dlja utverzhdennyh rabot v svjazi s drugimi trebovanijami otnositel'no imejushhihsja postavok s uchetom vozmozhnyh jekonomicheskih problem; c) vedut uchet vseh utverzhdennyh vydach, izuchajut harakter, kolichestva i celi vseh sushhestvujushhih zapasov v svjazi s provodimoj politikoj i zadachami; d) vedut uchet i izuchajut vse poteri deljashhihsja materialov vo vremja izgotovlenija ili drugih processov, a takzhe izuchajut mery, predprinjatye dlja sokrashhenija poter'; e) okazyvajut pomoshh' v razrabotke procedur i predlozhenij dlja togo, chtoby garantirovat', chto material ispol'zuetsja jekonomno i bystro vozvrashhaetsja. Kazhdaja gruppa obladaet znachitel'noj avtonomiej v ispol'zovanii deljashhihsja materialov dlja sobstvennyh povsednevnyh nuzhd. Vysheopisannaja administrativnaja mashina obespechivaet to, chto s ee pomoshh'ju uchenye, inzhenery, buhgaltery i administratory Upravlenija, svjazannye s problemami deljashhihsja materialov, mogut dejstvovat' kollektivno v obshhih ramkah soglasovannosti i s minimal'noj bumazhnoj volokitoj. V doklade privedena uproshhennaja shema osnovnyh potokov deljashhihsja materialov dlja mirnyh celej, prinjataja v Upravlenii po atomnoj jenergii v techenie goda, zakonchivshegosja 31 marta 1965 goda. (author)

Complex Hydride Compounds with Enhanced Hydrogen Storage Capacity

Energy Technology Data Exchange (ETDEWEB)

Mosher, Daniel A.; Opalka, Susanne M.; Tang, Xia; Laube, Bruce L.; Brown, Ronald J.; Vanderspurt, Thomas H.; Arsenault, Sarah; Wu, Robert; Strickler, Jamie; Anton, Donald L.; Zidan, Ragaiy; Berseth, Polly

2008-02-18

between alkaline metal hydrides (AmH), Alkaline earth metal hydrides (AeH2), alane (AlH3), transition metal (Tm) hydrides (TmHz, where z=1-3) and molecular hydrogen (H2). The effort started first with variations of known alanates and subsequently extended the search to unknown compounds. In this stage, the FPM techniques were developed and validated on known alanate materials such as NaAlH4 and Na2LiAlH6. The coupled predictive methodologies were used to survey over 200 proposed phases in six quaternary spaces, formed from various combinations of Na, Li Mg and/or Ti with Al and H. A wide range of alanate compounds was examined using SSP having additions of Ti, Cr, Co, Ni and Fe. A number of compositions and reaction paths were identified having H weight fractions up to 5.6 wt %, but none meeting the 7.5 wt%H reversible goal. Similarly, MSP of alanates produced a number of interesting compounds and general conclusions regarding reaction behavior of mixtures during processing, but no alanate based candidates meeting the 7.5 wt% goal. A novel alanate, LiMg(AlH4)3, was synthesized using SBP that demonstrated a 7.0 wt% capacity with a desorption temperature of 150°C. The deuteride form was synthesized and characterized by the Institute for Energy (IFE) in Norway to determine its crystalline structure for related FPM studies. However, the reaction exhibited exothermicity and therefore was not reversible under acceptable hydrogen gas pressures for on-board recharging. After the extensive studies of alanates, the material class of emphasis was shifted to borohydrides. Through SBP, several ligand-stabilized Mg(BH4)2 complexes were synthesized. The Mg(BH4)2*2NH3 complex was found to change behavior with slightly different synthesis conditions and/or aging. One of the two mechanisms was an amine-borane (NH3BH3) like dissociation reaction which released up to 16 wt %H and more conservatively 9 wt%H when not including H2 released from the NH3. From FPM, the stability of the Mg(BH4

Recent Advances in Low-Level Scintillation Counting of Tritium; Progres recents dans le comptage a scintillations de faibles teneurs en tritium; Poslednie dostizheniya v oblasti stsintillyatsionnogo scheta tritiya nizkogo urovnya; Progresos recientes en el recuento por centelleo de bajas concentraciones de tritio

Energy Technology Data Exchange (ETDEWEB)

Kaufman, W J; Nir, A; Parks, G; Hours, R M [University of California, Berkeley, CA (United States)

1962-01-15

obnaruzheno, chto vnutrennij istochnik kobal'ta-57 dostatochno khorosho kontroliruet ehffektivnost' scheta tritiya v predelakh ot 2 do 7% so standartnym otkloneniem v 0,1%. Po sravneniyu s predydushchimi metodami ehtot sposob imeet to preimushchestvo, chto pozvolyaet bystro opredelit' ehffektivnost' bez izmeneniya obraztsa. Dlya otsenki znacheniya lyuministsentnogo vzaimodejstviya i kosmicheskoj radiatsii bylo issledovano umen'shenie fona. Pri ehtom byl ispol'zovan s plastikovoj obolochkoj ehkran antisovpadeniya. Bylo takzhe izucheno dolgosrochnoe vliyanie iznosa obraztsa i drejfa schetnogo oborudovaniya na stabil'nost' sistemy. (author)

Production of Strontium-90 Thermal Power Sources; Fabrication de sources d'energie thermique au strontium-90; Proizvodstvo istochnikov ''teplovoj ehnergii iz Sr''9''0; Preparacion de fuentes de energia termica con estroncio-90

Energy Technology Data Exchange (ETDEWEB)

Cochran, J. S.; Bloom, J. L.; Schneider, A. [Martin Company, Nuclear Division, Baltimore 3, MD (United States)

1963-11-15

rajonakh. V ehtom smysle Sr{sup 90} priobretaet bol'shoe znachenie iz-za ego shirokoj dostupnosti, aktivnosti i toj sravnitel'noj legkosti, s kotoroj ego mozhno prevrashchat' v kompaktnye istochniki tepla. Generatory, rabotayushchie na Sr{sup 90} sluzhat v kachestve istochnikov pitaniya avtomaticheskikh meteorologicheskikh i navigatsionnykh stantsij; rassmatrivaetsya vozmozhnost' primeneniya Sr{sup 90} v kachestve istochnika ehnergii dlya dvigatelej kosmicheskikh korablej. Pri sravnitel'noj otsenke ryada strontsievykh soedinenij okazalos', chto naibolee tselesoobrazno ispol'zovat' titanat, tak kak on obladaet naibolee tsennymi svojstvami. Sr{sup 90}, otdelennyj ot drugikh produktov deleniya, ochishchaetsya do trebuemoj stepeni chistoty na predpriyatii Komissii po atomnoj ehnergii SSHA v Khehnforde i trasportiruetsya v vide karbonata v ''gorya- chuyu'' kameru(firmy ''Martin''), gde prevrashchaetsya v granulirovannyj titanat. V ehtom protsesse ispol'zuetsya distantsionnoe upravlenie, analogichnoe primenyaemomu v obychnom khimicheskom i keramicheskom proizvodstve. Granuly, zaklyuchennye v kapsuly, pomeshchayutsya v kontejnery tipa ''Khastellou C'' dlya primeneniya v ehnergeticheskikh ustanovkakh s termoehlektricheskim preobrazovaniem ehnergii. Zdes' prikhoditsya stalkivat'sya s neobychnymi ehkspluatatsionnymi problemami, tak kak bol'shie kolichestva obrabatyvaemogo Sr{sup 90} (milliony kyuri v god) obladayut strashnoj radioaktivnost'yu i sozdayut opasnost' zarazheniya. Opisano ustrojstvo prisposoblenij, oborudovaniya, kharakterizuyutsya tekhnologiya i tekhnika bezopasnosti. Opisyvayutsya dannye opyta, priobretennogo vo vremya nedavnej pererabotki pervykh 250 000 kyuri Sr{sup 90} v toplivo dlya generatora SNAP-7 (yadernaya batareya). Privodyatsya takzhe dannye po germetizatsii granul v kontejnerakh, po kalorimetrii, dezaktivatsii i metodike udaleniya otkhodov. (author)

Nuclear Materials Management in Relation to Safety and Criticality Control: A Study of Non-Inherently Safe Systems; La Gestion des Matieres Nucleaires dans ses Rapports avec la Securite et le Controle de la Criticite; Etude des Systemes a Securite Non Inherente; Obrashchenie s yadernymi materialami s uchetom bezopasnosti i kontrolya za kritichnost'yu. izuchenie sistem dopolnitel'noj avarijnoj zashchity; La Administracion de Materiales Nucleares y sus Relaciones con la Seguridad y el Control de la Criticidad; Estudio de los Sistemas de Seguridad No Inherente

Energy Technology Data Exchange (ETDEWEB)

Fruchard, Y. [Commissariat a l' Energie Atomique, Marcoule (France)

1966-02-15

The production, utilization and handling of certain fissionable materials are associated with a particular type of danger, the risk of criticality. The engineer must try to avoid this risk, at the least possible expense, without hindering too much the work of production or conversion. Roughly speaking, there are three ways of eliminating this risk: limitation of solution concentrations, limitation of mass, and judicious choice of geometries. The tendency is to employ the third method as much as possible, i.e. to operate with inherently safe systems. Nevertheless, non-inherently safe systems are still common in nuclear installations and recourse sometimes has to be had to the first or second procedure. These methods are bound up with nuclear materials management. In installations where small quantities of fissionable materials are handled it is often possible to ensure nuclear safety if the mass of fissionable material permitted in each room is less than the minimum critical mass. In larger installations this type of control, based entirely on materials management, becomes impossible. The paper considers the relation between management and nuclear safety in the special case of a plant for the aqueous processing of irradiated fuels (the fuels are based on natural uranium). From the point of view of criticality control such a plant comprises, broadly speaking, three sections: In the first section, where fairly dilute solutions are treated, the type of control required is that over concentration. This control (based on analysis and the use of neutron counters) is easy to carry out but it is difficult to ensure that no deposits are formed. Although experience has shown that there is no particular reason for fearing such deposits, the existence of a deficit in the material balance gives rise to apprehension in respect of criticality. In this section, materials management, still imperfectly carried out, is of prime importance for safety. The second section is where concentrated solutions and wet precipitates are treated. This is the realm of safe geometry. Materials management is of less direct interest here but is still an important factor as far as safety is concerned (where special action, cleaning of equipment, etc. is necessary). In the third section, for the treatment of dry products, control by mass is required and materials management presents no particular difficulty. An additional field which, although less, obvious, is nevertheless of paramount importance from the point of view of safety is that of recycling and waste processing. A look at the list of criticality accidents in the United States of America is sufficient to show that five out of six accidents were connected more or less directly with waste processing. If we examine these accidents in greater detail, we can observe that in most cases one of the contributory causes to a criticality accident was faulty management of fissionable materials. The ''over-all'' importance of the relation between safety and nuclear materials management should also be stressed. Although this management may not always form the basis of ''primary'' criticality control, it is still indispensable throughout any process since what is done in this respect in one section of a plant is of significance with regard to the safety of neighbouring sections, especially that concerned with waste processing. (author) [French] La production, la mise en oeuvre et la manutention de certaines matieres fissiles comportent un type de danger particulier qui est le risque de criticite. L'art de l'ingenieur est d'eviter ce risque, au moindre prix, sans trop gener le travail de production ou de transformation. Pour ecarter ce risque, il existe, en premiere approximation, trois methodes preventives; une limitation de la concentration des solutions, une limitation de la masse, un choix judicieux des geometries. La tendance est d'employer au maximum la troisieme methode, autrement: dit de fonctionner avec des systemes a securite inherente. Toutefois, les systemes a securite non inherente restent nombreux dans les installations nucleaires et le recours a l'une ou l'autre des deux premieres methodes devient necessaire. Ces methodes sont liees a la gestion des matieres nucleaires. Dans les installations ou sont manipulees de petites quantites de matieres fissiles, il est souvent possible d'assurer la securite nucleaire en admettant dans chaque salle une masse de matiere fissile inferieure a la masse ciritique minimale. Pour des installations plus importantes, un tel controle, qui repose entierement sur la gestion des matieres, devient impossible. L'auteur examine, dans le cas particulier d'une usine oe traitement de combustibles irradies par voie aqueuse (les combustibles sont a base d'uranium naturel), comment se presente la liaison entre gestion et securite nucleaire. Une telle usine comprend grossierement trois parties au point de vue du controle de la criticite: Dans la premiere partie, traitant des solutions assez diluees, le controle qui s'impose est celui de la concentration. Si ce controle est aise (analyse et compteurs neutrons), il est difficile de s'assurer qu'il ne se forme pas de depots: bien que l'experience ait montre qu'ils n'etaient pas tellement a craindre, le fait bien connu d'un bilan matieres deficitaire reste un souci en matiere de criticite. Dans cette partie, la gestion des matieres, encore imparfaitement realisee, est de premiere importance pour la securite. La deuxieme partie traite des solutions concentrees et des precipites humides. C'est le domaine de la geometrie sure. La gestion des matieres l'interesse moins directement mais reste un facteur de securite important (en cas d'intervention, de nettoyage des appareils, etc.). Un controle par la masse s'impose dans la troisieme partie qui traite des produits secs. La gestion ne presente pas de difficulte particuliere. A ce schema se superpose une partie moins spectaculaire mais qui sur le plan surete est de toute premiere importance: c'est la partie relative aux recyclages et au traitement des dechets. Il suffit de se rapporter a la liste des accidents de criticite survenus aux Etats-Unis pour constater que sur six accidents, cinq ont trait plus ou moins directement au traitement de dechets. Si l'on examine plus en detail ces accidents, on constate que dans la plupart des cas, parmi les causes qui se conjuguent pour creer un accident de criticite, l'une d'elles est un defaut dans la gestion des matieres fissiles. Il est bon enfin de souligner l'importance de la liaison entre securite et gestion des matieres nucleaires; en effet, si cette gestion n'est pas toujours la base du controle de la criticite, elle reste indispensable tout au long d'un procede, car la gestion des matieres dans une partie d'usine interesse la securite des parties voisines et tout specialement de la partie relative au traitement des dechets. (author) [Spanish] La produccion, el empleo y la manipulacion de ciertos materiales fisionables entranan el riesgo decriticidad. El ingeniero tiene que evitar este riesgo del modo mas economico posible y sin entorpecer demasiado las operaciones de produccion o de transformacion. Para ello puede hacer tres cosas: limitar la concentracion de las soluciones, limitar la masa o elegir juiciosamente las geometrias. La tendencia es emplear lo mas posible el tercer metodo, es decir, operar con sistemas de seguridad inherente. De todas formas, los sistemas de seguridad no inherente siguen siendo numerosos en las instalaciones nucleares y obligan a recurrir a uno u otro de los dos primeros metodos. Ambos van unidos a la administracion de los materiales nucleares. En las instalaciones donde los materiales fisionables se manipulan en pequenas cantidades se puede con frecuencia garantizar la seguridad nuclear admitiendo en cada sala una masa de materiales fisionables inferior a la masa critica minima. En instalaciones mas importantes esta forma de control, enteramente basada en la administracion de los materiales, resulta imposible. Examinemos las relaciones que existen entre la administracion y la seguridad nuclear en el caso especial de una planta de tratamiento por via acuosa de combustibles irradiados (combustibles a base de uranio natural). Desde el punto de vista del control de la criticidad, una planta de esta clase puede dividirse en tres partes: En la primera, donde se tratan soluciones bastante diluidas, lo que hay que controlar es la concentracion. Este control es facil (analisis y contadores neutronicos) pero resulta en cambio dificil asegurarse de que no se forman depositos: aunque la experiencia haya demostrado que no son muy peligrosos, el hecho bien conocido de un balance de materiales deficitario sigue siendo una preocupacion en lo que respecta a la criticidad. En esta primera parte, la administracion de los materiales, aun imperfecta, tiene una importancia primordial para la seguridad. En la segunda parte se tratan soluciones concentradas y precipitados humedos. Es la parte donde debe aplicarse una geometria segura. La administracion de los materiales tiene menos interes directo pero sigue siendo un factor importante de seguridad (en caso de intervencion, de limpieza de los aparatos, etc.). En la tercera parte, donde se tratan productos secos, es preciso controlar la masa. La administracion no presenta dificultades especiales. A este esquema se superpone una parte menos espectacular pero que desde el punto de vista de la seguridad tiene muchisima importancia: es la parte donde se efectuan los reciclados y el tratamiento de los desechos. Basta examinar la lista de los accidentes de criticidad en los Estados Unidos para comprobar que de cada seis, cinco estan mas o menos directamente relacionados con el tratamiento de desechos. Si examinamos estos accidentes con mas atencion comprobaremos que en la mayoria de los casos una de sus causas ha sido un defecto en la administracion de los materiales fisionables. Por ultimo, conviene subrayar la importancia 'global' de las relaciones que existen entre la seguridad y la administracion de los materiales nucleares; en efecto, si esta administracion no constituye siempre la base del control 'primario' de la criticidad, sigue siendo indispensable a lo largo de todo un proceso, ya que la administracion de los materiales en una parte de la planta repercute en la seguridad de las partes vecinas, en particular de la destinada al tratamiento de los desechos. (author) [Russian] Proizvodstvo, ispol'zovanie i obrabotka nekotoryh deljashhihsja materialov predstavljajut bol'shuju opasnost', osobenno opasnost', svjazannuju s kritichnost'ju. Umenie inzhenera zakljuchaetsja v tom, chtoby izbezhat' jetu opasnost' s naimen'shej cenoj i ne meshaja slishkom rabote, svjazannoj s proizvodstvom ili pererabotkoj jadernyh materialov. Dlja ustranenija jetoj opasnosti sushhestvujut,na pervyj vzgljad, tri profilakticheskih metoda: ogranichenie koncentracii rastvorov, ogranichenie massy, tshhatel'nyj vybor geometrij. Tendencija sostoit v maksimal'nom ispol'zovanii tret'ego metoda, inache govorja, v rabote s sistemami dopolnitel'noj avarijnoj zashhity. Odnako na jadernyh ustanovkah imeetsja mnogo sistem dopolnitel'noj avarijnoj zashhity, i primenenie togo ili drugogo iz dvuh metodov stanovitsja neobhodimym. Jeti metody imejut otnoshenie k obrashheniju s jadernymi materialami. Na ustanovkah, gde rabotajut s nebol'shimi kolichestvami deljashhihsja materialov, zachastuju mozhno obespechit' jadernuju bezopasnost', dopuskaja dlja kazhdogo pomeshhenija takuju massu deljashhegosja materiala, kotoraja nizhe minimal'noj kriticheskoj massy. V otnoshenii bolee krupnyh ustanovok podobnyj kontrol', kotoryj polnost'ju osnovan na obrashhenii s materialami, stanovitsja nevozmozhnym. Izuchim, kak vygljadit svjaz' mezhdu obrashheniem i jadernoj bezopasnost'ju na zavode po obrabotke obluchennogo topliva vodnym metodom (toplivo na osnove prirodnogo urana). Takoj zavod sostoit, v osnovnom, iz treh chastej s tochki zrenija kontrolja za kritichnost'ju. V pervoj chasti, gde obrabatyvajutsja dovol'no razbavlennye rastvory, neobhodim kontrol' za koncentraciej. Esli jetot kontrol' i udoben (analiz i nejtronnye schetchiki), to voznikaet trudnost' v ujasnenii togo, chto pri jetom ne obrazujutsja otlozhenija: hotja opyt i pokazal, chto ne sleduet bojat'sja jetih otlozhenij, no horosho izvestnym iz deficitnogo material'nogo balansa momentom javljaetsja zabota o kritichnosti. V jetoj chasti obrashhenie s materialami, eshhe ne polnost'ju dostignutoe, imeet pervostepennoe znachenie dlja bezopasnosti. Vo vtoroj chasti obrabatyvajutsja koncentrirovannye rastvory i syrye osadki. Geometrija materialov imeet zdes' osnovnoe znachenie. Obrashhenie s materialami imeet men'shee znachenie, no ostaetsja sushhestvennym faktorom bezopasnosti (v sluchae prinjatija special'nyh mer, chistki apparatury i t.p.). Kontrol' po masse osushhestvljaetsja v tret'ej chasti, gde obrabatyvajutsja suhie produkty. Obrashhenie ne predstavljaet soboj kakuju-libo osobuju trudnost'. Po jetoj sheme na pervoe mesto vydvigaetsja menee jeffektnyj moment, kotoryj, odnako, v plane bezopasnosti priobretaet pervostepennoe znachenie; jetot moment otnositsja k povtornym ciklam i k obrabotke othodov. Dostatochno soslat'sja na perechen' avarij, svjazannyh s kritichnost'ju, imevshih mesto v Soedinennyh Shtatah, chtoby ukazat' na to, chto iz shesti avarij pjat' imejut bolee ili menee prjamoe otnoshenie k obrabotke othodov. Esli my bolee podrobno izuchim jeti avarii, to otmetim, chto v bol'shinstve sluchaev odnoj iz prichin, kotorye privodjat k avarijam, svjazannym s kritichnost'ju, javljajutsja nedostatki v obrashhenii s deljashhimisja materialami. Sleduet takzhe podcherknut' ''global'noe'' znachenie svjazi mezhdu bezopasnost'ju i obrashheniem s jadernymi materialami; dejstvitel'no, esli jeto obrashhenie ne vsegda javljaetsja osnovoj ''pervichnogo'' kontrolja za kritichnost'ju, to ono neobhodimo na protjazhenii vsego processa, poskol'ku obrashhenie s materialami na odnoj chasti zavoda imeet otnoshenie k bezopasnosti sosednih chastej i, prezhde vsego, toj chasti, gde obrabatyvajutsja othody. (author)

Graft Polymerization of Styrene to Polyethylene; Polymerisation par greffage du styrene sur des pellicules de polyethylene; Privitaya polimerizatsiya stirola k poliehtilen; Polimerizacion por injerto de estireno en polietileno

Energy Technology Data Exchange (ETDEWEB)

Silverman, J.; Srinivasan, S. I.; Phalangas, C. J. [Department of Chemical Engineering, University of Maryland, College Park, MD (United States)

1963-11-15

takzhe skorost' prevrashcheniya stirola v gomopolimer v suspenziyakh legkoj melkokristalliches koj kal'tsinirovannoj sody. Dlya opredeleniya kolichestva okklyudirovannogo gomopolimera provedeno issledovanie pod mikroskopom privitoj plenki. Rezul'taty pokazyvayut, chto bol'shaya chast' prirosta vesa v obraztsakh plenki usloalena okklyudirovannym gomopolimerom. V ehksperimentakh s legkoj melkokristallicheskoj kal'tsinirovannoj sodoj, pri kotorykh prirost vesa v znachitel'noj stepeni ob{sup y}asnyaetsya privitym sopolimerom, uvelichenie vesa nakhoditsya v primernoj linejnoj zavisimosti ot dozy, a skorost' reaktsii pochti proportsional'na kornyu kvadratnomu iz moshchnosti gamma-oblucheniya. Nizkaya ehnergiya aktivatsii dlya. skorosti reaktsii isklyuchaet vozmozhnost' kontrolya diffuzii v legkoj melkokristallicheskoj kal'tsinirovannoj sode i v tonkikh plenkakh pri moshchnostyakh oblucheniya nizhe 10{sup 5} r/hr. Pri ehksperimentakh v legkoj melkokristallicheskoj kal'tsinirovannoj sode pri temperature 18{sup o}C i moshchnosti dozy 7,2 x 10{sup 4} r/hr skorost' obrazovaniya gomopolimera takaya zhe, kak i v sluchae obrazovaniya polimera v chistoj stirole. Ehnergiya aktivatsii, ravnaya 3,5 kkal/moya{sup ,} pochti vdvoe men'she velichiny''dlya chistogo monomera. (author)

Radioactive Metrology Methods in the USSR; Methodes de metrologie de la radioactivite en URSS; Metody metrologii radioaktivnosti v SSSR; Metodos de Metrologia de la Radiactividad Aplicados en la Union de Republicas Socialistas Sovieticas

Energy Technology Data Exchange (ETDEWEB)

Aglintsev, K K; Bochkarev, V V; Grablevskij, V N; Karavaev, F M

1960-06-15

actividad de estos patrones son 10{sup -11} y 5 equivalentes gramo del Ra, respectivamente . Las fuentes {gamma} de control se preparan partiendo de los mismos radionuclidos que las fuentes y modelo. Sus actividades abarcan un intervalo muy amplio y las fuentes presentan formas y dimensiones sumamente diversas. Por ultimo, se utilizan dos clases de fuentes neutronicas modelo Ra-{alpha}-Be (con un contenido de 1 a 1000 mg de Ra) y Pu-{alpha}-Be (conteniendo de 0.01 a 15 g de Pu). Las fuentes Ra-{alpha}-Be consisten en una mezcla comprimida de RaBr{sub 2} y de Be en polvo, siendo la razon ponderal Ra/Be igual a 1/6. En cuanto a las fuentes Pu-{alpha}-Be, se preparan con una aleacion (PuBe{sub 13}) de estos dos metales. (author) [Russian] Avtory opisyvayut metody, primenyaemye v SSSR, i, v chastnosti, v institute metrologii im. Mendeleeva (Leningrad) dlya vosproizvodstv a pri pomoshchi standartnykh apparatov edinits izmereniya, ispol'zuemykh v radioaktivnosti (kyuri, gramm-ehkvivalen t radiya, rentgen, rad). Dlya radionuklido v v Sovetskom Soyuze proizvodyatsya istochnikiehtalony dvukh vidov: 1. Model'nye istochniki dlya sravnitel'nog o ehtalonirovani ya drugikh radioaktivnykh preparatov, a takzhe dlya kalibrovki radiometricheski kh priborov i kontrol'nykh priborov za izlucheniem; 2. Kontrol'nye istochniki, sluzhashchie isklyuchitel'n o dlya proverki raboty i kontrolya za vosproizvodimost' yu ukazanij izmeritel'ny kh priborov. Model'nye a-istochniki prigotovlyayuts ya pri pomoshchi ehlektrolitiche - skogo osazhdeniya na platine dolzhnym obrazom vybrannykh izluchatelej (estestvennyj uran, uran-233, plutonij-239, ameritsij-241). EHti istochniki mogut obespechivat' aktivnost' ot do 10{sup 6} raspadov v minutu. Kontrol'nye {alpha}-istochniki prigotovlyayuts ya putem ehlektroliticheskog o osazhdeniya plutoniya-239 v vide sloya s plotnost'yu ot 3 X 10-{sup 9} do 0,7 mg/em2, chto sootvetstvuet aktivnosti ot 10 do 10{sup 8} raspadov v minutu. Model'nye {beta

Operating Experience in Nuclear Power Plants with Boiling-Water Reactors; Experience acquise dans l'exploitation des reacteurs a eau bouillante; Opyt ehkspluatatsii kipyashchago reaktora; Experiencia adquirida con la explotacion de reactores de agua hirviente

Energy Technology Data Exchange (ETDEWEB)

Ascherl, R. J. [General Electric Company, San Jose, CA (United States)

1963-10-15

, ''Rejnish vestfalishes ehlektritsitetsverk und bajernverk'', Kal'-na-Majne, Zapadnaya Germaniya. Rabochaya kharakteristika kipyashchego reaktora atomnoj ehlektrostantsii pri obychnom rezhime raboty v kommunal'noj ehnergosisteme ochen' khoroshaya. Koehffitsient ispol'zovaniya i moshchnosti reaktora i ehlektrostantsii daet tverdoe osnovanie polagat', chto ehlektrostantsii s kipyashchimi reaktorami yavlyayutsya nadezhnymi s tochki zreniya ikh rabochej kharakteristiki. V techenie 1963 goda budut vvedeny v stroj chetyre dopolnitel'nye ehlektrostantsii s kipyashchimi reaktorami: atomnaya ehlektrostantsiya v Big Rok Pojnt, ''Kons'yumers pauehr kompani'', Sharl'vua, Michigan, atomnaya ehnergeticheskaya ustanovka v KHamboldt Bej, ''Pasifik gaz ehnd ehlektrik kompani'', Yurika, Kaliforniya, atomnaya ehlektrostantsiya v Garig'yano, Natsional'noe obshchestvo po atomnoj ehnergii, Skauri, Italiya,i Yaponskij demonstratsionnyj ehnergeticheskij reaktor. Yaponskij nauchno-issledovatel'skij institut po atomnoj ehnergii, Tokai-Mura, Yaponiya. Pusk i pervonachal'naya ehkspluatatsiya ehtikh ehlektrostantsij podtverzhdayut predpolozhenie o nadezhnosti ikh raboty, chto uzhe prodemonstrirovano atomnymi ehlektrostantsiyami v Drezdene, Kale i Vallesitose. Rabochaya kharakteristika atomnykh ehlektrostantsij v Drezdene, Kale i Vallesitose yavlyaetsya naglyadnym dokazatel'stvom stabil'nosti i bezopasnosti kipyashikh reaktorov. Krome togo, urovni radiatsii na samoj ehlektrostantsii i v okruzhayushchej srede znachitel'no nizhe predelov, ustanovlennykh litsenziyami na ehkspluatatsiyu. Podtverdilis' prostota i legkost' ehkspluatatsii kipyashchikh reaktorov. Kharakteristika kontrolya za nagruzkoj u kipyashchego reaktora s dvojnym tsiklom Drezdenskoj ehlektrostantsii okazalas' ochen' khoroshej. Krupnye i nebol'shie raboty po ukhodu i remontu mogut osushchestvlyat'sya obychnymi remontnymi gruppami bez vrednykh posledstvij ili bez limita vremeni, svyazannymi s soobrazheniyami radioaktivnogo oblucheniya. V

Gas-flow detector for uranium contamination on finned-can surface of a reactor fuel; Detecteur a courant gazeux pour deceler la contamination en uranium des nervures des gaines de combustible nucleaire; Gazopotochnyj detektor zagryazneniya uranom rebristoj poverkhnosti obolochki reaktornykh teplovydelyayushchikh ehlementov; Detector de flujo gaseoso para medir la contaminacion de uranio en la superficie de la vaina de aletas de los elementos combustibles para reactores

Energy Technology Data Exchange (ETDEWEB)

Miwa, H; Shiojiri, T; Maeda, Y [Kobe Kogyo Corporation, Okubo, Akashi, Hyogo (Japan)

1962-04-15

stavitsya pod otritsatel'noe napryazhenie. Prostranstvo mezhdu toplivnym ehlementom i setkoj sluzhit ulovitel'noj ionizatsionnoj kameroj. Setka sostoit iz parallel'nykh vol'framovykh provodov, zazemlennykh i raspolozhennykh tsilindricheski vokrug toplivnogo ehlementa. Kollektory sostoyat iz 16-ti tonkikh vol'framovykh provolochek, skonstruirovannykh analogichno setke, no kazhdaya provoloka izolirovana ehlektricheski ot drugikh. Vse kollektory soedineny mezhdu soboyu cherez soprotivleniya v 50 kiloomov i cherez pitayushchee soprotivlenie vklyucheny v set' s polozhitel'nym tokom vysokogo napryazheniya. Prostranstvo mezhdu setkoj, kollektorami i katodom sluzhit v kachestve gazovoj umnozhitel'noj kamery, podobno obychnomu proportsional'nomu schetchiku. Kazhdoe soprotivlenie v 50 kiloomov otdelyaet parazitnuyu emkost' podklyuchennogo kollektora ot drugikh emkostej. Vykhodyashchij iz detektora signal napravlyaetsya v usilitel' toka s malym vkhodnym kompleksnym soprotivleniem. Maloe vkhodnoe kompleksnoe soprotivlenie snizhaet takzhe vrednoe vliyanie parazitnoj emkosti vkhodyashchej skhemy. Ehto vedet k polucheniyu khoroshego sootnosheniya signal-pomekha i povyshaet chuvstvitel'nost' obnaruzheniya al'fa-chastits. Do proizvodstva izmerenij v schetchike predvaritel'no sozdaetsya vakuum otkachivaniem pri pomoshchi rotatsionnogo nasosa, posle chego v nego nagnetaetsya gaz PR (90% argona i 10% metana). Blagodarya ispol'zovaniyu ehtogo novogo oborudovaniya nam udalos' obnaruzhit' al'fa-chastitsy, ispuskavshiesya 1 x 10{sup -5} g prirodnogo urana, zagryaznyavshego rebristuyu poverkhnost' obolochki reaktornykh teplovydelyayushchikh ehlementov tipa Kvl'der-Kholl; vse teplovydelyayushchie ehlementy reaktora JRR-3 budut provereny ehtim schetchikom. (author)

Analyser for fast single events; Analyseur d'evenements rapides simples; Analizator bystrykh odnokratnykh yavlenij; Analizador de sucesos rapidos no recurrentes

Energy Technology Data Exchange (ETDEWEB)

Sedlmeyer, J W; Patten, R B; Fussell, L Jr [Edgerton, Germeshausen And Grier, Inc., Las Vegas, NV (United States)

1962-04-15

otrezki dostigaetsya pri pomoshchi vremennogo selektornogo impul'sa i intervala vremeni mezhdu otborom obraztsov, prichem i tot i drugoj mogut regulirovat'sya nezavisimo drug ot druga, nachinaya priblizitel'no s 4 nanosekund. Intervaly vremeni mogut zadavat'sya v nelinejnom poryadke, a razbros mezhdu nimi ne prevyshaet 0,5 nanosekund. Do nastoyashchego vremeni skorost' otvetnoj reaktsii ogranichivaetsya kharakteristikami dioda. Kazhdoe otobrannoe napryazhenie rasshiryaetsya v konture, kotoryj sokhranyaet amplitudu ehtogo napryazheniya. Udalos' osushchestvit' rasshirenie po vremeni v 10{sup 8} raz s sokhraneniem khoroshej ustojchivosti. Tochki pokazanij mogut soobshchat'sya i peredavat'sya po otkrytomu provodu v nizkochastotnoe registriruyushchee ustrojstvo, oni mogut byt' prevrashcheny v tsifrovye dannye dlya bystroj ikh obrabotki s pomoshch'yu obychnogo oborudovaniya; krome togo, ili vmesto ehtogo, oni mogut byt' dany vizual'no. Analizator imeet preimushchestva po sravneniyu s vysokoskorostnoj ostsiloskopiej, kogda trebuetsya provodit' individual'nyj analiz bol'shogo chisla odnokratnykh perekhodyashchikh signalov; ehto trebuetsya pri izuchenii kolebanij otvetnykh reaktsij sistem ili pri proizvodstvennykh ispytaniyakh komponentov. Analizator imeet preimushchestva, kogda analiz dannykh dolzhen proizvodit'sya neposredstvenno za poyavleniem signala; otpadaet neobkhodimost' proyavlyat' plenki ili prochityvat' ikh. Analizator udoben takzhe v tekh sluchayakh, kogda schetno-analiziruyushchij tsentr raspolozhen daleko ot mesta poyavleniya signala. EHtot metod shiroko primenyaetsya v oblasti yadernoj ehnergii. Metod pul'siruyushchikh nejtronov mozhet byt' primenen dlya bystrogo izucheniya kolebanij rezhima reaktorov i podkriticheskikh sborok. Mogut byt' opredeleny parametry nakopleniya i raspada detektorov i odnovremenno provodit'sya analiz statisticheskikh dannykh i kolebanij. Mozhet izmeryat'sya forma impul'sov radiatsionnykh voln, proizvodimykh yadernymi uskoritelyami. S

Radioautography in the Study of Radioisotopically-Tagged Substances in Insect Control; L'autoradiographie dans l'etude de substances marquees au moy en de radioisotopes utilisees dans la lutte contre les insectes; Primenenie radioavtografii pri izuchenii substantsij, mechennykh radioizotopami, v bor'be s nasekomymi; La autorradiografia en el estudio de las sustancias marcadas con radioisotopos utilizadas en la lucha contra los insectos

Energy Technology Data Exchange (ETDEWEB)

Joftes, D. L. [New England Deaconess Hospital, Boston, MA (United States)

1963-09-15

preparatov yavlyaetsya pogruzhenie ikh v rasplavlennuyu massu fotoehmul'sii v temnote i zatem ochistka nizhnej poverkhnosti predmetnogo stekla. Posle ehtogo predmetnye stekla pomeshchayutsya v temnuyu kameru s sukhoj inertnoj atmosferoj i vyderzhivayutsya tam v techenie vremeni, opredelyaemogo ehmpiricheski. Zatem predmetnye stekla proyavlyayutsya, tshchatel'no promyvayutsya, i na nikh nadevayutsya zashchitnye stekla. Posle ehtogo predmetnye stekla gotovy dlya issledovaniya, tochno tak zhe, kak obychnye gistologicheskie preparaty pri vsekh uvelicheniyakh. Neznachitel'noe smeshchenie fokusa vverkh vvodit v pole zreniya radioavtograficheskij obrazets, kotoryj mozhet byt' takim obrazom legko izuchen pri sravnenii s tkan'yu. Daetsya podrobnoe opisanie metodov i neobkhodimogo laboratornogo oborudovaniya. (author)